Text

Attachment 13, Browns Ferry Unit 1 - Technical Specification Change 467, ANP-2864(NP), Revision 2, Reload Safety Analysis Report
	ML093140265
Person / Time
Site:	Browns Ferry
Issue date:	10/31/2009
From:	; AREVA NP
To:	; Office of Nuclear Reactor Regulation
References
	L32 091019 801, TS 467 ANP-2864(NP), Rev 2
	Download: ML093140265 (285)
	v • d • e

ATTACHMENT 13 ATTACHMENT 13 Browns Ferry Nuclear Plant (BFN)

(BFN)

. Unit 1 Technical Technical Specifications Specifications (TS) Change 467 Revision of Technical Technical Specifications Specifications to allow allow utilization NP utilization of AREVA NP fuel and associated associated analysis methodologies methodologies Report Reload Safety Analysis Report Attached Attached is the non proprietary proprietary version of the Reload Reload Safety Safety Analysis report for 120%

120%

OLTP OL TP conditions.

L32 091019 801 r- 0 0 C

ANP-2864(NP) z 0 Revision 2 CD CD U)

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AREVA NP Inc.

ANP-2864(NP)

Revision 2 Browns Ferry I Cycle 9 Ferry Unit 1 Reload Reload Safety Analysis Analysis

AREVA AREVA NP Inc. lric.

ANP-2864(NP)

AN P-2864(N P)

INC.PROPRIETARY PROPRIETARY This Thisdocument documentandandany any information informationcontained contained herein, herein. isisthe theproperty propertyofofAREVA AREVANP NPInc.

Inc. (AREVA (AREVANP) NP)and and isistotobe beconsidered consideredproprietary proprietaryand andconfidential confidentialand and may may not notbe be reproduced reproducedororcopied copied in inwhole wholeororin in part.

part. Nor Normayit may'~ be be fumished fumishedtotoothers others without withoutthethe express expresswritten writtenconsent consentand andpermission permissionofofAREVA AREVANP,NP.nor normay mayititbe be used in any way that is or may be detrimental to AREVA NP. This document and any copies that used in any way that is or may be detrimental to AREVA NP. This document and any copies that may have beenmade may have been made must must be be returned returnedtotoAREVA AREVANP NPupon upon request request

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Analysis Reload Safety Analysis Page Page i Nature of Changes Changes Item Page Description and Justification Justification

1. 4-4 Corrected core pressure uncertainty.

2. 7-12-7-15 7-12-7-15 Corrected statepoint in in Figures 7.5-7.8.

AREVA AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Reload Safety Analysis Analysis Page iiii Page Contents Contents 1 .0 1.0 Intro d u ctio n ....................................................................................................................

Introduction ............. ;...................................................................................................... 1-1 2.0 Disposition of Events ......................................................................................................

.............................................. 2-1 3.0 Mechanical Design Mechanical Design A nalysis ..........................................................................................

Analysis .......................................................................................... 3-1 4.0 Thermal-Hydraulic Thermal-Hydraulic Design Analysis : ........ .'........................... ,......... 4-1 Analysis ................................ 4-1 4.1 Thermal-Hydraulic Thermal-Hydraulic Design and Compatibility .................................................... .4-1 Compatibility ..................................................... 4-1 4.2 4.2 Safety Limit MCPR Analysis ...............................................................................

............................................................................... 4-1 4.3 Core Hydrodynamic Hydrodynamic Stability .............................................................................

.............................................................................. .4-2 4-2 5.0 Anticipated Operational Operational Occurrences ............................................................................

Occurrences ............................................................................ 5-1 5.1 S ystem Transients System T ransients ..............................................................................................

.............................................................................................. 5-1 5.1.1 Load Rejection No Bypass (LRNB) (LRNB) ........................

............................................. :........ 5-3 5.1.2 Turbine Trip No Bypass (TTNB) ...........................................................

................................................... *....... 5-3 5.1.3 5.1.3 Feedwater Controller Feedwater Controller Failure (FWCF) ..................................................

.................................................. 5-4 5.1.4 5.1.4 Loss of Feedwater Feedwater Heating ..............................

.................................................................. 5-5

.5.1.5 5.1.5 Control Rod Withdrawal Error ..............................................................

Error .............................................................. 5-5 5-5 5.2 Slow Flow Runup Analysis ................................................................................

................................................................................. 5-6 5.3 5.3 Out-of-Service Scenarios Equipment Out-of-Service .................................................................

Scenarios ................................................................. 5-7 5-7 5.3.1 5.3.1 ...............................................

TBVOOS .................................. ;........................................................... 5-8 5.3.2 5.3.2 EO C -R PT-O O S ............

EOC-RPT-OOS ............ ~I.......................................................................

....................................................................... 5-8 5-8 5.3.3 5.3.3 ........................................

FHOOS ................................................................................................. 5-8

.3.4 55.3.4 P LU O O S ..............................................................

PLUOOS ..............................................................................................

............................... 5-9 5.3.5 Combined EOC-RPT-OOSEOC-RPT-OOS and TBVOOS ............................................

............................................ 5-9 5.3.6 Combined EOC-RPT-OOSEOC-RPT-OOS and FHOOS ..............................................

.............................................. 5-9 5.3.7 Combined EOC-RPT-OOSEOC-RPT-OOS and PLUOOS ............................................

PLUOOS ............................................ 5-9 5.3.8 Combined Combined TBVOOS and FHOOS ........................................................

FHOOS ........................................................ 5-9 5-9 5.3.9 Combined Combined TBVOOS TBVOOS and PLUOOS ........................

PLUOOS .................................................... 5-10 5-10 5.3.10 Combined ......................................................

Combined FHOOS and PLUOOS ...................................................... 5-10 5-10.

5.3.11 Combined EOC-RPT-OOS, Combined EOC-RPT-OOS, TBVOOS, TBVOOS, and FHOOS ..........................

FHOOS .......................... 5-10 5-10 5.3.12 Combined EOC-RPT-OOS, TBVOOS, Combined EOC-RPT-OOS, TBVOOS, and PLUOOS ........................ ........................ 5-10 5-10 5.3.13 Combined EOC-RPT-OOS, Combined EOC-RPT-OOS,FHOOS, FHOOS, and PLUOOS ............

............... ;.......... 5-10 5-10 5.3.14 Combined Combined TBVOOS, TBVOOS, FHOOS, FHOOS, and PLUOOS ....................................

.................................... 5-11 5.3.15 Combined EOC-RPT-OOS, TBVOOS, Combined EOC-RPT-OOS, TBVOOS, FHOOS, and P LUO O S ..................................................

PLUOOS ..................................... 5-1

.................................... ,........................................................ 5-111 5.3.16 Single-Loop Single-Loop Operation .......................................................................

Operation ....................................................................... 5-11 5-11 5.4 5.4 Licensing Pow er Shape ....................................................................................

Licensing Power Shape .................................................................................... 5-12 5-12 6.0 Postulated Accidents Postulated ..................................................

Accidents ...................................................................................................... 6-1 6.1 Loss-of-Coolant-Accident (LOCA) ................................................................

Loss-of-Coolant-Accident .................................................. *.................... :..... 6-1 .

6.2 Control Rod Drop Accident ...................................................................

Accident (CRDA) .............................................. :.................... 6-2 6.3 Fuel and Equipment Equipment Handling Handling Accident .............................................................

Accident ............................................................. 6-3 6.4 Fuel Loading Error (Infrequent (Infrequent Event) ................................................................

................................................................ 6-3 6.4.1 M islocated Fuel Bundle ........................................................................

Mislocated ........................................................................ 6-3 6-3 6.4.2 6.4.2 Misoriented Fuel Bundle ................................

Misoriented Fuel Bundle ....................................................................... 6-3 7.0 S pecial Analyses Special Analyses ............................................................................................................

........................................................................................................... 7-1 7.1 / ASMEASME Overpressurization Overpressurization Analysis ....................................................................

Analysis .................................................................... 7-1 AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 .* Revision 2 Reload Reload Safety Safety Analysis Analysis Page iii Page iii 7.2 ATWS TW S Event Evaluation ..................................................................................... 7-2 Evaluation ..................................................................................... 7-2 7.2.1 ATWS Overpressurization Analysis A TWS Overpressurization .....................................................

Analysis ..................................................... 7-2 7-2 7.2.2 Long-Term 7.2.2 Long-Term Evaluation Evaluation ..........................................................................

.......................................................................... 7-2 7-2 7.3 Standby Liquid Control Control System ..........................................................................

....................................... 7-4 7.4 7 .4 Fuel F ue l Criticality ..................................................................................................... 7-4 C riticality .....................................................................................................

8.0 Operating Operating Limits and COLR Input .................................................................................

.................................................................................. 8-1 8.1 8 .1 MCPR MC PR Limits ...................................................................................................... 8-1 Lim its ......................................................................................................

8.2 LHGR Limits .......................................................................................................

.............................................. 8-1 8.3 MA P LH G R Lim MAPLHGR Limits its ...............................................................................................

............................................................................................... 8-2 99.0

.0 R efe re nce s .....................................................................................................................

References ................................................................................................................... 9-1 Appendix A Operating Limits and Results Comparisons ........................

Comparisons ...................................... ~ ............. A-1 Tables Tables 1.1 ..........................................................................

EOD and EOOS Operating Conditions .......................................................................... 1-2 2.1 Disposition of Events Summary Summary for Browns ..............................................

Browns Ferry Unit 1 .............................................. 2-3 2-3 2.2 Disposition of Operating Flexibility Flexibility and EOOS Options on Limiting Events ................. ................. 2-12 2-12 2.3 Methodology Methodology and Evaluation Evaluation Models Models for Cycle Specific Specific Reload Analyses Analyses .... .................. 2-13

.............. 2-13 4.1 Fuel- and Plant-Related Fuel- Plant-Related Uncertainties Uncertainties for Safety Limit MCPR Analyses ....................... .......... 4-4 4.2 Results Summary for Safety Limit MCPR Analyses .......................................................

......................... 4-5 4-5 44.3

.3 O P R M Setpoints OPRM S etpoints ............................................................................................................

.............................................................................................................4-6 4.4 BSP Endpoints for Browns Ferry Unit 1 Cycle 9 ...........................................................

........................................................... 4-7

.4-7 5.1 Exposure Basis for Browns Exposure Browns Ferry Unit 1 Cycle 9 Transient .......................

Transient Analysis ........................... 5-13 5-13 5.2 Scram Scram Speed Speed Insertion Times Tim es .....................................................................................

..................................................................................... 5-14 5-14 5.3 NEOC Base Case LRNB Transient Results ................................................................

Results ................................................................. 5-15 5-15 5.4 EOCLB Base Case LRNB LRNB Transient Transient Results ............ ..............................................................

~ ................................................... 5-165-16 5.5 NEOC Base Case FWCF Transient Transient Results Results..................................................................5-17

................................................................ 5-17 5.6 EOCLB Base Case FWCF Transient Results ..............................................................

............................. 5-18 5-18 5.7 Loss of Feedwater Heating Transient Analysis Results ...................... ..................... :...... ;......... :....... 5-19 5-19 5.8 Control Control Rod Withdrawal Withdrawal Error Error ACPR

~CPR Results Results...............................................................

............................................................... 5-20 5.9 Operability Requirements RBM Operability Requirements ....................................................................................

.................................................................................... 5-21 5.10 Flow-Dependent MCPR Results .................................................................................

Flow-Dependent ................................................................................ 5-22 5.11 Licensing Licensing Basis Core Average Axial Power Profile .....................................................

..................................................... 5-23 AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 '.,.- Revision 2 Reload Safety Analysis Page iv iv 7.1 . ASME Overpressurization Overpressurization Analysis Analysis Results ........................................

.............................. :.......................... 7-5 7-5 7.2 A TWS Overpressurization ATWS Overpressurization Analysis Results ..................................................................

.................................................................. 7-6 7-6 7.3 [......................... 7-7

] ......................... 7-7 8.1 MCPR MCPRpp Limits for NSS Insertion ................................................

Insertion Times BOC to NEOC .................................................. 8-3 8.2 MCPR MCPRpp Limits for TSSS Insertion Insertion Times BOC to NEOC NEOC... ................................................

............................................. 8-7 8.3 MCPRpp Limits for NSS Insertion MCPR Insertion Times BOC to EOCLB; ............................................. 8-11 EOCLB- ............................................. 8-11 8.4 MCPR MCPRpp Limits for TSSS Insertion Insertion Times BOC to EOCLB .................... ............................................ 8-15 8-15 8.5 MCPRpp Limits for NSS Insertion MCPR Insertion Times BOC to FFTRlCoastdown FFTR/Coastdown ..............................

.............................. 8-19 8-19 8.6 MCPR MCPRpp Limits for TSSS Insertion Insertion Times BOC to FFTRiCoastdown FFTR/Coastdown ............................

............................ 8-22 8.7 Flow-Dependent Flow-Dependent MCPR Limits ATRIUM-10 ATRIUM-10 and GE14 GE14 Fuel. ....................................... 8-25 Fuel ........................................

8.8 . ATRIUM-1 ATRIUM-100 Steady-State .................................................................... ~ ...... 8-26 Steady-State LHGR Limits ...............................................................

8.9 ATRIUM-10 LHGRFACp ATRIUM-10 LHGRFACp Multipliers for NSS/TSSS NSSITSSS Insertion Insertion Times All Cycle C ycle 9 Exposures ....................................................................................................... 8-27 E xposures .......................................................................................................

8.10 GE14 LHGRFAC LHGRFACpp Multipliers for NSSITSSS NSS/TSSS Insertion Times All Cycle Cycle.99 Exposures ....................................................................................................................8-28 E xposu re s ................................................................................................................... 8-2 8 8.11 ATRIUM-10 ATRIUM-10 LHGRFAC LHGRFACff Multipliers All Cycle 9 Exposures .........................................

.......................................... :8-298-29 8.12 GE14 LHGRFAC LHGRFACff Multipliers Multipliers All Cycle 9 Exposures ...................................................

................................................... 8-30 8.13 ATRIUM-10 ATRIUM -10 MAPLHG MAPLHGR R Limits .................................................................................... ~8-31 Lim its .................................................................................... 8-31 Figures Figures 1.1 Browns Ferry Browns Power/Flow Map - EPU/MELLLA Ferry Power/Flow ..... :...................................................... 1-3 EPU/MELLLA ...........................................................

5.1 EOCLB LRNB at 100P/105F 1OOP/1 05F - TSSS Key Parameters ...............................................

Parameters ................................................. 5-24 5-24 5.2 EOCLB EOCLB LRNB at 1 00P/1 05F - TSSS Sensed 1OOP/1 Sensed Water Level ........................................ 5-25 Level ......................................... 5-25 5.3 EOCLB EOCLB LRNB at 100P/105F 10OP/105F -TSSS ...........................................

-TSSS Vessel Pressures ............................................. 5-26 5.4 EOCLB EOCLB FWCF at 100P/105F looP/1 05F - TSSS Key Parameters ...............................................

Parameters ............................................... 5-27 5.5 EOCLB FWCF at 1 1OOP/1 ........................................ 5-28 00P/1 05F - TSSS Sensed Water Level ........................................ 5-28 5.6 EOCLB FWCF at 100P/105F ............................................ 5-29 1OOP/1 05F - TSSS Vessel Pressures ............................................

7.1 MSIV Overpressurization Event at 1102P/105F MSIV Closure Overpressurization 02P/1 05F - Key Parameters Parameters ...................

................... 7-8 7-8 7.2 Overpressurization Event at 102P/105F MSIV Closure Overpressurization MSIV 102P/105F - Sensed Sensed Water Water Level .............................................................: ................................................................. 77-9 L e v e l................................................................................................................................ -9 7.3 Overpressurization Event at 1102P/105F MSIV Closure Overpressurization 02P/1 05F - Vessel Pressures ............................................... :....................................................................... 7-10 P re ssu re s ...................................................................................................................... 7-10 AREVA NP Inc.Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Page vv 7.4 MSIV Closure Overpressurization Event at 102P/105F - Safety/Relief 7.4 MSIV Closure Overpressurization Event at 102P/105F - Safety/Relief Valve Flow R Valve ates ................................

Rates ........................................................................................................

........................................................................ 7-11 7-1*1 7.5 PRFO ATWS Overpressurization Overpressurization Event at 100P/99F 100P/99F - Key Parameters Parameters ....................

.................... 7-12 7-12 7.6 PRFO ATWS Overpressurization Overpressurization Event at 100P/99F 100P/99F - Sensed Water Le v e l........................

Level .............................................................................................................................

....................................................................................................7-13 7 -13 7.7 PRFO ATWS Overpressurization Overpressurization Event at 1OOP/99F- 100P/99F - Vessel Pressures .................. .............. : ... 7-14 7-14 7.8 PRFO ATWS Overpressurization Overpressurization Event at 10OP/99F Safety/Relief 100P/99F - Safety/Relief V alve Flow Rates Valve* R ates .........................................................................................................

..........................................................................................................7-15 7-15 AREVA NP Inc.

ANP~2864(NP)

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Analysis Reload Safety Analysis Page vi Nomenclature Nomenclature 2PT two pump triptrip ADS ADS depressurization system automatic depressurization automatic AOT AOT abnormal operational transient abnormal transient APLHGR APLHGR average planar linearlinear heat generation generation rate rate ARO ARO all control rods out all ASME ASME American SOciety Mechanical Engineers Society of Mechanical Engineers AST alternate alternate source term ATWS ATWS anticipated transient without scram anticipated ATWS-PRFO ATWS-PRFO anticipated transient without scram anticipated scram pressure regulator failure open ATWS-RPT ATWS-RPT anticipated anticipated transient without scram scram recirculation recirculation pump trip trip BF1 Browns Browns Ferry Unit 1 BLEU blended low enriched uraniumuranium BOC beginning-of-cycle beginning-of-cycle BPWS BPWS banked position withdrawal sequence banked sequence*

BSP BSP backup backup stability stability protection BWR BWR boiling water reactor ,

BWROG BWROG Boiling Water Reactor Owners Owners Group Group CAD atmosphere dilution containment atmosphere dilution CFR Code of Federal Regulations Regulations COLR COLR core operating operating limits report CPR critical power ratio power ratio CRDA accident control rod drop accident

'CRWE

'CRWE control rod withdrawal control withdrawal error DIVOM delta-over-initial delta-over-initial CPR versus oscillation magnitude oscillation magnitude ECCS ECCS emergency emergency core coolingcooling system EFPD effective effective full-power daysdays EFPH .effective effective full-power full-power hours EFPY EFPY effective effective full-power years*

years EOC EOC end-of-cycle end-of-cycle EOCLB end-of-cycle end-of-cycle licensing basis licensing basis EOC-RPT-OOS end-of-cycle EOC-RPT-OOS recirculation pump trip out-of-service end-of-cycle recirculation out-of-service EOD extended extended operating operating domain EOFP EOFP end of full power power EOOS EOOS equipment equipment out-of-service out-of-service EPU extended extended power uprate FFTR FFTR feedwater temperature

. final feedwater temperature reduction FHOOS FHOOS feedwater heaters out-of-service out-of-service FSAR final safety analysis report FW FW feedwater FWCF FWCF controller failure feedwater controller failure GE GE General Electric General Electric GNF GNF Global Nuclear Fuels Fuels AREVA NP Inc.

Inc.

ANP-2864(NP)

' . Browns Ferry Ferry Unit 1 Cycle 9 Hevision2

,Revision 2 Reload Safety Safety Analysis Analysis Page vii Page Nomenclature Nomenclature (Continued)

(Continued)

HCOM hot channel channel oscillation magnitude magnitude HFR HFR heat flux ratio HPCI high pressure coolant injection coolant injection ICF ICF increased core flow increased flow IHPS IHPS inadvertent HPCI pump start inadvertent IORV inadvertent opening of

. inadvertent otaa relief valve LFWH loss of feedwater feedwater heating heating LHGR LHGR generation rate linear heat generation rate .

LHGRFACf LHGRFACf flow-dependent linear heat generation flow-dependent generation rate multipliers multipliers LHGRFAC p LHGRFACp power-dependent linear power-dependent linear heat heat generation generation rate multipliers multipliers LOCA loss-of-coolant accident loss-of-coolant accident LOFW loss of feedwater flow flow

.LPRM LPRM local power range range monitor monitor LRNB LRNB generator load rejection with no bypass generator bypass MAPLHGR MAPLHGR maximum average average planar planar linear heat generation generation rate MCPR MCPR minimum critical power ratio ratio MCPRf MCPRf flow-dependent minimum critical power ratio flow-dependent ratio MCPRp MCPRp power-dependent minimum power-dependent minimum critical powerpower ratio ratio MELLLA MELLLA maximum extended maximum extended load line limit analysis analysis MSIV MSIV main steam isolation isolation valve valve MSRV main steam relief valve valve MSRVOOS MSRVOOS main steam relief valve out-of-service out-of-service NEOC NEOC near end-of-cycle end-of-cycle NSS NSS nominal scram nominal scram speed NRC NRC Nuclear Regulatory Nuclear Regulatory Commission, U.S.

OLMCPR OLMCPR operating limit minimum critical power ratio operating ratio OLTP OLTP original licensed thermal power OPRM OPRM oscillation power range monitor Pbypass Pbypass power below which direct scram on TSV/TCV TSVITCV closure is bypassed PCT peak cladding temperature temperature PLU power load unbalance unbalance PLUOOS PLUOOS power load unbalance unbalance out-of-service out-of-service PRFO pressure regulator failure open.

RBM (control) rod block monitor monitor RHR RHR residual heat removal RPT recirculation pump trip recirculation trip AREVA NP Inc.

ANP-2864(NP)

ANP-2864(NP) g-Browns Ferry Unit 1 Cycle 9- Revision 2 Revision Reload Safety Analysis Page viii Nomenclature Nomenclature (Continued)

(Continued)

SLC standby liquid control SLCS standby liquid control system SLMCPR satety limit minimum critical safety critical power ratio SLO SLO single-loop single-loop operation

. SS SS steady state TBVOOS out-of-service turbine bypass valves out-ot-service TBV valves turbine bypass valves .

TCV turbine control valve valve TIP .traversing incore probe incore probe TIPOOS incore probe out-ot-service traversing incore out-of-service

, TLO operation two-loop operation TSSS technical specifications scram speed TSV turbine stop valve turbine valve TTNB turbine trip with no bypass bypass TVA Tennessee Valley Authority Tennessee ACPR t.CPR change in in critical power ratio AREVA NP Inc.

ANP-2864(NP)

Browns Browns Ferry Unit 1 Cycle 9 Revision Revision 2-2- .

Analysis Reload Safety Analysis Page 1-1 1.0 1.0 Introduction Introduction Reload licensing analyses results generated by AREVA AREVA NP Inc.* are presented presented in support of operation. The analyses cycle operation. analyses reported document were performed reported in this document performed using methodologies methodologies previously approved approved for generic application application to boiling water reactors. The Nuclear Nuclear Regulatory Commission, U.S. (NRC) technical limitations associated application of the approved associated with the application methodologies have been methodologies been satisfied by these analyses.

The core consists of a total of 764 fuel assemblies, including 332 fresh ATRIUMTM-10t ATRIUM*-10t and 432 irradiated assemblies and432 irradiated .GEI4 Licensing analyses support the core design

.GE14 assemblies. licensing presented in Reference presented Reference 1.

Reload licensing analyses performed for potentially analyses were performed potentially limiting events and analyses identified identified in Section 2. Results of analyses analyses are used to establish the Technical Specifications/COLR limits Specifications/COLR limits and ensure design and licensing criteria criteria are met. Design and safety safety analyses analyses are based on both .

operational operational assumptions and plant parameters provided by the utility. The results of the reload licensing support operation licensing analysis support operation for the power/flow map presented presented in Figure 1.1 and also support operation with the equipment support operation out-of-service (EOOS) scenarios equipment out-of-service presented in Table 1.1.

scenarios presented 1.1.

AREVA NP Inc. is an AREVA AREVA and Siemens company.

t ATRIUM is a trademark of AREVA AREVA NP.

AREVA NP Inc.

ANP-2864(NP)

Browns Ferry.Unit Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page 1-2 Page 1-2 Table 1.1 EOD and EOOS EOOS Operating Conditions' Operating Conditions Extended Operating Domain Extended Operating Domain Conditions (EOD) Conditions Increased core flow (ICF)

Increased Maximum extended load line limit analysis (MELLLA)

Maximum extended (MELLLA)

Combined final feedwater reduction (FFTR) I/

feedwater temperature reduction coastdown Equipment Out-of-Service Equipment Out-of-Service Conditions*

(EOOS) Conditions*

out-of-service (TBVOOS)

Turbine bypass valves out-of-service (TBVOOS) recirculation pump trip out-of-service EOC recirculation out-of-service (EOC-RPT-OOS)

(EOC-RPT-OOS)

Feedwater Feedwater heaters out-of-service (FHOOS).

heaters out-of-service Power load unbalance Pdwe(load out-of-service (PLUOOS) unbalance out-of-service (PLUOOS)

Combined EOC-RPT-OOS Combined EOC-RPT-OOS and TBVOOS TBVOOS EOC-RPT-OOS and FHOOS Combined EOC-RPT-OOS FHOOS Combined EOC-RPT-OOS EOC-RPT-OOS and PLUOOS PLUOOS Combined TBVOOS and FHOOS FHOOS Combined TBVOOS and PLUOOS PLUOOS Combined FHOOS and PLUOOS PLUOOS Combined EOC-RPT-OOS, TBVOOS, and FHOOS Combined EOC-RPT-OOS, FHOOS Combined EOC-RPT-OOS, TBVOOS, and PLUOOS Combined EOC-RPT-OOS, PLUOOS Combined EOC-RPT-OOS, FHOOS, and PLUOOS Combined EOC-RPT-OOS, PLUOOS Combined Combined TBVOOS, FHOOS, and PLUOOS PLUOOS Combined EOC-RPT-OOS, Combined EOC-RPT -OOS, TBVOOS, FHOOS, and PLUOOS PLUOOS Single-loop Single-loop operation operation (SLO)

SLO SLO may may bebe combined combined with with all all of of the.other EOOS conditions.

the.other EOOS conditions. Base case and Base case and each each EOOS condition EOOS condition is supported in is supported in combination with 11 MSRVOOS, combination with MSRVOOS, up up to to 22 traversing traversing incore incore probe (TIP) machines probe (TIP) machines out-of-out-of-service (TIPOOS)

(TIPOOS) or the the equivalent equivalent number of TIP channels number of channels (per (per operating operating requirements requirements defined in defined in Section 4.2), and/or and/or up to 50% of the LPRMs out-of-service.

oUt-of-service.

AREVA NP Inc.

Inc.

ANP-2864(NP)

Browns Ferry Ferry Unit Unit 11 Cycle Cycle 9* 9. Revision Revision 22 Reload SafetySafety Analysis Analysis Page Page 1-3 no 120

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Figure 1.1 1.1 Browns Ferry Ferry Power/Flow Map Map - EPU/MELLLA EPU/MELLLA AREVA AREVA NP NP Inc. Inc.

ANP-2864(NP)

Browns Ferry-Unit 1 Cycle 9 Browns Ferry"Unit Revision 2 Reload Reload Safety Analysis Page 2-1 2.0 Disposition of Events Events The objective is to identity identify limiting limiting events events for analysis, supporting operation operation with ATRIUM-10 ATRIUM-10 fuel. Events and analyses potentially limiting are either evaluated analyses identified as potentially evaluated generically generically for the'the introduction of AREVA fuel or on a cycle-specific introduction cycle-specific basis.

The first step is to identify the licensing licensing basis of the plant. Included in the licensing licensing basis are descriptions of the postulated events/analyses descriptions events/analyses and the associated associated criteria. Fuel-related Fuel-related system design criteria must be met, ensuring regulatory regulatory compliance compliance and safe operation.

operation. The licensing licensing basis, related to fuel and applicable for reload analysis, is containedcontained in the Final Safety Analysis Analysis Report Report (FSAR), the Technical Specifications, Specifications, Core Gore Operating (COLR), and other Operating Limits Reports (GOLR),

reload analysis analysis reports. The licensing basis for adding EPU operation operation is obtained obtained in References References 33, 34, and 35. Reference 33,34, Reference 39 provides pr<:>vides the applicability applicability of AREVA AREVA BWR methods for EPU.

Reference 34 is based on EPU for Browns Ferry Units 2 and 3:

Reference 3'. Reference 34 is applicable applicable for Unit 1 because because the analyses analyses and basis for EPU are identicalidentical between between all three units. Reference Reference 35 provided provided the EPU licensing licensing basis for Units 2 and 3 for GE14 fuel. ReferenceReference 34 supplements Reference 35 with ATRIUM-10 supplements Reference ATRIUM-10 fuel and AREVA methods. The counterpart counterpart of Reference 35 for Unit 1 is Reference Reference Reference 36. The only significant differencedifference between the the References 35 and 36 analyses was the initial power level assumed before EPU. Unit 1 References analyses analyses assumed 100% 100% OLTP, whereas whereas Units 2 and 3 assumed assumed 105% OLTP. ReferencesReferences 34, 35 and 36 all have have the same final powerpower conditions of 120%120% OLTP for EPU; therefore, therefore, thethe analyses analyses in Reference Reference 34 are equally applicable Unit 1.

applicable for Unit Ferry Units All three Browns Ferry Units (1, 2, and 3) are essentially .the the same, except for core loading, because core operational because operational conditions, modeled geometry, safety system performance, and ECCS parameters are identical. A re~iew EGGS parameters review of geometry between Units 1; 1, 2, and 3 determined the only significant the.only significant difference was the recirculation recirculation piping for Unit 3 (Unit 3 has undergone undergone a recirculation header and riser replacement).

recirculation replacement). Differences Differences in recirculation piping for Unit 3 do not inrecirculation not result in any modifications to the recirculation recirculation piping model used in the analyses analyses (simplification (simplification of the recirculation recirculation piping model does does not distinguish the differences).

differences). The review of differences differences between units concluded none of the analyses, or dispositions between dispositions in Reference 34, neededneeded to be be revised for Unit .1.

1. Differences in core design design between between units are addressed on a cycle-specific cycle-specific basis.

AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page 2-2 2-2 AREVA reviewed all fuel-related fuel-related design criteria, events, and analyses identified identified in the licensing licensing basis. In In many cases, when operating operating limits are established established to ensure acceptable acceptable consequences consequences of of an abnormal operational operational transient (AOT) or accident, the fuel-related fuel-related aspects aspects of the system design criteria are met. All fuel-related fuel-related events were reviewed and dispositioned into one of the following categories:

1. No further analysis required. This classification classification may result from one of the following:

a. consequences of the event are bound by consequences The consequences consequences of aa different different event.

b. consequences of the event are benign, i.e.,

The consequences i.e., the event causes no significant significant change in margins margins to the operating operating limits.

c. event is not affected The event affected by the introduction of a new fuel design and/or the the current analysis of record record remains applicable.

2. Address Address event each reload. The consequences consequences of the event event are potentially limiting and need need to be addressed addressed each reload.

reload.

3. Address Address for initial reload. This classification may result from one of the following:

a. The analysis is performed performed using conservative conservative bounding assumptions and inputs inputs such that the initial reload results will remain applicable applicable for future reloads reloads of thethe same fuel design.

b.

b. Results from the first reload will be used to quantitatively quantitatively demonstrate that the the results remain applicable applicable for future reloads of the same fuel design because the design because the consequences are benign or bound by those of another consequences another event.

The impact of operation operation in the EOOS scenarios scenarios presented in Table 1.1 1.1 was also considered.

considered.

A disposition disposition of events summary summary is presented presented in Table 2.1.

2.1. The disposition summary presents a list of the events events and analyses, the corresponding corresponding FSAR section, the disposition disposition status, and any applicable comments. In each comment, the basis of the disposition applicable comments: disposition is categorized as:

- FSAR analysis (which may include include Reference Reference 34).

- Generic Generic analysis. A bounding bounding analYSis that is independent analysis independent of plant type.

- Plant specific specific analysis. The analysis is based on Browns Ferry (independent (independent of unit) and is bounding for cycle-to-cycle cycle-to-cycle variations.

Cycle specific specific analysis.

analysis. The analysis analysis is specific to the Unit and Cycle.

The disposition for the EOOS scenarios scenarios are summarized summarized in Table 2.2. ICF and MELLLA operation regions of the -power/flow operation power/flow map are included included in the disposition disposition results prese!1ted presented in in Table 2.1.2.1. Methodology Methodology and evaluation models models used for the cycle specific analyses are provided in Table 2.3. Overpressurization Overpressurization analyses analyses are performed with the NRC approved approved code code COTRANSA2 (References (References 12 and 41). 41).

AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 Browns ,-Revision

- Revision 2 Reload Safety Analysis Reload Analysis Page 2-3 2-3 Table Table 2.1 Disposition of Events 2.1. Disposition Events Summary

. for Browns Ferry Unit I1 FSAR Section Event IAnalysis

/Analysis Disposition Status Disposition Comments Comments 3.2 Fuel mechanical mechanical Address event Address event for Cycle specific specific analysis (results and and design each reload analyses generally do not change from from cycle-to-cycle, cycle-to-cycle, unless a design feature is modified).

Refer to Reference Reference 2 for the analysis, acceptance criteria, methodology and evaluation evaluation model.

Demonstrate design design criteria are met.

3.6 Nuclear Nuclear design Address event each Address event each Cycle specific specific analysis.

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

evaluation Demonstrate design criteria are met.

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

hydraulic design hydraulic reload Demonstrate design Demonstrate criteria are design criteria are met:

met. Fuel Fuel hydraulic hydraulic design and compatibility results results are provided in the Thermal-Hydraulic Thermal-Hydraulic Design report. Refer to Reference 3 for acceptance criteria, the analysis, acceptance methodology methodology and evaluation evaluation model. Other cycle specific specific criteria are presented this presented in this report, i.e., thermal operating limits.

thermal operating 3.8 Standby liquid Standby Address event each Cycle specific specific analysis. .

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

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Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Analysis Page 2-4 Table 2.1 Disposition of Events Summary for Browns Browns Ferry Unit 1

. (Continued)

(Continued)

FSAR )

Section /Analysis Event IAnalysis Disposition Status Status Comments Comments 4.2 Reactor vessel and Reactor No further analyses Reference 34.

FSAR analysis and Reference appurtenances appurtenances required The vessel fluence irradiation is primarily mechanical design The vessel upon dependent f1uence theirradiation is primarily effective full power mechanical dependent upon the effective full power years (EFPY),

(EFPY), power distribution, power management scheme. The level, and fuel management The ATRIUM-10 fuel neutron spectrum of the ATRIUM-10 neutron is sufficiently similar to the spectrum evaluation of applied in the licensing basis evaluation the vessel irradiation irradiation limits. The void, power distributions, and the fission spectrum for ATRIUM-10 ATRIUM-10 fuel are not impacted.by significantly impacted by BLEU. An evaluation of ATRIUM-10 ATRIUM-10 BLEU fuel flux flux concluded that the GE EPU analyses analyses remained bounding. The introduction of remained ATRIUM-10 fuel with or without BLEU will ATRIUM-10 effect on the fluence have an insignificant effect f1uence

. (E > 1.0 MeV) at the reactor vessel wall and internals.

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Browns Ferry Unit 1 Cycle 9 Browns . Revision 2 Reload Safety Analysis Reload Analysis Page 2-5 2.1 Disposition Table 2.1* Disposition of Events Summary Unit 1I for Browns Ferry Unit (Continued)

(Continued)

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

pressure relief reload specific analysis plant specific analysis (LOCA).

(LOCA).

system Analysis of limiting ASME and A ATWS TWS overpressurization events required each overpressurization reload.

Evaluations of the ADS capability are addressed as part oUhe of the LOCA analyses analyses (References 19 and 20).

(References 5.2 Primary analyses No further analyses FSAR analysis analysis and Reference 34 34...

containment system containment required required Except for the CAD evaluation, the Except primary for the CAD evaluation, containment the characteristics system primary containment characteristics following a postulated postulated LOCA are not fuel fuel related. The CAD system criteria were met for ATRIUM-1 ATRIUM-10. 0. The Unit 1 containment containment characteristics are the same as Units characteristics Units 2 assessment of CAD and 3, therefore the assessment for those units applies to Unit 1.

5.3 Secondary Secondary No further analyses analyses FSAR analysis and Reference 34.

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

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

LOCA LOCAis is aa potentially potentially limiting accident.

Limiting Limiting break characteristics characteristics are identified identified for the initial ATRIUM-10 ATRIUM-10 reload. Refer Refer to to References References 19 and 20 for the analysis, acceptance criteria, acceptance methodology and criteria, methodology evaluation model.

evaluation LOCA LOCA heatup heatup analysis for reload reload fuel is evaluated for follow-on evaluated follow-on reloads reloads to address address changes changes in neutronic neutronic design.

design.

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Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page 2-6 2-6 Table 2.1 Disposition Disposition of Events Summary for Browns Ferry Unit 1 (Continued)

(Continued)

FSAR Section Section Event IAnalysis

/Analysis Disposition Status Comments Comments 7.5 Neutron Neutron Address event each specific and cycle specific analysis.

Plant specific monitoring system monitoring reload Cycle specific Cycle OPRM trip specific OPRM trip setpoint setpoint calculations. RBM setpoints evaluated evaluated for CRWE event. Backup stability the CRWE protection. Long term ATWS analysesanalyses remain applicable applicable for ATRIUM-1 ATRIUM-10 0 (Section 7.2.2).

7.19 Anticipated Anticipated Address event each Cycle specific specific analysis.

transient transient without reload scram demonstrate Analyses are performed to demonstrate that the peak vessel pressure for the the limiting ATWS event is A TWS event I~ss less than the design design pressure.

8.10 Station blackout No further analyses analyses FSAR analysis and Reference Reference 34.

required remains The licensing basis analysis remains ATRIUM-10 fuel is designed to applicable. ATRIUM-10 applicable.

perform in manner similar to and in a manner analogous with fuel of current and analogous previous designs.

10.2 10.2 New fuel storage storage Address for initial Plant speCific Plant specific analysis.

reload Refer to Reference Reference 24 for the analysis, acceptance methodology and acceptance criteria, methodology evaluation model.

evaluation model.

Evaluated Evaluated for new.

new fuel storage racks. _

applicability each reload.

Confirm applicability 10.3 10.3 Spent fuel storage storage -Address Address for initial Plant specific analysis.

reload Reference 25 for the analysis, Refer to Reference acceptance criteria, methodology, and acceptance evaluation model.

Evaluated for spent fuel storage Evaluated storage racks.

applicability each reload.

Confirm applicability 10.11 Fire protection protection Address Address for initial for initial Plant specific analysis.

systems reload Appendix R criteria are met for ATRIUM-Appendix R criteria are met for ATRIUM-10 fuel. This issue is addressed in in Reference 37.

Refe-rence AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 Revision 2-Analysis Reload Safety Analysis Page 2-7 Table 2.1 Disposition of Events Summary for Browns Ferry Unit1 Unit.1 (Continued)

(Continued)

FSAR Section Event IAnalysis

/Analysis Disposition Status Comments Comments 14.5.2.1 14.5.2.1 Generator Generator trip No further analyses FSAR analysis analysis and Reference Reference 34.

(TCV fast closure)

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

bypass valve failure ..

14.5.2.2 14.5.2.2 Generator Generator trip Address event each each Cycle specific specific analysis.

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

potentially limiting bypass valve valve failure 14.5.2.2.4 14.5.2.2.4 LRNB with EOC- Address event each Cycle specific specific analysis.

RPT-OOS RPT-OOS reload This event potentially limiting event is a potentially limiting AOT.

14.5.2.3 14.5.2.3 Loss of condenser

.Loss condenser No further further analyses FSAR analysis.

vacuum required required Bound by the turbine trip with turbine turbine bypass valve failure.

14.5.2.4 14.5.2.4 Turbine trip (TSV No further analyses FSAR analysis.

closure) required required Bound by the turbine trip with turbine turbine failure.

bypass valve failure.*

14.5.2.5 . Turbine Turbine bypass Address Address for initial Cycle specific specific analysis, analysis, for initial reload.

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

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

valves failure reload following turbine Generally bound Generally bound by the generator generator trip with trip (TTNB),

(TINB), low turbine bypass valve failure. If If 14.5.2.5 14.5.2.5 is power power bound by generator bound generator trip with turbine turbine bypass 14.5.2.6 is also bypass valve failure, then 14.5.2.6 bound.

bound.

14.5.2.7 14.5.2.7 Main steam No further analyses Reference 34.

FSAR analysis and Reference isolation isolation valve required closure closure Relative to thermal thermal operating limits, bound bound by the generator generator trip with turbine bypass bypass valve failure.

AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 . Revision 2 .

Reload Safety Analysis Analysis Page 2-8 Table 2.1 -Disposition

.Disposition of Events Summary for Browns Browns Ferry Unit 1 (Continued)

(Continued)

FSAR Section Event /Analysis Event IAnalysis Disposition Status Comments Comments 14.5.2.8 14.5.2.8 Pressure Pressure regulator No further analyses FSAR analysis analysis and Reference Reference 34.

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

hydraulic 14.5.3.1 Loss of feedwater Address event each Cycle specific analysis.

heater heater (LFWH)

(LFWH) reload Generally bound by the LRNB and FWCF Generally FWCF events. Addressed each cycle to demonstrate that itit remains bound bound by the the other events.

14.5.3.2 Shutdown cooling No further analyses FSAR analysis.

(RHR) malfunction malfunction required

- decreasing decreasing Benign event.

temperature 14.5.3.3 14.5.3.3 Inadvertent HPCI Inadvertent HPCI No further analysis FSAR analysis analysis and Reference Reference 34.

pump start required (IHPS)

(IHPS) Generally bound by the LRNB and FWCF Generally FWCF events. The IHPS event is similar to the the LFWH event. The IHPS is is slightly more more CPR limiting, whereas whereas the LFWH is is slightly more thermal-mechanical thermal-mechanical limiting.

limiting.

Both IHPS and LFWH events have considerable considerable margin to the limiting LRNB LRNB and FWCF events. The LFWH transient is is analyzed analyzed for each cycle to demonstrate, on a relative basis, that the LFWH and IHPS events remain non-limiting.

non-limiting.

14.5.4.1 14.5.4.1 Continuous rod Address event event each Cycle specific analysis.

withdrawal during during reload power range potentially limiting AOT.

This event is a potentially operation 14.5.4.2 14.5.4.2 Continuous Continuous rod No further analyses analyses FSAR analysis.

withdrawal withdrawal during during required reactor startup Benign event.

14.5.4.3 14.5.4.3 Control rod No further analyses analyses FSAR analysis.

removal error required during refueling This event is not credible.

AREVA AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9

_. Browns Revision 2

,Revision Reload Analysis Reload Safety Analysis Page 2-9 Table 2.1 Disposition Disposition of Events Summary Summary for Browns Ferry Ferry Unit 1 (Continued)

(Continued)

FSAR Section /Analysis Event IAnalysis Disposition Status Comments Comments 14.5.4.4 14.5.4.4 Fuel assembly assembly No further analyses analyses FSAR analysis.

insertion error required required during refueling This event is not credible.

Mislocated Mislocated or Address event each Generic analysis.

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

failure open reload (PRFO) Relative to AOT thermal operating operating limits, benign event.

PRFO - maximum steam demand is a potentially limiting ATWS A TWS overpressurization event. A overpressurization TWS-PRFO is ATWS-PRFO considered for FSAR 7.19.

considered 14.5.5.2 Inadvertent Inadvertent No further analysis FSAR analysis.

opening of a required MSRV (IORV)

MSRV Benign event.

14.5.5.3 Loss of feedwater feedwater No further analysis FSAR analysis.

flow (LOFW)

(LOFW) required Benign event.

14.5.5.4 14.5.5.4 Loss of auxiliary No further analyses FSAR analysis analysis power required Benign event.

Benign 14.5.6.1 14.5.6.1 Recirculation flow Recirculation No further analysis FSAR analysis analysis..

control control failure - . required decreasing decreasing flow Non-limiting event.

Non-limiting 14.5.6.2 14.5.6.2 Trip of one No further analyses FSAR analysis.

recirculation recirculation pump required Consequences of this event are benign Consequences benign and bound by the turbine trip with nono bypass event.

14.5.6.3 14.5.6.3 Trip of two No further analyses FSAR analysis.

recirculation recirculation required pumps Consequences of this event are benign Consequences benign and bound by the turbine trip with no no bypass event.

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, Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Safety Analysis Page 2-10 2-10 Table 2.1 Disposition Disposition of Events Summary for Browns Ferry Ferry Unit 1 (Continued)

(Continued)

FSAR Section Section Event Event /Analysis IAnalysis Disposition Status Comments Comments 14.5.6.4 14.5.6.4 Recirculation Recirculation No further analysis FSAR analysis.

pump seizure seizure required The consequences consequences of this accident are bounded by the effects of a LOCA.

14.5.7.1 14.5.7.1 Recirculation Recirculation flow Address event each Cycle specific analysis.

control failure - reload increasing increasing flow Consequences of the slow flow run-up Consequences run-up event determine determine the flow-dependent flow-dependent MCPR and LHGR operating operating limits and are are evaluated each reload.

evaluated 14.5.7.2 14.5.7.2 Startup of idle No further further analysis FSAR analysis.

recirculation recirculation loop required Benign event.

Benign event.

14.5.8.1 14.5.8.1 Feedwater Feedwater Address event each ' Cycle specific specific analysis.

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

maximum demand demand .

14.5.8.2

14.5.8.2 Feedwater Feedwater Address event each Cycle specific specific analysis.

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

demand maximum demand with EOC-RPT-OOS OOS 14.5.8.3 Feedwater Feedwater . .

Address event eVEmt each Cycle specificanalysis.

specific analysis ...

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

demand maximum demand with TBVOOS TBVOOS 14.5.9 14.5.9 Loss of habitability No further analyses FSAR analysis.

of the control control room required This is postulated as a special event to demonstrate demonstrate the ability to safely safely shutdown the reactor from outside the control room.

14.6.2 14.6.2 Control rod drop Address Address event each Cycle specific analysis.

analysis.

accident accident (CRDA) reload Consequences Consequences of the CRDA are evaluated to confirm acceptance criteria are confirm that the acceptance satisfied.

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Browns Ferry Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Safety Analysis Analysis Page 2-11 2-11 Table 2.1 Disposition Disposition of Events Summary Ferry Unit 1 for Browns Ferry (Continued)

(Continued)

FSAR Section /Analysis Event IAnalysis Disposition Disposition Status Comments Comments 14.6.3 14.6.3 Loss-of-coolant Loss-of -coola nt Address event event each Plant specific analysis analysis and cycle specific specific accident (LOCA) reload analysis.

Consequences Consequences of the LOCA are evaluated to determine appropriate cycle-specific appropriate cycle-specific MAPLHGR limits. Refer to References MAPLHGR References 19 and 20 for the analysis, acceptance acceptance criteria, methodology methodology and evaluation model.

LOCA heatup analysis analysis for reload fuel is evaluated for follow-on reloads to address evaluated address changes in neutronic changes neutronic design.

14.6.4 14.6.4 Refueling accident Address Address event event each Plant specific analysis.

reload Refer to Reference Reference 27 for the analysis, acceptance acceptance criteria, methodology methodology and evaluation evaluation model.

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

14.6.5 14.6:5 Main steam line No further analysis FSAR analysis and Reference 34.

break break accident accident required consequences of a large steam line The consequences line break are far from limiting with respect respect to 10 CFR 50.46 acceptance acceptance criteria.

Radiological dose dose consequences consequences havehave been been performed performed utilizing AST in in accordance accordance with 10 CFR 50.67. The The consequences consequences of the eventevent are not a failures function of fuel type since no fuel failures are calculated occur.. The dose calculated to occur. dose is a function of the radionuclide radionuclide inventory inventory in in the coolant itself prior to the event.

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Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page Page 2-12 2-12 Table 2.2 Disposition of Operating Flexibility Flexibility and EOOS Options Events Options on Limiting Events Option Option Affected Limiting _ Comments Events/Analyses Events/Analyses One MSRV MSRV ASME Overpressurization Overpressurization This scenario is included included as part of the base Out-of-Service Out-of-Service case condition for the events/analyses events/analyses FWCF identified.

identified.

LRNB TINB TTNB ATWS ATWS Single-loop operation operation LOCA The impactof impact of SLOon SLO on LOCA is addressed addressed (SLO) SLMCPR in Section 8.

SLMCPR*

The SLO SLMCPR is addressed addressed each reload.

Final Feedwater Feedwater FWCF-FWCF This scenario is included included in each reload for Temperature Temperature Reduction Reduction each of these events/analyses.

(FFTR)/Feedwater (FFTR)/Feedwater Option III Stability Solution Solution Out-of-Service Heater Out-of-Service Backup Stability Protection Backup Stability Protection (FHOOS)

(FHOOS) (BSP)

(BSP)

Turbine bypass valve FWCF The FWCF event with TBVOOS TBVOOS is system out-of-service evaluated evaluated each reload.

(TBVOOS)

EOC-RPT out-of-service EOC-RPT out-of-service FWCF This scenario scenario is included included in each reload for (EOC-RPT OOS) each of these events/analyses.

events/analyses.

LRNB LRNB U-NB TINB Power Power load unbalance unbalance LRNB The LRNB event with PLUOOS PLUOOS is evaluated out-of~service out-of-service each reload.

(PLUOOS)

Traversing in-core probe Traversing in-core SLMCPR TIP OOS is included in the SLMCPR SLMCPR out-of-service (TIP) out-of-service analysis.

analysis.

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Ferry-Unit 1 Cycle 9 Browns Ferry,Unit Revision 2 Analysis Reload Safety Analysis Page Page 2-13 2-13 2.3 Methodology Table 2.3 Methodology and Evaluation Models Models for Cycle Specific Specific Analyses

. Reload Analyses Analysis Analysis FSAR Methodology Evaluation Acceptance Criteria and Acceptance Section Section Event IAnalysis Event /Analysis Reference Model Comments 4*

4 SAFLlM2 SAFLIM2 SLMCPR criteria: < 0.1 0.1%% fuel 3.7 Thermal and hydraulic design 12 COTRANSA2 rods experience boiling boiling 12 COTRANSA2 transition.

13 XCOBRA XCOBRA Transient criteria: Power and Transient criteria: Power and 14 XCOBRA-T flow dependent MCPR MCPR and 16 RODEX2 LHGR operating limits limits 16 RODEX2 established to meet the fuel established failure criteria.

3.8 Standby liquid Standby 15 CASMO-4 SLCS criteria: Shutdown margin control system /MICROBURN-IMICROBURN-B2 of at least 0.88% ~klk. Ak/k.

control system B2 4.4 Nuclear system Nuclear 12 COTRANSA2 COTRANSA2 Analyses for ASME and A TWS ATWS pressure relief overpressurization.

overpressurization.

system ASME overpressurization ASME overpressurization criteria: Maximum criteria: Maximum vessel pressure pressure limit of 1375psig 1375-psig and maximum dome maximum dome pressure limit of 1325 psig.

ATWS A overpressurization TWS overpressurization criteria: Maximum Maximum vessel pressure pressure limit of 1500 psig.

6.0 Emergency core Emergency 38 HUXY LOCA criteria:

LOCA criteria: 10CFR50.46.

10CFR50.46.

cooling systems EXEM BWR-2000 EXEM BWR-2000 Methodology.Methodology.

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

7.5 7.5 Neutron Neutron 77 STAIF STAIF Long term stability solution solution monitoring system 8 RAMONA5-FA Option III Option III criteria:

criteria: OPRM OPRM monitoring system 8 RAMONA5-FA setpoints do not result in setpoints do not result in 9 CASMO-4 CASMO-41/ exceeding OLMCPR limits.

exceeding OLMCPR 10 MICROBURN-MICROBURN-10 CRWE criteria:

criteria: Power Power B2 B2 dependent MCPR and LHGR dependent MCPR and LHGR 11 operating limits established to operating limits established to 15 15 the fuel failure meet the failure criteria.

30 30 Backup Backup stability protection protection criteria: Stability Stability boundaries boundaries that do not exceed do exceed acceptable acceptable global, global, regional regional and channel decay decay ratios ratios as as defined defined by the the STAIF methodology.

methodology.

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Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Safety Analysis Reload Analysis 2-14 Page 2-14 Methodology and Evaluation Table 2.3 Methodology Models for Cycle Specific Evaluation Models Specific Reload Analyses (Continued)

(Continued)

Analysis Analysis FSAR Methodology Methodology Evaluation Acceptance Acceptance Criteria Criteria and Section /Analysis Event IAnalysis Reference Reference Model Comments Comments 7.19 7.19* Anticipated Anticipated '12 12 COTRANSA2 A TWS overpressurization ATWS overpressurization transient without transient criteria: Maximum Maximum vessel scram pressure limit of 1500 psig.

pressure ATWS peak pressure only.

14.5.2.2 Generator trip Generator 12 COTRANSA2 COTRANSA2 Transient Transient criteria: Power and (TCV fast closure) 13 XCOBRA flow dependent MCPR and 13 XCOBRA with turbine LHGR operating limits LHGR limits bypass valve 14 XCOBRA-T XCOBRA-T established to meet the fuel established fuel failure 16 RODEX2 failure criteria.

16 . RODEX2 14.5.2.2.4 14.5.2.2.4 LRNB with EOC- 12 12 COTRANSA2 COTRANSA2 Transient criteria: Power RPT-OOS 13 XCOBRA dependent dependent MCPR and LHGR LHGR 13 XCOBRA operating limits established operating established to 14 14 XCOBRA-T XCOBRA-T meet the fuel meet the fuel failure failure criteria.

criteria.

16 RODEX2 14.5.2.5 14.5.2.5 Turbine bypass Turbine bypass 12 12 COTRANSA2 COTRANSA2 Transient criteria: Power valves failure 13 XCOBRA dependent MCPRand dependent MCPR and LHGR LHGR 13 XCOBRA following turbine operating operating limits established established to trip (TTN-B),

(TTNB), high 14 14 XCOBRA-T XCOBRA-T meet the meet the fuel failure criteria.

fuel failure criteria.

power 16 16 RODEX2 RODEX2 14.5.2.6 14.5.2.6 Turbine bypass 12 12 COTRANSA2 COTRANSA2 Transient criteria: Power valves failure 13 XCOBRA dependent dependent MCPRMCPR and LHGR LHGR 13 XCOBRA following turbine operating limits established established to trip (TTNB), low 14 14 XCOBRA-T meet the fuel failure criteria.

power 16 16 RODEX2 RODEX2 14.5.3.1 14.5.3.1 Loss of feedwater 15 CASMO-4 CASMO-4 Transient criteria:

criteria: Power Power heater (LFWH) heater (LFWH) 18 IMICROBURN-

/MICROBURN- dependent dependent MCPRMCPR and LHGR LHGR 18 B2 established to operating limits established meet the fuel failure criteria meet the fuel failure criteria 14.5.4.1 14.5.4.1 Continuous rod Continuous 15 CAS M0-4 CASMO-4 CRWE criteria:

criteria: Power Power withdrawal during IMICROBURN-

/MICROBURN- dependent dependent MCPRMCPR and LHGR LHGR power range - B2 operating limits established established to -

operation meet the fuel failure criteria criteria Mislocated or Mislocated 15 CASMO-4 CAS M 0-4 Mislocatedimisoriented criteria:

Mislocatedimisoriented criteria:

misoriented fuel misoriented /MICROBURN-IMICROBURN- Small fraction of 10 10 CFR 50.67 50.67 assembly 23 23 B2 limits limits analysis...

Generic analysis AREVA NP Inc Inc...

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Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page 2-15 Page 2-15 Table 2.3 Methodology Methodology and Evaluation Models Models for Cycle Specific Specific Reload Analyses (Continued)

(Continued)

Analysis Analysis FSAR FSAR Methodology Methodology Evaluation Evaluation Acceptance Criteria arid Acceptance and Section Event /Analysis IAnalysis Reference Model Comments Comments 14.5.7.1 14.5.7.1 Recirculation flow Recirculation 14 CASMO-4 Transient Transient criteria: Flow control failure - 15 IMICROBURN-

/MICROBURN- dependent MCPR and LHGR dependent LHGR 15 increasing increasing flow B2 operating limits established to XCOBRA meet the fuel failure criteria.

XCOBRA 14.5.8.1 14.5.8.1 Feedwater Feedwater 12 COTRANSA2 COTRANSA2 Transient criteria: Power controller failure 13 XCOBRA dependent dependent MCPR and LHGR LHGR 13 XCOBRA (FWCF) - operating limits established operating established to maximum demand maximum 14 XCOBRA-T meet the fuel failure criteria.

16 RODEX2 14.5.8.2 14.5.8.2 Feedwater Feedwater 12 COTRANSA2 COTRANSA2 Transient criteria: Power controller failure 13 XCOBRA dependent dependent MCPR and LHGR LHGR 13 XCOBRA (FWCF) - operating operating limits established to maximum demand 14 14 XCOBRA-T XCOBRA-T meet the fuel failure criteria.

with EOC-RPT- 16 16 RODEX2 RODEX2 OOS OOS 14.5.8.3 Feedwater Feedwater 12 COTRANSA2 COTRANSA2 Transient criteria: Power Power controller controller failure 13 XCOBRA dependent MCPR and LHGR dependent MCPR LHGR 13 XCOBRA (FWCF) - operating operating limits established to maximum demand maximum 14 14 XCOBRA-T XCOBRA-T meet the fuel failure criteria.

with TBVOOS 16 16 RODEX2 RODEX2 14.6.2 Control rod drop 15 15 CASMO-4 CASMO-4 CRDA criteria: Maximum Maximum accident (CRDA) accident (GRDA) IMICROBURN-

/MICROBURN- deposited fuel rod enthalpy is is B2 B2 less than less 280 cal/g.

than 280 cal/g.

14.6.3 14.6.3 Loss-of-coolant Loss-of-coolant 38 HUXY HUXY LOCA criteria: 10CFR50.46.

10CFR50.46.

accident accident (LOCA) EXEM BWR-2000 EXEM BWR-2000 Methodology.

Methodology.

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

design.

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Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Page 3-1 3.0 3.0 Mechanical Design Mechanical Analysis Design Analysis Mechanical design exposure Mechanical design presented in Reference ATRIUM-10 fuel are presented exposure limits for ATRIUM-10 Reference 2. The The maximum exposure limits for the ATRIUM-10 maximum ATRIUM-10 reload fuel are:

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

Maximum exposure Maximum unchanged from that presented exposure limits for GE14 fuel assemblies remain unchanged in presented in Reference 26.

Reference The fuel cycle design analyses (Reference design analyses assemblies remain within licensed (Reference 1) verified all fuel assemblies burnup limits,.

limits, The ATRIUM-10 Section 8.0. The GE14 ATRIUM-10 LHGR limits are presented in Section presented in GE14 LHGR limits presented Section Section 8.0 ensure thermal-mechanical design criteria for GE14 fuel are satisfied.

ensure that the thermal-mechanical AREVA NP Inc.

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Browns Ferry Browns Unit 1I Cycle Ferry Unit Cycle 9 Revision 2 2 Reload Safety Reload Safety Analysis Analysis Page 4-1 Page 4-1 4.0 4.0 Thermal-Hydraulic Design Analysis Thermal-Hydraulic Analysis 4.1 Thermal-HydraulicDesign Thermal-Hydraulic Design and and Compatibility Compatibility Results of thermal-hydraulic characterization and compatibility analyses are presented in in Reference 3. Analysis results demonstrate Reference demonstrate the thermal-hydraulic design and compatibility ATRIUM-10 and GE14 criteria are satisfied for the transition core consisting of ATRIUM-10 GEl4 fuel.

4.2 Safety Limit MCPR MCPR Analysis The safety limit MCPR (SLMCPR) is defined defined as the minimum value of the critical power ratio ratio ensuring less than 0.1 0.1%

% of the fuel rods are expected to experience experience boiling transition during normal operation, or an abnormalabnormal operational operational transient (AOT). The SLMCPR SLMCPR for all fuel was was determined using the methodology described Reference 4. The analysis was performed with described in Reference a power distribution conservatively conservatively representing expected reactor operation throughout the the cycle.

SLMCPR SLMCPR analysis used the SPCB critical critical power correlation* additive additive constants and additive and additive constant uncertainty uncertainty for ATRIUM-10 ATRIUM-10 fuel described in References References 5 and 31 Addendum. The The SPCB additive constants constants and additive constant uncertainty uncertainty for the coresident GE14 fuel were developed using the indirect approach developed described in Reference approach described Reference 6.

Determination Determination of the SLMCPR explicitly includes SLMCPR explicitly includes the effects of channel channel bow relying on the the following assumptions: no fuel channels used for more than one fuel bundle lifetime, lifetime, and assembly average burnup remains less than 45 GWd/MTU average burriup GWd/MTlI for centralcentral ATRIUM-10 ATRIUM-10 and and GE14 GE14 fuel types. The channel channel bow local peaking peaking uncertainty uncertainty is a function function of the nominal nominal and bowed bowed local peaking factors and the standard standard deviation of the channel channel bow.

Fuel- and and plant-related uncertainties used in the SLMCPR plant-related uncertainties SLMCPR analysis are presented presented in Table 4.1. 4.1.

The radial radial power uncertainty uncertainty used in the analysis includes the effects effects of up to 40% of the TIP TIP

/

channels channels out-of-service, out-of-service, up to 50% of the LPRMs out-of-service, and LPRMsout-of-service, and a 2500 2500 EFPH LPRM calibration interval.

calibration interval.

AREVA has submitted Reference 31 to the NRC. Reference 31 addresses Condition Report 2007-

AREVA has submitted Reference 31 to the NRC. Reference 31 addresses Condition Report 2007-3653 3653 regarding regarding the CPR test looploop power error. Analyses Analyses incorporate incorporate the revised ATRIUM-10 ATRIUM-10 additive additive constants.. Reference 31 constants. Reference* 31 was was approved approved byby the the NRC in the NRC in the final final safety safety evaluation evaluation of Reference Reference 42.

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I-Cycle 99 Browns Ferry Unit 1-Cycle - Revision 2 Reload Safety Analysis Page 4-2 Analysis results support two-loop operation SLMCPR of 1.07 and single-loop (TLO) SLMCPR operation (TLO) operation single-loop operation (SLO) SLMCPR of 1.10. Analysis results including including the SLMCPR and the percentage percentage of rods rods expected expected to experience experience boiling transition are summarized summarized in Table 4.2.

4.3 Core Hydrodynamic Core Stability Hydrodynamic Stability Browns Ferry has implemented BWROG Long Term Stability Solution Option III (Oscillation Browns (Oscillation Power Monitor-OPRM). Reload Power Range Monitor-OPRM). Reload validation has been performed performed in accordance accordance with with Reference Operating Limit MCPR (OLMCPR) is provided for two Reference 7. The stability based Operating conditions as a function of OPRMOPRM amplitude amplitude setpoint in Table 4.3. The two conditions evaluated are for a postulated postulated oscillation at 45% core flow steady state operation operation (SS)

(SS) and following following a two recirculation pump trip (2PT) from the limiting recirculation limiting full power operation state point. Power-Power,; and Flow-dependent limits provide provide adequate adequate protection against SLMCPR for postulated against violation of the SLMCPR postulated reactor instability as long as the operating operating limit is greater than or equal to the specified value for the selected selected OPRM OPRM setpoint. Setpoints supporting supporting EOOS operating operating conditions conditions are provided in in Table 4.3..

Table 4.3

. Evaluations by General General Electric (GE) have shown that that the generic DIVOM curves specified in generic DIVOM in Reference 7 may not be conservative Reference operating conditions conservative for current plant operating conditions for plants plants which implemented Stability Option III.

have implemented Ill. The non-conservatism non-conservatism was addressed by performing performing calculations for the relative calculations relative change in CPR as a function of the calculated calculated hot channel channel oscillation oscillation (HCOM). Analyses were performed magnitude (HCOM). performed with the RAMONA5-FA RAMONA5-FA code in accordance accordance with Reference 30. The code is a coupled neutronic-thermal-hydraulic Reference neutronic-thermal-hydraulic three-dimensional three-dimensional transient model model for the purpose of determining the relationship between between the relative ~CPR and relative change in ACPR the HCOM on a plant specific basis. The method was developed consistent with the the recommendations of the BWROG in Reference recommendations Reference 8. Generation plant-specific DIVOM data is Generation of plant-specific consistent with the BWROG resolution of the non-conservatism non-conservatism as provided provided in Reference Reference 9. TheThe stability-based OLMCPRs were calculated stability-based calculated using the most limiting calculated calculated change in relative relative ACPR

~CPR for a given oscillation oscillation magnitude.

In cases where the OPRM OPRM system is declared inoperable, Backup Stability Stability Protection (BSP) is provided in accordance provided accordance with Reference Reference 10. 10. BSP curves ~ave have been evaluated evaluated using STAIF STAIF (Reference 11)

(Reference 11) to determine determine endpoints meeting meeting decay ratio criteria for the BSP Base Minimal Region I (scram region) region) and Base Minimal Minimal Region IIII (controlled entry region). Stability AREVA AREVA NP Inc.

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Browns Ferry Unit 1I Cycle 9 Browns *Revision Revision 2 Reload Safety Safety Analysis Analysis Page 4-3 boundaries based on these endpoints can then be determined boundaries determined using using the generic shape shape generating generating function Reference 10. Analyses have been function from Reference performed to support been performed support operation operation for both nominal, nominal, and reduced reduced feedwater temperature temperature conditions (both FFTR and FHOOS).

The STAIF acceptance acceptance criteria criteria for the BSP endpoints are global decay ratios::::;

ratios < 0.85, and channel decay ratios::::;

regional and channel ratios < 0.80. Endpoints for the BSP regions *provided provided in Table 4.4 ratios < 0.85, and regional and channel decay have global decay ratios::::; ratios < 0.80.

decay ratios::::;

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. Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Analysis 4-4.

Page 4-4*

Table 4.1 Fuel- and Plant-Related Plant-Related Uncertainties Uncertainties for for Safety Limit MCPR MCPR Analyses Analyses Parameter Parameter Uncertainty Uncertainty Fuel-Related Uncertainties Fuel-Related Uncertainties I

I Plant-RelatedUncertainties Plant-Related Uncertainties Feedwater flow Feedwater rate flowrate 1.8%

Feedwater temperature Feedwater temperature 0.8%

Core pressure 0.7%

Total core flow rate rate TLO 2.5%

. SLO.

SLO 6.0%

[

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Browns Ferry Unit Unit 1 Cycle 9 Revision 2 ..- -

Reload Safety Safety Analysis Analysis Page 4-5 Table 4.2 Results Summary for for Safety Limit MCPR Analyses Analyses Percentage Percentage SLMCPR SLMCPR of Rods in Boiling Boiling Transition

. TLO -1.07

- 1.07 0.069 0.069 SLO--1.10 SLO 1.10 0.073 0.073 AREVA AREVA NP Inc.

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Browns Ferry Ferry Unit Unit 11 Cycle Cycle 9 Revision 2 Safety Analysis Reload Safety Analysis Page 4-6 4-6 Table 4.3 OPRM Setpoints OPRM OLMCPR OLMCPR OPRM OPRM OLMCPR OLMCPR OLMCPR OLMCPR Setpoint (SS)

(SS) (2PT)

(2PT) 1.05 1.05 1.16 1.16 1.07 1.07 1.06 1.06 1.18 1.18 1.09 1.09 1.07 1.07 1.20 1.20 1.11 1.11 1.08 1.22 1.22 1.12 1.12 1.09 1.23 1.23 1.14 1.14 1.10 1.10 1.25 1.25 1.16 1.16 1.11 1.11 1.27 1.27 1.18 1.18 1.12 1.12 1.30 1.30 1.20 1.20 1.13 1.13 1.32 1.32 1.22 1.22 1.14 1.14 1.34 1.34 1.24 1.24 1.15 1.15 1.36 1.36 1.26 1.26 Rated Power Off-Rated Off-Rated OLMCPR OLMCPR as as Acceptance Acceptance OLMCPR OLMCPR described described in Criteria Criteria at 45% Flow . Section Section 8.0 8.0 AREVA AREVA NP NP Inc.

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Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page 4-7 Endpoints for Table 4.4 BSP Endpoints Browns Browns Ferry Unit 1 I Cycle 9 Feedwater Feedwater Temperature Temperature Operation End Point Power Flow Flow Mode Mode Region Designation Designation (%

(% rated) . (% rated)

Nominal Nominal Scram Scram. IA IA 57.35 57.35 41.00 Nominal Nominal Scram IB 1B 39.34 39.34 29.00 Nominal Nominal Controlled Controlled IIA 64.50 50.00 entry Nominal Controlled liB 1iB 27.54 29.00 entry .

FFTR/

FFTRI Scram IA 62.53 62.53 47.50 FHOOS FHOOS FFTR/

FFTRI Scram IB l1B 34.00 29.00 FHOOS FHOOS FFTR/

FFTRI Controlled Controlled IIA 64.50 50.00 FHOOS entry FFTR/

FFTRI Controlled liB lib 27.54 29.00 29.00 FHOOS entry AREVA NP Inc.

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- Browns Ferry Unit Unit 1 Cycle 9 Revision Revision 2 Reload Safety Safety Analysis Page 5-1 5.0 Anticipated Anticipated Operational Occurrences Occurrences This section describes describes the analyses performed to determine the power- and flow-dependent flow-dependent operating limits for base case operation.

MCPR operating operation.

COTRANSA2 (Reference COTRANSA2 (Reference 12), XCOBRA-T (Reference 13),

XCOBRA-T (Reference 13), XCOBRA XCOBRA (Reference 14), and and CASMO-4/MICROBURN-B2 (Reference CASM04/MICROBURN-B2 (Reference 15)

15) are the major codes used used in the thermal limits thermal limits analyses analyses as described in the AREVA THERMEX methodology methodology report (Reference (Reference 14) and and neutronics methodology report (Reference neutronics (Reference 15). COTRANSA2 is a system transient simulation 15). COTRANSA2 code, which includes an axial one-dimensional one-dimensional neutronics neutronics model that captures captures the effects of axial power power shifts associated with the system transients. XCOBRA-T is a transient thermal- thermal-hydraulics code used in the analysis of thermal margins margins for the limiting fuel assembly. XCOBRA is used in steady-state steady-state analyses. The SPCB critical powerpower correlation* (References (References 5 and 31) 31) is used to evaluate the thermal margin of the ATRIUM-10 ATRIUM-10 and GE14 fuel. The application application of the the SPCB correlation correlation to GE14 fuel follows the indirect process described Reference 6. Fuel described in Reference Fuel pellet-to-cladding conductance values are based on RODEX2 (Reference pellet-to-cladding gap conductance 16),calculations (Reference 16),calculations for the BF1 Cycle 9 core.

5.1 System Transients System Transients.

The reactor plant parameters for the system transient analyses analyses were provided provided by the utility.

Analyses performed to determine power-dependent Analyses have been performed MCPR limits that protect power-dependent MCPRlimits operation throughout the power/flow domain depicted depicted in Figure 1.1.

Figure 1.1.

At BF1, BF1, direct scram on turbine stop valve (TSV) position position and turbine control valve (TCV) fast closure are bypassed at power (Pb~pass). Scram will occur when the power levels less than 26% of rated (Pbypass). the high pressure or high neutron flux scram setpoint is reached. ReferenceReference 17 indicates indicates that MCPR MCPR limits only need to be monitored monitored at power levels greater greater than or equal to 23% 23% of rated, which is the lowest lowest power analyzed for this report.

The limiting exposure for rated poWer power pressurization pressurization transients is typically typically at end of full power (EOFP) when the control rods are fully withdrawn. To provide additional margin to the operating operating limits earlier in the cycle, analyses were also performed performed to establish operating limits at a near

AREVA has submitted Reference 31 to the NRC. Reference 31 addresses Condition Report 2007-

AREVA has submitted Reference 31 to the NRC. Reference 31 addresses Condition Report 2007-3653 regarding the CPR test loop power power error. Analyses incorporate incorporate the revised ATRIUM-10 ATRIUM-10 additive additive Reference 31 was approved constants. Reference approved by the NRC inin the final safety evaluation of Reference 42.

of Reference AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page 5-2 end-of-cycle (NEOC) end-of-cycle (NEOC) core average average exposure exposure of 27,135 MWd/MTU.

MWd/MTU. Analyses were performed performed at exposures prior to NEOC to ensure cycle exposures ensure that the operating limits provide provide the necessary protection. The end-of-cycle protection. end-of-cycle licensing basis (EOCLB) performed at EOFP + 15 (EOCLB) analysis was performed EFPD (core average exposure of 29,748 MWd/MTU).

average exposure MWd/MTU). Analyses Analyses were also performed performed to support

. extended cycle operation operation with final feedwater temperature temperature reduction (FFTR) and power coastdown. The licensing licensing basis exposures exposures used to develop develop the neutronics inputs to the transient transient analyses are presented presented in Table 5.1. 5.1.

All pressurization pressurization transients transients assumed assumed that one *of of the lowest setpoint main steam relief valves valves (MSRV) was inoperable. The basis supports operation operation with 1 MSRV MSRV out-of-service.

out-of-service.

Reductions in feedwater Reductions feedwater temperature temperature of less than 10°F from the nominal feed feedwater water temperature temperature and variation of +/-10 psi in dome pressure are considered considered base case operation, operation, not an EOOS EOOS condition.

condition. Analyses were performed to determine determine the limiting limiting conditions in the allowable allowable ranges.

FFTR is used to extend rated power operation by decreasing power operation decreasing the feedwater temperature. The The amount of feedwater feedwater temperature temperature reduction reduction is a function of power with the maximum decrease decrease of 65 0 F (55 0 F + 10°F 65°F (55°F bias) at rated power. Analyses were performed performed to support support combined combined FFTR/Coastdown FFTRICoastdown operation operation to a core average exposure of 31,270 MWd/MTU.

average exposure MWd/MTU. The analyses analyses were performed performed with the limiting feedwater feedwater and domedome pressure pressure conditions in the allowable allowable ranges.

pressurization transient results are sensitive System pressurizatiQn to scram speed assumptions. To take sensitive toscram take advantage of average scram advantage scram speeds speeds faster than those associated with the Technical associated with I

Specifications requirements, scram speed-dependent Specifications speed-dependent MCPR MCPRPp limits are provided. The nominal scram scram speed (NSS) insertion insertion times and the Technical Specifications Specifications scram speed (TSSS) insertion times used in the analyses analyses are presented presented in Table 5.2. The NSS MCPR MCPRPp limits can only only be applied ifif the scram speed speed test results meet the NSS insertion insertion times. System transient transient analyses analyses were performed performed to establish establish MCPRp MCPRp limits for both NSS and TSSS insertion times.

Technical Specifications Technical Specifications (Reference (Reference 17) allow for operation operation with up to 13 "slow" and 1 stuck 13 "slow" control rod. One additional control rod is assumed to fail to scram. Conservative adjustments scram. Conservative adjustments to the NSS the NSS and TSSS scram speeds speeds-were were made to the analysis inputs to appropriately appropriately account for these effects effects on scram reactivity. For cases below Forcases below 26% power, the results are relatively relatively AREVA AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 99 Revision 2 Revision Reload Safety Analysis Page 5-3 5-3 insensitive to scram speed, and only TSSS analyses are performed.

performed. At 26%. (Pbpass),

26% power (Pbypass),

analyses analyses were performed, both with and and without bypass .of the direct direct scram scram function, resulting in in an operating limits step change.

5.1.1 Load Rejection Rejection No Bypass (LRNB)

(LRNB)

Load rejection causes a fast closure of the turbine control control valves. The resulting compression wave travels through through the steam steam lines into the vesseland vessel'and creates a rapid pressurization. The pressurization. The increase increase in pressure causes a decrease decrease in core voids, which in turn causes a rapidrapid increase increase in in power. Fast closure of the turbine control valves also causes aa reactor scram and RPT. Turbi~e Turbine bypass system operation, operation, which also mitigates the consequences consequences of the event, is not credited.

The excursion excursion of the core power due to the void collapse is terminated primarily by the reactor scram and revoiding of the core.

LRNB analyses analyses assume assume the power load unbalance (PLU) is inoperable unbalance (PLU) inoperable for power levels less.

less than 50% of rated. The LRNB sequence sequence of events events is different than the standard event when the* the PLU is inoperable. Instead of a fast closure, the TCVs close in servo servo mode and there is no no direct scram on TCV closure. The powerpower and pressure excursion excursion continues until the highhigh pressure scram occurs occurs...-

analyses were performed LRNB analyses performed for a range of power/flow power/flow conditions conditions to support generation generation of .

the thermal limits. Base Base case limiting LRNB transient analysis results used to generate the generate the NEOC and EOCLB operating limits, for both TSSS and NSS insertion insertion times, are shown in in Tables 5.3 and 5.4. Responses of various reactor reactor and plant parameters parameters during the LRNB LRNB eventevent initiated at 100% of rated power power and 105%

105% of rated core flow with TSSS insertion times are shown in Figures 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 several different causes the TSV to close in order to prevent prevent damage to the turbine. The TSV closure creates a compression wave traveling compression traveling through the steam lines into the vessel causing causing a rapid pressurization. The increase pressurization. increase in pressure results in a decrease decrease in core voids, which in turn .

causes a rapid increase increase in power. Closure of the TSV also causes a reactor reactor scram and an RPT which which helps helps mitigate the pressurization pressurization effects. Turbine bypass system operation, which also AREVA AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 Browns Revision Revision 2 Reload Safety Analysis Reload Safety Page 5-4 5-4 credited. The excursion of the core consequences of the event, is not credited.

mitigates the consequences core. power due 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 The consequences of a fast closure of the TCV are very similar to those resulting consequences resulting from a TSV closure.

difference is the time required to close the valves. While the TCV full stroke closure The main difference closure greater than that of the TSV (0.150 sec compared to 0.100 sec), the initial position of the time is greater the dependent on the initial steam flow. At rated power and lower, the initial position of the TCV is dependent the TCV is such that the closure time is less than that of the TSV. However, the TCV closure closure characteristics characteristics are nonlinear nonlinear such that the resulting core pressurization pressurization and LlCPR ACPR may not always bound those of the slower slower TSV closure.

Analyses were performed demonstrating that the TTNB event is equivalent to or bound by the performed demonstrating the .

LRNB event; therefore, the thermal limits established for the LRNB will also protect against the against the TINB event.

TTNB 5.1.3 5.1.3 Feedwater Controller Failure Feedwater Controller Failure (FWCF) feedwater flow due to a failure of the feedwater control system to maximum The -increase in feedwater maximum demand results in an increase in the water level demand level and a decrease temperature at decrease in the coolant temperature inlet subcooling causes an increase in core power. As the the core inlet. The increase in core inletsubcooling the feedwater flow continues maximum demand, continues at maximum water level continues demand, the water continues to rise and eventually eventually reaches the high water level trip setpoint. The initial water level is conservatively reaches conservatively assumed assumed to be be level normal operating range to delay the high-level at the low level maximize the core inlet high-level trip and maximize subcooling resulting from the FWCF. The high water water level trip causes the turbine stop valves to damage to the turbine from excessive order to prevent damage close in order* excessive liquid inventory in the steam line.

traveling back to the core, causing void collapse compression wave traveling Valve closure creates a compression Valve 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 Because of the partially closed initial position of the control closure mode. Because valves, they will typically close faster than the stop valves and control the pressurization portion of the event. However, TCV closure characteristics nonlinear so that the resulting core characteristics are nonlinear core ACPR results may not always bound pressurization and ilCPR pressurization bound those of the slower TSV closure at increases above rated before fast TCV closure). The limiting rated power (steam flow increases limiting of TCV, or AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page 5-5 TSV closure, for the initial operating conditions, conditions, was used iri FWCF analyses, based in the FWCF based on on .

sensitivity analyses. The turbine bypass valves are assumed assumed operable operable and provide some some pressure relief. The core power excursion is mitigated in part by pressure relief, but the primary mechanisms for termination of the event are reactor scram and revoiding of the core.

mechanisms FWCF analyses were performed for aa range of power/flow power/flow conditions to support support generation generation of the thermal limits. Tables 5.5 and 5.6 present the base case limiting FWCF transient analysis analysis results used used to generate generate the NEOC and EOCLB EOCLB operating limits for both TSSS and NSS NSS insertion times. Figures 5.4 - 5.6 show the responses of various reactor and plant parameters parameters during the FWCF event initiated initiated at 100% of rated power and 105% 105% of rated core flow with TSSS TSSS insertion times.

5.1.4 Loss of Feedwater Feedwater Heating Heating

. The loss of feedwater feedwater heating heating (LFWH)

(LFWH) event analysis supports supports an assumed assumed 100°F 100'F decrease ih in the feedwater feedwater temperature. The result is an increaseincrease in core core inlet subcooling, reduces subcooling, which reduces voids, thereby increasing increasing core power power and shifting shifting axial axial power power distribution toward toward the bottom bottom of the core. As a result of the axial power power shift and increased increased core power, voids begin to build up in the bottom region of the core, actingacting as negative feedback to the increased subcooling effect.

increased subcooling The negative negative feedback moderates the core power increase. Although there is aa substantial feedback moderates increase in core thermal power increase power during the event, the increase in steam flow is much less less because a large part of the added added power power is used to overcome overcome the increase in inlet subcooling.

The increase increase in steam steam flow is accommodated accommodated by the the-pressure pressure control system via the TCVs or the turbine bypass valves, so no pressurization cycle.,~pecifiG analysis was performed pressurization occurs. A cycle-specific performed in accordance accordance with the Reference Reference 18 18 methodology methodology to determine determine the change in MCPRMCPR for thethe event. The LFWH results presented in Table 5.7.

results are presented 5.7..

5.1.5 Control Rod Withdrawal Withdrawal Error Error The control rod withdrawal withdrawal error (CRWE) transient is an inadvertent inadvertent reactor operator initiated operator initiated withdrawal withdrawal of a control rod. This withdrawal increases local power and withdrawal increases and core thermal thermal power, lowering the lowering core MCPR.

the core MCPR. TheThe CRWE transient is typically terminated by control rod blocks blocks initiated by the rod block monitor monitor (RBM).

(RBM). The CRWECRWE event was analyzedanalyzed assuming assuming no xenon and allowing credible*instrumentation credible .instrumentation out-of-service out-of-service in the rod block monitor monitor (RBM)

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Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page 5-6 rod pattern. The rated power CRWE results are shown in Table 5.8 for the analytical analytical RBM high high power power setpoint 117%. At all intermediate setpoint values of 107% to 117%. intermediate and lower lower power setpoint values, MCPRpp values for ATRIUM-10 the MCPR ATRIUM-10 and GE14 GE14 fuel bound bound or are equal to the CRWE MCPR MCPR values. Analysis results indicate standard filtered RBM setpoint reductions are supported.

Analyses demonstrate that the 11%

Analyses demonstrate % strain and centerline centerline melt criteria are met for both ATRIUM-10 ATRIUM-10 and GE14 fuel, for the LHGR LHGR limits and their associated presented in associated multipliers presented in Sections 8.2 and 8.3. Recommended Recommended operability operability requirements supporting unblocked unblocked CRWE operation are shown in Table 5.9, based on the SLMCPR SLMCPR values presented presented in Section 4.2.

5.2 Flow Runup Analysis Slow Flow Flow-dependent MCPR and LHGR limits are established Flow-dependent established to support support operation operation at off-rated core flow conditions.

conditions. Limits are based on the CPR and heat heat flux changes experienced experienced by the fuel during slow flow excursions. The slow flow excursion event assumes recirculation recirculation flow control system failure such that core flow increases increases slowly to the maximum maximum flow physically physically attainable.

attainable by the equipment (107% of rated core flow). An uncontrolled uncontrolled increase increase in flow creates creates the potential for a significant increase increase in core power and heat flux. A conservatively conservatively steep flow runup path was used used in the analysis. Analyses were performed performed to support operation operation in all the EOOS EOOS scenarios.

scenarios.

MCPRff limits are determined MCPR determined for both ATRIUM-10 ATRIUM-10 and GE14 fuel. XCOBRA is used to calculate calculate the change in critical power power ratio during a two-loop two-loop flow runup to the maximum flow rate. The The MCPRf limit is set so an increase MCPRf increase in core power, resulting from the maximum maximum increase increase in core flow, assures the TLO safety limit MCPR is not violated. Calculations were performed violated. Calculations performed over aa range of initial flow rates to determine the corresponding corresponding MCPR values causing limiting causing the limiting assembly to be at the safety limit MCPR for the high flow flow condition condition at the end of the flow aUhe excursion.

Analysis Analysis results are presented presented in Table MCPRff limits providing Table 5.10. MCPR providing the required protection protection are presented in Table 8.7. MCPR presented MCPRff limits are applicable for all exposures.

Flow runup analyses were performed performed with CASMO-4/MICROBURN-B2 CASMO-4/MICROBURN-B2 to determine flow-dependent LHGR dependent multipliers (LHGRFAC LHGR multipliers (LHGRFACf)f ) for ATRIUM-10 ATRIUM-1 0 fuel. The analysis assumes assumes recirculation flow increases recirculation increases slowly along along the limiting rod line to the maximum physically maximum flow physically attainable by the equipment. A series of flow excursion excursion analyses analyses were performed at several AREVA AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 , Revision 2 Reload Safety Analysis Page 5-7 exposures exposures throughout the cycle, starting starting from different initial powe rlfl ow conditions. Xenon is power/flow assumed assumed to remain remain constant during LHGRFACff multipliers are established to provide during the event. LHGRFAC provide centerline melt and overstraining protection against fuel centerline overstraining of the cladding during aa flow runup.

LHGRFACf LHGRFACf multipliers are presented in Table 8.11. 8.11. A process consistent with the GNF thermal-mechanical methodology was used to determine mechanical methodology determine flow-dependent flow-dependent LHGRLHGR multipliers (LHGRFACf) multipliers (LHGRFACt)

LHGRFACff multipliers protecting for GE14 fuel. GE14 LHGRFAC protecting against fuel centerline centerline melt, and clad overstrain overstrain during operation at off-rated during operation off-rated core flow conditions, conditions, are presented presented in Table 8.12.

maximum flow during The maximum during a flow excursion in single-loop operation operation is much less than the the maximum fI~w during two-loop operation. Therefore, the flow-dependent maximum flow flow-dependent MCPR limits and LHGR LHGR multipliers for two-loop operation are applicable for SLO.

5.3 Equipment Out-of-Service Scenarios Equipment Scenarios The equipment out-of-service out-of-service (EOOS) scenarios supported (EOOS) scenarios supported for BF1 Cycle 9 operation operation are shown in Table 1.1.

1.1. The EOOS scenarios scenarios supported are:

0 Turbine bypass valves out-of-service (TB1VOOS) out-of-service (TBVOOS) ,

- EOC recirculation pump trip out-of-service (EOC-RPT-OOS) out-of-service (EOC-RPT -~OS)

0 Feedwater heaters out-of-service Feedwater heaters out-of-service (FHOOS)

- unbalance out-of-service Power load unbalance out-of-service (PLUOOS)

- EOC-RPT-OOS Combined EOC-RPT TBVOOS

-OOS and TBVOOS

- Combined EOC-RPT EOC-RPT-OOS-OOS and FHOOS FHOOS

- EOC-RPT-OOS and PLUOOS Combined EOC-RPT-OOS PLUOOS

- Combined TBVOOS TBVOOS and FHOOSFHOOS

- Combined TBVOOS PLUOOS TBVOOS and PLUOOS

- Combined Combined FHOOS and PLUOOS PLUOOS

- Combined EOC-RPT-OOS, TBVOOS, Combined EOC-RPT-OOS, TBVOOS, and FHOOS FHOOS

- Combined EOC-RPT-OOS, Combined EOC-RPT-OOS, TBVOOS, TBVOOS, and PLUOOS PLUOOS

- Combined EOC-RPT-OOS, FHOOS, and PLUOOS Combined EOC-RPT-OOS, PLUOOS

- Combined Combined TBVOOS, TBVOOS, FHOOS, and PLUOOS PLUOOS

- Combined EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS Combined EOC-RPT-OOS, PLUOOS

- Single-loop Single-loop operation operation (SLO)

(SLO) - recirculation loop out-of-service out-of-service The base case thermal limits support The operation with 1 MSRV support operation MSRV out-of-service, up to 2 TIPOOS (or the equivalent equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.

out-of-service. The The analyses presented in this section analyses section also include these EOOS conditions conditions protected by the base case limits. No further discussion presented in this section.

discussion for these EOOS conditions is presented AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision .2 Revision*2 Reload Safety Safety Analysis Page 5-8 5.3.1 5.3.1 TBVOOS TBVOOS The effect of operation with TBVOOS TBVOOS is a reduction in the system pressure relief capacity, which makes the pressurization pressurization events more severe. While the base case LRNB lRNB and TTNB TINB events are analyzed events analyzed assuming the turbine turbine bypass valves out-of-service, operation operation with TBVOOS has an adverse effect on the FWCF event. Analyses of the FWCF event event with TBVOOS TBVOOS were performed to establish the TBVOOS operating limits.

5.3.2 EOC-RPT-OOS EOC-RPT-OOS When EOC-RPT is inoperable, no credit is assumed for recirculation pump trip on TSV position or TCV fast closure. The function function of the EOC-RPT EOC-RPT feature is to reduce reduce the severity severity of the core power excursion power excursion caused caused by the pressurization pressurization transient. The RPT accomplishes accomplishes this by helping helping revoid the core, thereby reducing reducing the magnitude magnitude of the reactivity insertion resulting from the the pressurization pressurization transient. Failure of the RPT feature can result in higher operating limits.

performed for lRNB Analyses were performed LRNB and FWCF events events assuming EOC-RPT-OOS.

assuming EOC-RPT-OOS.

5.3.3 FHOOS

. FHOOS The FHOOS scenario scenario assumes assumes a feedwater feedwater temperature 650 F (55°F + 10°F bias) at temperature reduction of 65°F rated power and steam flow. The effect reduced feedwater effect of reduced feedwater temperature temperature is an increase increase in core core inlet subcooling, changing axial power shape and and core void fraction. Additionally, steam flow for a given power level decreases because more power is required to increase decreases because increase coolant coolant enthalpy enthalpy to saturated conditions. Generally, lRNB saturated LRNB and TTNB events are less severe with FHOOS FHOOS decrease in steam flow relative to nominal conditions due to the decrease conditions conditions. FWCF events with nominal conditions.

FHOOS conditions conditions are generally generally worse due to aa larger change in inlet subcooling subcooling and core core.

pressurization phase of the event.

power prior to the pressurization Separate Separate FHOOS limits are not needed EOCLB exposure since aa needed for operation beyond the EOClB feedwater temperature reduction is included feedwater included to attain the additional cycle extension extension to the the FFTR/coastdown FFTR/coastdown exposure, i.e., FFTR is equivalent equivalent to FHOOS since both are based on the the feedwater temperature reduction.

same feedwater reduction.

AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 99 *Revision 2

-Revision Reload Safety Analysis Page 5-9 5.3.4 PLUOOS PLUOOS The PLU device in normal operation is assumed to not function below 50% power. PLUOOS is is assumed to mean mean the PLU PLU device does not function for any power level, level, and does not initiate initiate fast TCV closure. The following PLUOOS scenario scenario was assumed for the load reject event.

Initially, the TCVs remain in pressure/speed control mode. There is no direct scram or Initially, or EOC-RPT EOC-RPT on valve motion.

Loss of load results in in increasing turbine speed. Depending on initial power, a turbine turbine overspeed overs peed condition may be reached to initiate a turbine trip resulting in scram and EOC-RPT.

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

Analyses were performed performed for LRNB events assuming PLUOOS.

5.3.5 Combined EOC-RPT-OOS Combined EOC-RPT-OOS and TBVOOSTBVOOS FWCF analyses analyses with both EOC-RPT EOC-RPT-OOS -OOS and TBVOOS were performed. Operating limits for this combined EOOS scenarioscenario were established using these FWCF results and results results previously discussed.

5.3.6 Combined EOC-RPT-OOS Combined EOC-RPT-OOS and FHOOS FHOOS FWCF analyses EOC-RPT-OOS and FHOOS were performed. Operating limits for analyses with both EOC-RPT-OOS this combined EOOS scenario were established using these FWCF results and results results previously previously discussed. Separate EOC-RPT-OOS discussed. Separate EOC-RPT-OOS and and FHOOS FHOOS combined combined limits are are not needed for operation operation beyond beyond the EOCLB exposure exposure since since a FW temperature temperature reduction reduction is included inclu~ed to attain the additional additional cycle extension extension to the FFTRlcoastdown FFTRlcoastdown exposure.

5.3.7 Combined EOC-RPT-OOS EOC-RPT-OOS and and PLUOOS PLUOOS LRNB analyses LRNB EOC-RPT-OOS and PLUOOS were performed.

analyses with both EOC~RPT-OOS performed. Operating Operating limits limits for for this this combined combined EOOS scenario were established using EOOS scenario using these these LRNB LRNB results and results previously previously discussed.

discussed.

5.3.8 5.3.8 Combined Combined TBVOOS TBVOOS and and FHOOS FHOOS FWCF analyses FWCF analyses with with both TBVOOS TBVOOS and and FHOOS FHOOS were performed.

performed. Operating Operating limits limits for this this combined combined EOOS EOOS scenario scenario were established established using using these FWCF FWCF results results and results previously previously AREVA AREVANP NP Inc.

Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page 5-10 5-10 discussed. Separate Separate TBVOOS and FHOOS combined limits are not needed needed for operation beyond beyond the EOCLB exposure exposure since a FW temperature reduction is included to attain the temperature reduction the additional additional cycle extension to the FFTRlcoastdown FFTR/coastdown exposure.

5.3.9 Combined TBVOOS and PLUOOS PLUOOS established to support operation with both TBVOOS Limits were established TBVOOS and PLUOOS.

PLUOOS. No additional analyses are are required to construct construct MCPRp MCPRp operating operating limits for TBVOOS TBVOOS and PLUOOS PLUOOS sincesince independent EOOS TBVOOS and PLUOOS are independent EOOS conditions (TBVOOS only impacts FWCF FWCF events; PLUOOS only impactsimpacts LRNB events).

5.3.10 Combined Combined FHOOS and PLUOOS PLUOOS LRNB analyses analyses with both FHOOS and PLUOOS were performed. performed. Operating limits for this this combined EOOS scenario were established established using these LRNB results and results previously discussed. Separate FHOOS and PLUOOS combined limits are not needed for operation discussed. Separate operation temperature reduction is included beyond the EOCLB exposure since a FW temperature included to attain attain the the additional extension to the FFTR/coastdown additional cycle extension FFTRlcoastdown exposure.

5.3.11 5.3.11 Combined EOC-RPT-OOS.

EOC-RPT-OOS, TBVOOS.

TBVOOS, and FHOOS FHOOS FWCF analyses analyses with EOC-RPT-OOS, EOC-RPT-OOS, TBVOOS, TBVOOS, and FHOOS were performed.

performed. Operating Operating limits limits for this combined EOOS scenario using these FWCF results and results scenario were established uSing results previously discussed. Separate Separate EOC-RPT-OOS, EOC-RPT-OOS, TBVOOS, TBVOOS, and FHOOS combined limits are not needed for operation operation beyond beyond the EOCLB exposure exposure since a FW temperature temperature reduction reduction is included to attain the additional additional cycle cycle extension extension to the FFTRlcoastdown FFTR/coastdown exposure.

5.3.12 Combined EOC-RPT-OOS, TBVOOS, and PLUOOS EOC-RPT-OOS. TBVOOS. PLUOOS Limits were established established to support operation with EOC-RPT-OOS, EOC-RPT-OOS, TBVOOS, TBVOOS, and PLUOOS. No additional analyses analyses are required to construct MCPR MCPRpp operating limits for EOC-RPT EOC-RPT-OOS,

-OOS, TBVOOS, and PLUOOSPLUOOS since TBVOOS TBVOOS and PLUOOS PLUOOS are independent independent EOOS EOOS conditions conditions (TBVOOS only impacts impacts FWCF events; PLUOOS only impacts LRNB events).

5.3.13 Combined EOC-RPT-OOS, EOC-RPT-OOS. FHOOS.FHOOS, and PLUOOS PLUOOS LRNB analyses analyses with EOC-RPT-OOS, EOC-RPT-OOS, FHOOS, and PLUOOS were performed. Operating Operating limits limits for this combined EOOS scenario were established EOOS scenario established using using these LRNB results and results results AREVA AREVA NP Inc.

ANP-2864(NP)

Browns Browns Ferry Unit 1 Cycle 9 .-Revision Revision 2 Reload Safety Analysis Analysis Page 5-11 5-11 previously discussed.

discussed. Separate EOC-RPT-OOS, EOC-RPT-OOS, FHOOS, FHOOS, and PLUOOS combined limits are not needed for operation beyond the EOCLB exposure

. needed exposure since aa FW temperature reduction reduction is included to attain the additional FFTR/coastdown exposure.

additional cycle extension to the FFTRlcoastdown 5.3.14 Combined Combined TBVOOS, FHOOS, and PLUOOS TBVOOS. FHOOS. PLUOOS Limits were established established to support support operation operation with TBVOOS, FHOOS, and PLUOOS. No TBVOOS, FHOOS, additional additional analyses are required to construct MCPR MCPRPp operating operating limits for TBVOOS, FHOOS, FHOOS, and PLUOOS since TBVOOS and PLUOOS PLUOOS are independent independent EOOS EOOS conditions (TBVOOS only only impacts FWCF events; PLUOOS PLUOOS only impacts impacts LRNB LRNB events). Separate Separate TBVOOS, TBVOOS, FHOOS, and PLUOOS combined combined limits are not needed needed for operation operation beyond beyond the EOCLB EOCLB exposure since a FW temperature temperature reduction reduction is included to attain the additional additional cycle extension extension to the the FFTR/coastdown exposure.

FFTR/coastdown 5.3.15 Combined EOC-RPT-OOS, TBVOOS, FHOOS.

EOC-RPT-OOS. TBVOOS. FHOOS, and PLUOOS PLUOOS established to support operation with EOC-RPT-OOS, Limits were established EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS. No additional PLUOOS. additional analyses are required required to construct MCPR MCPRpp operating operating limits for EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS EOC-RPT-OOS, PLUOOS since TBVOOS and PLUOOS PLUOOS are independent EOOS conditions (TBVOOS only impacts FWCF events; PLUOOS only impacts independent impacts EOC-RPT-OOS, TBVOOS, LRNB events). Separate EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS PLUOOS combined limits combined limits*

are not needed needed for operation beyond beyond the EOCLB exposure since a FW temperature temperature reduction reduction is included to attain the additional cycle extension to the FFTRlcoastdown FFTR/coastdown exposure.

5.3.16 Single-Loop Single-Loop Operation Operation In SLO, the two-loop operation ACPRs and LHGRFAC multipliers remain applicable.

operation ilCPRs applicable. The onlyonly impacts on the MCPR, LHGR, and MAPLHGR MAPLHGR limits for SLO are an increase of 0.03 in in the the SLMCPR SLMCPR as discussed discussed in Section 4.2, and the application application of an SLO MAPLHGR MAPLHGR multiplier multiplier discussed discussed in Section 8.3. The net result is a 0.03 increase Section 8,3. increase in the base case MCPRP MCPRp limits and a decrease in the MAPLHGR decrease MAPLHGR limit. The same situation is true for the EOOS forthe Adding EOOS scenarios. Adding 0.03 to the corresponding corresponding two-loop two-loop operation operation EOOS MCPRP MCPRp limits results in SLO MCPRP MCPRp limitslimits for the EOOS conditions. The TLO EOOS LHGRFAC multipliers remain applicable EOOS LHGRFAC applicable in SLO.

AREVA AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page 5-12 5-12 5.4 Licensing Power Licensing Shape Power Shape licensing axial power profile used by AREVA for the plant transient analyses The licensing analyses bounds the the projected end of full power projected power axial power profile. The conservative conservative licensing axial power profile profile generated generated at the EOCLB core average exposure of 29,748 MWd/MTU average exposure MWd/MTU is given in Table Table 5.11.

5.11.

Cycle 9 operation is considered to be in compliance when:

normalized power The normalized generated in the bottom 7 nodes power generated projected EOFP nodes from the projected EOFP solution at the state state conditions conditions provided provided in Table 5.11 is greater than the normalized normalized generated in the bottom 7 nodes in the licensing basis axial power profile.

power gene-rated

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

EOCLB.

If the criteria cannot (i.e., not all 7 nodes are at a higher cannot be fully met (Le., higher power power than the licensing licensing profile), the licensing licensing basis may nevertheless nevertheless remain valid but further assessment assessment will bebe required.

The licensing basis power profile in Table 5.11 was calculated using using the MICROBURN-B2 MICROBURN-B2 code.

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

POWERPLEX-III*.

Note that the power profile comparison should be done without incorporating instrument incorporating instrument updates to the axial profile because because the updated updated power is not used in the core monitoring monitoring system to accumulate accumulate assembly burnups.

POWERPLEX is a trademark of AREVA NP registered in the United States and various other POWERPLEX is a trademark of AREVA NP registered in the United States and various other countries.

AREVA AREVA NP Inc.

ANP-2864(NP)

Browns Browns Ferry Unit Unit 1 Cycle 9.

9 -Revision 2 Reload Reload Safety Safety Analysis Analysis Page Page 5-13 5-13 Table 5.1 Exposure Exposure Basis for Browns Ferry Ferry Unit 1 I Cycle 9 Transient Analysis Transient Analysis Core Core Exposure Average Exposure (MWd/MTU)

(MWd/MTU) Comments Comments 11,635 11,635 Beginning of cycle cycle 27,135 Break point for exposure-limits MCPRpp limits dependent MCPR (NEOC) 29,748 29,748 Design basis rod patterns to EOFP + + 15 EFPD (EOCLB) 31,270 Maximum licensing licensing core exposure exposure - including FFTR FFTR

/Coastdown 24,207 (16,928)* Cycle 8 EOC (nominal (nominal value) 23,193 (15,913)* Cycle 8 EOC (short window) 24,613 (17,333)* Cycle 8 EOC (long window)

Corresponding Cycle 8 cycle exposure.

Corresponding Cycle 8 cycle exposure.

AREVA AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Safety Analysis Reload Safety Analysis Page 5-14 5-14 Table 5.2 Scram Scram Speed Insertion Insertion Times Times TSSS TSSS NSS NSS Control Control Rod Analytical Analytical Position Position. Time Time Time (notch) (sec) (sec) 48 (full-out)

(full-out) 0.00 0.00 48 0.20 0.20 46 0.46

0.46 0.421 36 1.09 1.09 0.991 26 1.86 1.62 1.62 6 3.50 3.04 3.04 o

0 (full-in) 4.0 3.5 3.5 AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis 5-15 Page 5-15 Table Table 5.3 5.3 NEOC Base Case LRNBLRNB Transient Results Power ATRIUM-10 ATRIUM-10 GEI4 Power ATRIUM-10 ATRIUM-10 GE14

(% rated) ACPR

~CPR HFR ACPR

~CPR Insertion Times TSSS Insertion 100 0.35 1.26 1.26 0.33 0.33 90 0.38 1.30 0.35

-77.6 0.39 1.30 0.35 0.35 50 0.77 1.67 1.67 0.75 40 0.84 1.74 1.74 0.82 26 1.01 1.89 1.89 1.00 1.00 23 at > 50%F below Pbypass 1.04 1.04 1.92 1.92 1.03 1.03 23 at <:::; 50%F below below Pbypass 0.92 1.70 1.70 0.92 NSS Insertion Insertion Times Times 100 100 0.31 1.23 0.29 90 0.35 1.27 1.27 0.32 77.6 77.6 0.36 1.28 *0.33 0.33 50 0.76 1.66 1.66 0.74 40 0.83 1.73 1.73 0.81 26 26 1.00 1.00 1.89 1.89 0.99 AREVA NP Inc.

, ANP-2864(NP)

-Browns Browns Ferry Unit 1 Cycle Cycle 9 Revision Revision 2 Reload Safety Analysis Reload Analysis Page 5-16 5-16 Table 5.4 EOCLB Base Base Case LRNB LRNB Transient Results Transient Results Power ATRIUM-10 ATRIUM-10 GE14 Power ATRIUM-10 ATRIUM-10 GE14

(% rated)

(% ACPR

~CPR HFR ACPR

~CPR Insertion Times TSSS Insertion 100 0.37 1.31 0.37 90 0.39 1.35 1.35 0.38 77.6 0.40 1.34 1.34 0.39 50 0.77 1.70 1.70 0.75 40 0.84 1.75 1.75 0.82 26 1.01 1.89 1.89 1.00 1.00 23 at > 50%F below Pbypass Pbypass 1.04 1.04 1.92 1.92 1.03 1.03 23 at <~ 50%F below PPbpass bypass 0.92 1.71 0.92 Insertion Times NSS Insertion 100 100 0.35 1.29 1.29 0.34 90 0.37 1.33 1.33 0.36 77.6 0.38 1.33 1.33 0.36 50 0.76 1.69 1.69 0.74 40

.40 0.83 1.74 1.74 0.81 26 1.00 1.00 1.89 1.89 0.99 AREVA NPNP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Safety Reload Safety Analysis Analysis Page 5-17 5-17 Table 5.5 NEOC Base Case FWCF Case FWCF Transient Results Transient Results Power ATRIUM-10 ATRIUM-10 GE14 Power ATRIUM-10 ATRIUM-10 GE14

(% rated) . ACPR

~CPR HFR ACPR

~CPR TSSS Insertion TSSS Insertion Times 100 0.40 1.34 1.34 0.37 90 0.46 1.42 0.44 0.44 77.6 0.52 1.47 0.50 60 0.64 1.54 0.61 55 0.67 1.57 0.65 0.65 50 0.71 1.61 0.70 0.70 40 0.80 1.70 0.83 26 1.15 1.15 2.06 1.13 1.13 26 at >> 50%F below Pbypass below Pbypass 1.50 2.49 1.61 26 at :S< 50%Fbelow 50%F below PbYPass Pbypass 1.46 2.36 1.53 1.53 23 at >> 50%F below below PbypaSS Pbypass 1.63 2.62 1.73 1.73 23 at5 <50%F at :S Pbypass 50%F below Pbypass 1.58 2.41 1.65 1.65 NSS Insertion NSS Insertion Times Times 100 0.36 1.31 0.34 0.34 90 90 0.43 1.39 1.39 0.41 77.6 0.50 1.45 1.45 0.48 60 0.61 1.53 1.53 0.59 55 0.65 0.65 1.56 1.56 0.63 50 0.69 1.60 1.60 0.68 40 0.78 0.78 1.69 1.69 0.82 26 26 1.14 1.14 2.05 2.05 1.12 1:12 AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page 5-18 5-18 .

Table 5.6 EOCLB Base Case FWCFFWCF Results Transient Results Power .ATRIUM-10 ATRIUM-10 ATRIUM-10 ATRIUM-10 GE14 GE14

(%

(% rated) ~CPR ACPR HFR ACPR

~CPR Insertion Times TSSS Insertion 100 100 0.40 1.36 1.36 0.41 90 0.46 1.43 1.43 0.46 77.6 0.52 1.50 1.50 0.51 0.51 60 60 0.64 1.55 1.55 0.61 0.61 55 55 0.67 1.57 1.57 0.65 50 0.71 0.71 1.61 0.70 40 0.80 1.70 1.70 0.83 26 26 1.15 1.15 2.06 2.06 1.13 1.13 26 at > 50%F below below Pbypass PbypasS 1.50 1.50 2.49 2.49 1.61 26 at:s; at < 50%F below Pbypass 1.46 1.46 2.36 2.36 1.53 1.53 23 at > 50%F below below Pbypas; Pbypass 1.63 1.63 2.62 2.62 1.73 1.73 23 at :s;< 50%F below Pbypass 1.58

1.58 2.41 1.65 1.65 NSS Insertion Insertion Times Times 100 100 0.37 0.37 1.33 1.33 0.38 90 90 0.43 0.43 1.42 1.42 0.44 77.6 77.6 0.50 0.50 1.49 1.49 0.49 0.49 60 60 0.61 1.55 1.55 0.59 55

.55 0.65 0.65 1.56 1.56 0.63 50 50 0.69 0.69 1.60

1.60 0.68 40 0.78 0.78 1.69 1.69 0.82 0.82 26 26 1.14 1.14 2.05 1.12 1.12 AREVA AREVA NP Inc.

ANP-2864(NP)

. Browns Ferry Unit 1 Cycle 9 Revision 2

. Revision Analysis Reload Safety Analysis Page 5-19 5-19 Table 5.7 Loss of Feedwater Table FeedwaterHeating Heating Results Transient Analysis Results Power Power ATRIUM-10/GE14 ATRIUM-10/GE14

(% rated)

(% ACPR

~CPR 100 100 0.09 0.09 90 90 0.10 0.10 80 0.11 0.11 70 0.12 0.12 60 0.13 0.13 50 0.15 0.15 40 40 0.18 0.18 30 0;22 0.22 25 0.26 AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page 5-20 Table 5.8 Control Rod Withdrawal Withdrawal Error Error

~CPR Results ACPR Results Analytical RBM Setpoint Setpoint (without filter) ACPR*

LlCPR* CRWE

(%) MCPRt MCPRt 107 0.24 1.31 111 0.28 1.35 1.35 114 0.32 1.39 1.39 117 0.33 1.40 1.40

Results are for the most limiting of the ATRIUM-10 or GE14 fuel in the core.

Results are for the most limiting of the ATRIUM-10 or GE14 fuel in the core .

. t For rated power and a 1.07 SLMCPR..

For rated power and a 1.07 SLMCPR..

AREVA NP Inc.

ANP-2864(NP)

Browns Browns Ferry Unit Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page 5-21 Page Table 5.9 RBM Operability Requirements Operability Requirements Applicable Applicable Thermal Thermal Power ATRIUM-10/GE14 ATRIUM-10/GE14

(% rated)

(%rated) MCPR MCPR 1.80 18 1.80 TLO L

TLO

_>27% and < 90%

~ 27% and < 90% 1.85 SLO 1.85 SLO

~90%

>90% 1.44 TLO*

TLO AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Page 5-22 Table Flow-Dependent Table 5.10 Flow-Dependent MCPR Results Results Core ATRIUM-10 ATRIUM-10 GE14 GE14 Flow Limiting Limiting Limiting

(% rated)

(% MCPR MCPR MCPR 30 1.25 1.25 1.25 40 . 1.23 1.22 1.22 50 1.25 1.23 1.23 60 1.24 1.23 1.23 70 1.21 1.22 1.22 80 1.19 1.18 1.18 90 1.17 1.17 1.16 1.16 100 1.15 1.15 1.14 1.14 107 1.07 1.07 1.07 1.07 AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit Unit-11 Cycle 9 Revision 2 Reload Safety Analysis Page 5-23 5-23 Table 5.11 Licensing Licensing Basis Core Average Average

.Axial Power Power Profile Profile State Conditions for State Conditions for Evaluation Power Shape Evaluation Power, MWt . 3952.0 3952.0 Core pressure, psia 1050.0 1050.0 Inlet subcooling, Btu/Ibm Btu/lbm 25.6 25.6 Flow, Mlb/hr 107.6 107.6 Control state state ARO ARO average exposure Core average exposure 29,748 (EOCLB), MWd/MTU Licensing Axial Power Profile Profile (Normalized)

(Normal ized)

Node Power Power Top 25 0.180 24 0.545 23 0.716 0.716 22 0.815 0.815 21 0.876 20 0.921 19 0.964 18 18 1.014 1.014 17 17 1.071 16 16 1.145 1.145 15 15 1.210 1.210 14 14 1.334 1.334 13 13 1.372 1.372 12 12 1.385 1.385 11 11 1.374 1.374 10 10 1.347 1.347 9 1.306 1.306 8 1.244 1.244 7 1.167 1.167 6 1.089 1.089 5 1.028 1.028 4 0.991 0.9.91 3 0.938 2 0.751 Bottom 1 0.216 0.216 AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis.

Reload Safety Analysis Page 5-24 5-24 5

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ANP-2864(NP)

Browns Ferry Unit Unit 1-Cycle 1 Cycle 9. Revision 2*

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ANP-2864(NP)

Browns Ferry Unit Unit 1 Cycle 9 Revision 2 Revision Safety Analysis Reload Safety Analysis Page Page 5-26 5-26 1280.0-r-----------------------------------,

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ANP-2864(NP)

Browns Ferry Unit Unit 1 Cycle 9 Revision 2 Revision Reload Reload Safety Analysis Analysis Page 5-27 500.0~---------:--------------------~------,

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-Figure OOP/1 05F - TSSS TSSS Parameters Key Parameters AREVA AREVA NP Inc.

ANP-2864(NP)

Browns Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Analysis Reload Safety Analysis 5-28 Page 5-28 70.0 c-c o0 Q)

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ANP-2864(NP)

Browns Browns Ferry Unit 1 Cycle Cycle 9 Revision 2 Revision.2 Reload Reload Safety Analysis Analysis Page 5 5-29 1300.0.----------------------------------,

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ANP-2864(NP)

Unit11 Cycle 9 Browns Ferry Unit Revision 2 Reload Safety Analysis Page 6-1 6.0 Postulated Postulated Accidents Accidents 6.1 Loss-of-Coolant-Accident (LOCA)

Loss-of-Coo/ant-Accident (LOCA)

As discussed in Section 2, the LOCA models, evaluation, and results are the same for all three three units for a full core of ATRIUM-10 ATRIUM-10 fuel. The basis for applicability of PCT results from full cores cores of ATRIUM-10 fuel (based on AREVA methods) and GE14 fuel (based on GNF methods) methods) for a mixed (transition) core is provided provided in Reference Reference 39 Appendix A. Thermal-hydraulic Thermal-hydraulic characteristics of the GE14 and ATRIUM-10 characteristics ATRIUM-10 fuel designs designs are similar similar as presented presented in Reference Reference

3. Therefore, the core response response during during a LOCA will not be significantly significantly different different for a full core of GE14 fuel or a mixed core of GE14 and ATRIUM-10 ATRIUM-10 fuel. In addition, sincesince about about 95% of the the outside the core region, slight changes reactor system volume, is 'outside changes in core volLime volume and fluid fluid energy due to fuel design differences differences will produce produce an insignificant insignificant change change in total system volume and energy. Therefore, Therefore, the current GE14 LOCA ~OCA analysis and resulting licensing PCT and MAPLHGR MAPLHGR limits remain applicable.

applicable.

The results of the ATRIUM-10 ATRIUM-10 LOCA analysis are presented presented in References References 19 and 20. The The MAPLHGR limits presented in Reference MAPLHGR Reference 20 remain valid for ATRIUM-10 ATRIUM-10 fuel.

Limiting Break: ft2 split 0.5 ff Recirculation Pump Discharge Recirculation Line Discharge Line power Battery (DC) power Based Based on the PCT results in Reference Reference 20 and subsequent subsequent evaluations evaluations to provide provide 10 CFR 50.46 reporting estimates (Reference 40, equally applicable estimates' (Reference applicable for Unit 1), the current current licensing PCT is provided licensing provided below. The MCPR value used in the LOCA analyses analyses is less than the the rated power MCPR limits.

power MCPR (OF)

Initial PCT CF) 2007 (Reference

, (Reference 20) 10 CFR 50.46 Estimates -5 cumulative value CF) net cumulative (OF)

(Reference 40)

(Reference .

CurrentLicensing Current Licensing PCT (OF) (OF) 2002 The peak local metal-water metal-water reaction for the limiting PCT PCT lattice lattice design is 1.71%. maximum 1.71 %. The maximum core wide metal-water metal-water reaction (for hydrogen generation) generation) for a full ATRIUM-10 ATRI UM-1 0 core is <1.0%.

AREVA NP Inc.

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Browns Ferry Unit Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page 6-2 6-2 ATRIUM-10 reload fuel PCT was calculated to be 1979°F The cycle specific ATRIUM-10 1979 0 F (1984°F - 5°F);

50 F);

therefore, therefore, in terms of PCT, the limiting neutronic neutronic design Reference 20 remains design used in Reference remains bounding. The peak local metal-water metal-water reaction and total core wide metal-water metal-water reaction were calculated to be 1.72%

1.72% and < 1.0%, respectively. When compared compared to the acceptance criteria of acceptance criteria less than 17%

17% local cladding oxidation thickness, the local metal-water metal-water reaction reaction result remains remains acceptable.

Analyses and results support the EOD and EOOS conditions listed in Table 1.1. 1.1. Note:

EOC-RPT-OOS, PLUOOS, and TIPOOS/LPRM TBVOOS, EOC-RPT-OOS, TIPOOS/LPRM out-of-service out-of-service have no direct influence on the LOCA LOCA events.

The GE14 LOCA analysis results are presented References 21 and 26. No system presented in References modifications have been made at BF1 that would invalidate the reactor BF1that reactor system response system response assumed assumed in the GE14 LOCA analysis analysis of record.

6.2 Control Rod Drop Control Drop Accident (CRDA)

Plant startup utilizes utilizes a bank position position withdrawal sequence sequence (BPWS) including rod worth minimization strategies. CRDA evaluation was performed minimization* performed for both A and B sequence startups s~quence startups consistent consistent with the withdrawal sequences specified by TVA. Approved AREVA generic CRDA sequences specified methodology is described in Reference 22. Subsequent calculations have have-shown the the methodology is applicable to fuel modeled with the CASM04/MICROBURN-:B2 CASMO4/MICROBURN-B2 code code system.

demonstrate the maximum Analysis results demonstrate maximum deposited deposited fuel rod enthalpy is less than 280 cal/g; the estimated number of fuel rods that exceed exceed the fuel damage threshold of 170 cal/g is less less than the number number of failed rods assumed in FSAR FSAR (850 rods).

dropped control Maximum dropped control rod worth, mk 11.17 11.17 average Doppler Core average Ak/k/°F Doppler coefficient, L\k/kfF 1066

-10.51 xx 10-

-10.51 Effective delayed delayed neutron neutron fraction 0.0052 0.0052 Four-bundle Four-bundle local peaking factor 1.382 1.382 Maximum deposited fuel rod enthalpy, cal/g Maximum 194.2 194.2 Maximum number Maximum number of rods exceeding exceeding 170 cal/g 366 AREVA NP Inc.

AREVA

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis 6-3 Page 6-3 6.3 Fuel and Equipment Fuel Equipment Handling HandlingAccident The fuel handling accident radiological analysis implementing implementing the alternate alternate source term (AST) approved in Reference as approved Reference 27 was performed performed with consideration of ATRIUM-10 ATRIUM-10 core source source terms. Fuel assembly and reactor core isotopic inventories inventories used as input to design basis basis radiological radiological accident analyses are applicable to all three units (Reference (Reference 27).The number of 27).The number failed fuel rods for the ATRIUM-10 fuel as previously Reference 28 for use in previously provided to TVA in Reference in the AST analysis is unchanged.

unchanged. No other aspect of utilizing the ATRIUM-10 ATRIUM-10 fuel affects the the current current analysis; therefore, the AST analysis remains bounding for Cycle 9.

6.4 Fuel Loading Error Fuel Loading Error(Infrequent (Infrequent Event)

Event)

There are two types of fuel loading errors possible in a BWR - the mislocation mislocation of a fuel assembly assembly in a core position prescribed prescribed to be loaded loaded with another fuel assembly, and the the misorientation of a fuel assembly misorientation assembly with respect to the control blade. As described described in Reference Reference 23, the fuel loading error is characterized characterized as an infrequent infrequent event. The acceptance acceptance criteria is that the offsite dose consequences consequences due to the event shall not exceed aa small fraction of the 10 CFR 50.67 limits.

6.4.1 Mislocated Fuel Bundle Mislocated Bundle AREVA AREVA has performed performed a bounding bounding fuel mislocation mislocation error analysis analysis and has demonstrated demonstrated applicability of the bounding results. The analysis continued applicability analysis considered considered the impact of aa mislocated mislocated assembly against potential fuel rod failure mechanisms mechanisms due to increased increased LHGR and reduced CPR. Based reduced Based on the analyses, the offsite dosedose criteria (a small fraction 6f of 10 CFR CFR 50.67) is conservatively conservatively satisfied. A dose consequence consequence evaluation is not necessary necessary since no rod approaches the fuel centerline melt or 1 approaches 1%

% strain limits, and less than 0.1%

0.1 % of the fuel rods are expected to experience experience boiling transition.

transition.

6.4.2 Bundle Misoriented Fuel Bundle AREVA AREVA has performed a bounding fuel assembly misorientation analysis. The analysis was has performed was performed assuming that the limiting assembly performed assembly was loaded in the worst orientation orientation (rotated 180'), while simultaneously 180°), simultaneously producing sufficient power to be on the MCPR operating operating limit as ifif it were were oriented correctly. The analysis analysis demonstrates demonstrates the small fraction of 10 CFR 50.67 offsite offsite dose conservatively satisfied. A dose consequence evaluation dose criteria is conservatively evaluation isis not necessary necessary since AREVA NP Inc.

AREVA

.A.NP-2864(NP)

ANP-2864(NP)

Cycle 9 Browns Ferry Unit 1 Cycle Browns -Revision 22

'Revision Reload Safety Analysis Reload Analysis Page Page 6-4 6-4 rod approaches no rod approaches fuel centerline melt or 11% limits, and

% strain limits, and less than than 0.1 0.1% fuel rods

% of the fuel rods to experience boiling transition.

are expected to transition.

AREVA NP Inc.

AREVA Inc.

ANP-2864(NP)

Browns Ferry Unit 1 I Cycle 99 Revision 2 Reload Safety Analysis Page 7-1 7.0 Special Analyses Special Analyses 7.1 ASME Overpressurization ASME Overpressurization Analysis This section describes the maximum overpressurization overpressurization analyses analyses performed to demonstrate demonstrate compliance with the ASME Boiler compliance Boiler and Pressure Vessel Code. The analysis Pressure Vessel analysis shows that the the safety/relief valves have sufficient capacity safety/relief capacity and performance performance to prevent the reactor vessel vessel pressure pressure from reaching reaching the safety limit of 110% of the design pressure.

MSIV closure, TSV closure, aild and TCV closure (without bypass) analyses were performed with the AREVA plant simulator code COTRANSA2 (Reference 12) for 102% power and both 99%

COTRANSA2 (Reference and 105% highest cycle exposure.

105% flow at the highest exposure. The MSIV MSIV closure event is similar to the other steam line valve closure events in that the valve closureclosure results in a rapid pressurization pressurization of the the core. The increase in pressure pressure causes a decrease decrease in void which in turn causes a rapid increase increase in power. The turbine bypass valves do not impact the system response and are not modeled in the analysis. The following assumptions assumptions were mademade in the analysis.

- The most critical active component (direct scram on valve position) active component position) was assumed to fail.

However, scram scram on high neutron neutron flux and high dome dome pressure is available.

pressure

- To support operation with 1 MSRVOOS, MSRVOOS, the plant configuration configuration analyzed analyzed assumed that one of the lowest setpoint MSRVs lowest setpoint MSRVs was inoperable.

inoperable.

- insertion times were used.

TSSS insertion

- The initial dome pressure was set at the maximum allowed by the Technical Specifications plus an additional Specifications additional 5 psi bias, 1070 psia (1055 psig).

- A fast MSIV MSIV closure time of 3.0 seconds was used.

- The analytical limit ATWS-RPT ATWS-RPT setpoint and function function were assumed.

assumed ....

Results of the MSIVMSIV closure, TCV closure, and TSV closure overpressurization overpressurization analyses analyses are presented in Table 7.1. 7.1. Various reactor plant parameters parameters during the limiting MSIV closure event are presented in Figures 7.1-7.4. The maximum pressure of 1340 1340 psig occurs in the lower plenum. The maximum dome pressure pressure for the same event is 1308 psig. Results demonstrate demonstrate the maximum vessel pressure 1375 psig and dome pressure limit of 1325 pressure limit of .1375 1325 psig are not exceeded exceeded for any analyses.

Pressure results include include a 7-psi increase increase to bound a bias in the void-quality void-quality correlations. The The void-quality bias is further discussed void-quality discussed in Reference Reference 32.

AREVA NP Inc.

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Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page 7-2 7-2 7.2 A TINS Event Evaluation A TWS Evaluation 7.2.1 ATWS Overpressurization Analysis ATWSOverpressurization Analysis This section describes analyses performed to demonstrate that the peak vessel vessel pressure pressure for the the event is less than the ASME SerVice limiting ATWS eventis Service Level C limit of 120%

120% of the design design pressure pressure Overpressurization analyses (1500 psig). Overpressurization analyses were performed at 100% power power at both 99% and 105%

105% flow over the cycle exposure range for both the "MSIV MSIV closure event and the pressure pressure regulator failure open (PRFO) events. The PRFO event assumes a step decrease decr~ase in p'ressure pressure demand demand such that the pressure control control system system opens the turbine turbine control control and turbine bypass bypass valves. Steam flow demand is assumed to increase 125% demand increase to 125% demand (equivalent to 131.25%

131.25% of rated steam flow) allowing a maximum maximum TCV flow of 105.0%

105.0% and aa maximum maximum bypass system flow flow of 21.69%. The system pressure decreases decreases until the low pressure pressure setpoint *is is reached resulting resulting in the closure closure of the MSIVs.

MSIVs. The subsequent subsequent pressurization pressurization wave collapses collapses core voids, thereby increasing core power.

The following assumptions assumptions were made in the analyses.

- The analytical limit ATWS-RPT ATWS-RPT setpoint and function were assumed.

assumed.

- To support operation operation with 1 MSRVOOS, MSRVOOS, the plant configuration analyzed assumedassumed that one of the lowest setpoint MSRVs was inoperable.

inoperable.

- All scram functions functions were disabled.

- The initial dome dome pressure was set to the nominal nominal pressure of 1050 1050 psia.

- A nominal MSIV closure time of 4.0 seconds seconds was used for both events.

Analyses Analyses results are presented in Table 7.2. The response of various reactor plant parametersparameters during the limiting PRFO event are shown shown in Figures 7.5-7.8. The maximum maximum lower plenum pressure is 1486 psig and the maximum pressure maximum dome pressure is 1466 psig. The results demonstrate demonstrate that the ATWS maximum vessel vessel pressure pressure limit of 1500 psig is not exceeded.

Pressure results include Pressure include a 10-psi increase increase to bound a bias in the void-quality correlations. The The void-quality void-quality bias is further discussed in Reference Reference 32.

7.2.2 Long-Term Long-Term Evaluation Evaluation Fuel design differences differences may impact the power and pressure pressure excursion experienced experienced during the during the ATWS event. This in turn may impact impact the amount of steam discharged discharged to the suppression suppression pool

.and containment.

AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Safety Analysis Analysis Page 7-3

[

I The suppression suppression pool temperature temperature and containment containment pressure limits and the corresponding corresponding licensing (Reference 36) are presented licensing values of record (Reference presented in the following table: i AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Ferry Uriit Unit 11 Cycle Cycle 9 Revision 2 Reload Safety Analysis Reload Safety Analysis Page 7-4 Page 7-4 ATWS A TWS Criteria Limit Licensing Value Value Suppression pool temperature (OF) (°F) 281 187.3 187.3 Drywell pressure (psig) 56 48.5 Wetwell pressure (psig) 56 30.5 Relative to the 10 CFR 50.46 acceptance Relat!ve acceptance criteria (i.e., PCT and cladding oxidation),'the oxidation), the consequences of an A consequences ATWS TWS event are bound by those of the limiting LOCA event.

7.3 Standby Liquid Control Standby Control System In the event that the control rod scram function becomes incapable of rendering the core in a shutdown state, the standby liquid control (SLC) system is required to be capable of bringing the the reactor from full power to a cold shutdown condition at any time in the core life. The Browns Browns Ferry Unit 1 SLC system is required to be able to inject 720 ppm natural natural boron equivalent at 70°F into the reactor reador coolant. AREVA has performed an analysis demonstrating demonstrating the SLC system SLCsystem meets the required shutdown shutdown capability for the cycle. The analysis was performed performed at a coolant temperature 366 0 F, with a boron concentration temperature of 366°F, concentration equivalent to 720 ppm at 68°F*. The The temperature of 366°F corresponds to the low pressure temperature pressure permissive permissive for the RHR shutdown RHRshutdown cooling suction valves, and represents the maximum maximum reactivity condition condition with soluble soluble boron in in the coolant. The analysis shows the core to be subcritical subcritical throughout throughout the cycle by at least 2.98%

~k1k Ak/k based on the Cycle 8 EOC short window, which which is the most most limiting limiting exposure exposure bound by the the short and and long Cycle 8 exposurewindow.

exposurewindow.

7.4 Fuel Criticality Fuel Criticality The The new fuel storage new fuel storage vault vault criticality criticality analysis analysis for ATRIUM-10 ATRIUM-10 fuel is presented presented in Reference Reference 24.

The spent The spent fuel fuel pool criticality analysis pool criticality analysis for ATRIUM-1 0 fuel for ATRIUM-10 fuel is presented presented in Reference Reference 25. The The ATRIUM-10 ATRIUM-10 fuel fuel assemblies assemblies identified identified for the cycle cycle meet both both the new new and spent fuel storage storage requirements.

requirements.

VA Browns Ferry SLC licensing basis documents indicate a minimum of 720 ppm boron at a

TVA Browns Ferry SLC licensing basis documents indicate a minimum of 720 ppm boron at a temperature 0 F. The AREVA temperature of of 70 70°F. The cold analysis analysis basis basis of 68'F represents a negligible 68°F represents negligible difference difference and and the the results results are are adequate adequate to protect protect the 70OF 70°F licensing licensing basis basis for the plant.

AREVA AREVA NP Inc.

Inc.

ANP-2864(NP)

Browns Ferry-Unit Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Reload Analysis Page 7-5 7-5 Table 7.1 ASME Overpressurization Overpressurization Analysis Analysis Results*

Results*

Maximum Maximum Peak Peak Vessel Maximum Maximum Neutron Heat Pressure Dome Dome Flux Flux Lower-Plenum Lower-Plenum Pressure Event (% rated) (% rated)

(% (psig) (psig)

MSIV MSIV closure 336 127 1340 1308 336 127 1340 1308 (1 02P/1 05F)

(102P/105F)

MSIV closure MSIV 320 128 1332 1302 320 128 1332 1302 (102P/99F) closure TSV closure without bypass 628 136 136 1338 1305 1305 (102P/1 05F)

(1 closure TSV closure without bypass 562 136 136 1335 1304 1304 (102P/99F)

TCV closure closure without bypass 629 136 1338 1338 1305 -

1305 (102P/1 05F)

(102P/105F)

TCV closure without bypass 559 136 1335 1335 1304 1304 (102P/99F)

(102P/99F)

Pressure 1375 1325 Limit Limit

--- --- 1375 -1325

Pressure results include include a 7-psi increase to bound aa bias in the void-quality correlations void-quality correlations (Reference 32).

(Reference AREVA NP Inc.

Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 Browns . Revision 2 Reload Safety Analysis Reload Analysis Page 7-6 .

Table 7.2 A ATWS TWS Overpressurization Overpressurization Results*

Analysis Results*

Maximum Maximum Peak Peak Vessel Maximum Maximum*

Neutron Heat Heat Pressure Pressure Dome Dome Flux Flux Lower-Plenum Lower-Plenum Pressure Pressure Event (% rated)

(% (%

(% rated) (psig) (psig)

MSIV closure 295 295 140 140 1472 1472 1452 1452 (100P/105F)

(1OOP/1 05F)

MSIV MSIV closure closure (IOOclosur 300 139 (100P/99F) 300 139 1480 1460 1460 (100P/99F)

PRFO PRFO (IOO 249 249 147 147 1479 1459 (100OP/1 05F)

(1 00P/1 05F)

PRFO PRFO P 9F) 244 145 (100OP/99F) 244 145 1486 1466 (100P/99F)

Pressure Pressure 1500 1500 Limit LImit 1500 1500

- Pressure results Pressure include aa 10-psi results include 10-psi increase increase to to bound bound aa bias- in the bias* in the void-quality void-quality correlations correlations (Reference (Reference 32).

AREVA NP Inc.

AREVA

ANP-2864(NP)

Browns Ferry Ferry Unit 1 Cycle-9 Revision 2 Reload Safety Analysis Analysis Page 7-7 7-7 Table 7.3 [

I I

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AREVA NP Inc.

AREVA

ANP-2864(NP)

Browns Browns Ferry Unit 1 Cycle 9 Revision Revision 22** .'

Reload Safety Analysis Analysis Page 7-8 7-8 400.0.-----------------------------------,

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ANP-2864(NP)

Browns Ferry Browns Cycle 9 Ferry Unit 1 Cycle Revision Revision 22 Reload Safety Analysis Reload Analysis Page Page 7-9 35.0

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ANP-2864(NP)

Browns Ferry Unit Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page 7-10 Page 7-10 1350.0,--------------:---------------------,

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ANP-2864(NP)

Browns Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page 7-11 7-11 1500.0 1500.0~-------------------------------,

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10.0 10.0 12.0 12.0 Time. (seconds)

Time (seconds)

Overpressurization Event at Figure 7.4 MSIV Closure Overpressurization at 1 Safety/Relief Valve Flow Rates 02P/1 05F - Safety/Relief 102P/1 Rates AREVA AREVA NP Inc.

ANP-2864(NP)

Browns Ferry Unit 1 Cycle 9 . Revision 2 Reload Safety AnalysisAnalysis 7-12 Page 7-12 2 50.0-r-----------------....,...-----------------,

250.0 Relative Core Power Relative Heat Flux Relative Total Core Flow 200.0

- -Relative

- - -Steam

- - -Flow----

Relative Feed Flow 150.0

-0 04l 0

0:::

....0a 100.0

....c::C QJ 0U L-0 QJ LI-el-50.0

.0

-50.0 - j - - - - - - - , - - - - - - - r - - - - - - - r - - - - - - - - - - , , - - - - - - - - - i

.0 10.0 20.0 30.0 40.0 50.0 Time (seconds)

Figure 7.5 PRFO ATWS Overpressurization Overpressurization Event at 100P/99F 1OOP/99F - Key Parameters Parameters AREVA NP Inc.

ANP-2864(NP)

.. ~ Browns Ferry Unit 1 Cycle 9 2 Revision 2*

Reload Safety Analysis Analysis 7-13 Page 7-13 60.0

~

0 l-V N

N

.....C v

0) 40.0 E

J

.....Vl I-C

.£;

.....0

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v a.

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.0

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3:

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> 750.0 750.0 Qi 0::

.C E 500.0 0

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-+J Vl o2500.0-C

0 .)

250.0

.O+-----------,---~------_r----------_r----------~--~--~--~

.010.0 20.0 30.0 40.0 50.0

.0 10.0 20.0 Time (seconds) 30.0 40.0 so.o Time (seconds)

Figure 7.8 PRFO ATWS Overpressurization Overpressurization Event at at 1OOP/99F - Safety/Relief 100P/99F Safety/Relief Valve Flow.Rates Flow.Rates AREVA NP Inc.

ANP-2864(NP)

-Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Reload Safety Analysis Page 8-1 8.0 Operating Limits and COLR Operating COLR Input Input 8.1 MCPR Limits Determination of MCPR limits are based Determination based on analyses of the limiting abnormal abnormal operational transients transients (AOTs). The MCPR operating limits are established established so that less than 0.10.1%

% of the fuel rods in the core are expected expected to experience experience boiling transition during an AOT initiated initiated from rated or off-rated conditions and are based on Jhe the Technical Specifications two.,.loop Technical Specifications two-loop operation operation SLMCPR of 1.07 and a single-loop operation SLMCPR of 1.10. Exposure-dependent operationSLMCPR Exposure-dependent MCPR MCPR limits were -established to support operation were -established operation from BOC to near end-of-cycle end-of-cycle (NEOC), NEOC NEOC to end-of-cycle licensing basis (EOCLB) and combined end-of-cycle combined FFTR/Coastdown.

FFTRlCoastdown. MCPR limits are established to support base case operation and the EOOS scenarios established scenarios presented presented in Table 1.1.

1.1.

Two-loop Two-loop operation MCPRP MCPRp limits for ATRIUM-10 ATRIUM-10 and GE14 fuel are presented presented in Tables 8.1-8.1-8.6 for base case operation operation and the EOOS conditions. Limits are presented presented for nominal nominal scram speed (NSS) and Technical Specification Specification scram scram speed (TSSS) insertion insertion times for the exposure exposure considered. Tables 8.1 and 8.2 present the MCPR ranges considered. MCPRpp limits for the BOC to NEOC NEOC exposure exposure range. Tables 8.3 and 8.4 present the MCPR MCPRpp limits applicable applicable for the BOC to EOCLB exposure exposure range. Tables 8.5 and 8.6 present the MCPR MCPRPp limits for FFTR/Coastdown FFTRlCoastdown operation.

operation.

MCPRPp limits for single-loop operation MCPR operation are 0.03 higher for all cases. Comparisons Comparisons of the limiting limiting AOT analysis results and the MCPRPMCPRp limits for ATRIUM-10 ATRIUM-10 and GE14 fuel are presented presented in in Appendix A.

MCPRff limits protect against MCPR against fuel failures during postulated slow flow excursion. ATRIUM-10 during a postulated ATRIUM and GE14 fuel limits are presented presented in Table 8.7 and are applicable applicable for all cycle exposures exposures andand EOOS conditions Table 1.1.

conditions identified in Table 1.1.

8.2 LHGR Limits The LHGR limits for ATRIUM-10 presented in Table 8.8. The LHGR limits for GE14 ATRIUM-10 are presented GE14 fuel are Reference 29. Power- and flow-dependent presented in Reference flow-dependent multipliers (LHGRFACp (LHGRFAC p and LHGRFACf)f ) are applied directly LHGRFAC directly to the LHGR LHGR limits to protect against fuel melting and overstraining overstraining of the cladding during an AOT.

LHGRFACpp multipliers LHGRFAC multipliers for ATRIUM-10 ATRIUM-10 fuel are determined using the heat flux ratio results from the transient analyses. The LHGRFACp LHGRFAC p and LHGRFAC LHGRFACff multipliers were developed developed in a manner consistent with the GNF thermal-mechanical consistent methodology for GE14 fuel.

thermal-mechanical methodology

- AREVA NP Inc.

ANP-2864(NP)

Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Reload Safety Analysis Page 8-2 Page 8-2 LHGRFACp LHGRF established to support operation at all cycle exposures AC p multipliers were established exposures for both NSS and TSSS insertion insertion times and for the EOOS EOOS conditions identified identified in Table 1.1 with and without TBVOOS. LHGRFAC LHGRFACpp limits are presented presented in Tables 8.9 and 8.10 for ATRIUM-10 ATRIUM-10 and GE14 fuel, respectively. Comparisons Comparisons of the limiting results and the LHGRFAC LHGRFACpp limits are presented in Appendix presented Appendix A.

LHGRFACff multipliers are established LHGRFAC established to provide protection against fuel centerline centerline melt and overstraining of the cladding during a postulated overstraining LHGRFACf limits are postulated slow flow excursion. LHGRFACf'limits presented presented in Table 8.11 and 8.12 for ATRIUM-10 ATRIUM-10 and GE14 fuel, respectively. LHGRFAC LHGRFACff multipliers multipliers are applicable applicable for all cycle cycle exposures exposures and EOOS conditions conditions identified in Table 1.1.

1.1.

The SLO LHGR LHGR multiplier GE14 fuel is presented multiplier for GE:14 References 21 and 26.

presented in References 8.3 MAPLHGR Limits ATRIUM-10 ATRIUM-10 MAPLHGR Reference 20. The TLO operation MAPLHGR limits are discussed in Reference operation limits are presented in Table 8.13. For operation presented operation in SLO, a multiplier of 0.85 must be applied to the TLO TLO MAPLHGR limits. Power and flow dependent MAPLHGR dependent MAPFAC setdowns are not required; required; therefore, MAPFAC=1.0.

MAPFAC=1.0.

The GE14 APLHGR References 21 and 26. The TLO and SLO operation APLHGR limits are discussed in References presented in References limits are presented References 21 and 26.

AREVA NP Inc.

ANP-2864(NP)

Browns Browns Ferry Unit 1 Cycle 9-9'" Revision 2 Reload Safety Analysis Reload Analysis . Page 8-3 8-3 Table 8.1 MCPRMCPRpp Limits for NSS Insertion Times NSS Times BOC to NEOC*

MCPRp MCPRp Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%of rated)

(% Fuel Fuel 100.0 1.43 1.41 90.0 1.50 1.48 1.48 50.0 1.76 1.75 1.75 50.0 1.83 1.81 Base case 40.0 1.90 1.89 1.89 operation 26.0 2.21 2.19 2.19 26.0 at at> > 50%F 2.57 2.68 2.68 23.0 at > 50%F 2.70 2.80 2.80 26.0 at <s 50%F 2.53 2.60 2.60 23.0 at s< 50%F 2.65 2.72 2.72 100.0 1.46 1.44 1.44 90.0 1.54 1.51 50.0 ---

50.0 1.83 1.81 40.0 1.90 1.92 '

1.92 TBVOOS TBVOOS 26.0 2.26 2.23 2.23 26.0 at > 50%F 3.05 3.11 3.11 23.0 at > 50%F 3.28 3.27 26.0 at <s 50%F 2.75 2.84 2.84 23.0 at

at > 50%F 2.57 2.68 2.68 23.0 at > 50%F 2.70 2.80 26.0 at s< 50%F 2.53 2.60 23.0 at s< 50%F 2.65 2.72 2.72 100.0 100.0 1.46 1.46 1.44 1.44 90.0 1.52 1.52 1.50 1,.50 50.0 ---

50.0 1.83 1.83 1.81 FHOOS013 40.0 40.0 1.93 1.93 1.96 1.96 FHOOS 26.0 2.31 2.29 2.29 26.0 at > 50%F 2.69 2.80 23.0 at at>> 50%F 2.83 2.94 26.0 at s< 50%F 2.63 2.70 23.0 at s< 50%F 2.76 2.85 2.85

~~Limits support operation with any combination combination of 1 MSRVOOS, MSRVOOS, up to 2 TIPOOS TIPOOS (or the equivalent number of TIP channels), and up to 50% of the LPRMs out-of-service.~~
out-of-service. For single-loopoperation, single-loop operation ,
MCPRpp limits will be 0.03 higher.
MCPR .
AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 I Cycle 9 Revision 2 Safety Analysis Reload Safety Analysis 8-4 Page 8-4 Table 8.1 MCPRMCPRpp Limits for NSSlnsertion Times NSS Insertion Times BOC to NEOC BOCto NEOC (Continued)
(Continued)
. MCPR MCPRpp Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel 100.0 1.43 1.41 90.0 1.50 1.S0 1.48 1.48 50.0 SO.O - --
50.0 SO.O 1.85 1.8S 1.84 1.84 40.0 1.90 1.90 1.89 1.89 PLUOOS 26.0 2.21 2.19 26.0 2.21 2.19 26.0 at > 50%F SO%F 2.57 2.S7 2.68 23.0 at > 50%F SO%F 2.70 2.80 26.0 at S< 50%F SO%F 2.53 2.S3 2.60 23.0 at S< 50%F SO%F 2.65 2.6S 2.72 100.0 100.0 1.46 1.46 1.45 1.4S 90.0 1.54 1.S4 1.52 1.S2 50.0 SO.O ---...-- --
50.0 SO.O 1.83 1.83 1.81 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.90 1.90 1.92 1.92 and TBVOOS 26.0 2.26 2.23 26.0 at > 50%F SO%F 3.05 3.0S 3.11 3.11 23.0 at > 50%F SO%F 3.28 3.27 26.0 at S< SO%F 50%F 2.75 2.7S ' 2.84 23.0 at S5 50%F SO%F 3.00 3.08 100.0 100.0 1.46 1.46 1.44 1.44 90.0 1.52 .
1.S2 1.50 1.S0 50.0 SO.O ---
50.0 SO.O 1.83 1.83 1.81 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.93 1.93 1.96 1.96 and FHOOS 26.0 2.31 2.29 2.29 26.0 at > SO%F 50%F . 2.69 2.80 2.80 23.0 at > SO%F 50%F 2.83 2.94 2.94 26.0,at 26.0 at 5S SO%F 50%F 2.63 2.70 2.70 23.0 at S< 50%F SO%F . 2.76 2.85 2.8S 100.0 1.43 1.43 1.41 90.0 90.0 1.50
' 1.S0 1.48 1.48 50.0 SO.O ---
50.0 SO.O 1.85 1.8S 1.84 1.84 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.90 1.89 1.89 and PLUOOS 26.0 2.21 2.19 2.19 26.0 at > SO%F 50%F 2.57 2.S7 2.68 2.68 23.0 at > 50%F SO%F 2.70 2.80 2.80 26.0 at at S< 50%F SO%F 2.53 2.S3 2.60 2.60 23.0 23.0 at S< 50%F SO%F 2.65 2.6S 2.72 2.72 AREVA AREVA NP Inc.
Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Analysis Reload Safety Analysis Page Page 8-5 8-S Table 8.1 MCPR Table MCPRpp Limits for NSS NSS Insertion Times Times BOC to NEOC BOCto (Continued)
(Continued)
MCPRP MCPRp Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (% of rated)
(% rated) Fuel Fuel 100.0 100.0 1.49 1.47 1.47 90.0 1.55 1.SS 1.53 1.S3 50.0 SO.O SO.O 50.0 1.85 1.8S 1.83 1.83 TBVOOS 40.0 1.96 1.99 1.99 FHOOS and FHOOS 26.0 2.35 2.3S 2.32 2.32 26.0 at > SO%F 50%F 3.18 3.24 23.0 at at>> SO%F 50%F 3.40 3.40** 3.40 26.0 at <S SO%F 50%F 2.89 2.97 23.0 at<5 50%F ats SO%F 3.15 3.1S 3.26 100.0 1.46 1.44 1.44 90.0 1.54 1.S4 1.51 1.S1 50.0 SO.O -- --
50.0 SO.O 1.85 1.8S 1.84 TBVOOS 40.0 1.90 1.92 1.92 PLUOOS and PLUOOS 26.0 2.26 2.23 26.0 at >> SO%F 50%F 3.05 3.0S. 3.11 3.11 23.0 at > SO%F 50%F 3.28 .3.27
.3.27 26.0 at < 50%F S SO%F 2.75 2.7S 2.84 23.0 at < 50%F S SO%F 3.00 3.08 100.0 100.0 1.46 1.44 1.44 90.0 1.52 1.S2 1.50 1.S0 50.0 SO.O ---
50.0 SO.O 1.85 1.8S 1.84 1.84 FHOOS 40.0 1.93 1.96 1.96 PLUOO S and PLUOOS 26.0 2.31 2.29 2.29 50%F 26.0 at > SO%F 2.69 2.80 2.80 23.0 at > SO%F 50%F 2.83 2.94 2.94 26.0 at S- SO%F 50%F 2.63 2.70 23.0 at S
< SO%F 50%F 2.76 2.85 2.8S 100.0 1.49 1.47 1.47 90.0 1.55 1.S5 1.53 1.S3 50.0 SO.O ---
50.0 SO.O 1.85 1.8S 1.83 1.83 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.96 1.99 40.0 1.96 1.99 TBVOOS, TBVOOS, 26.0 2.35 2.32 and FHOOS 26.0
~~2. 2.3S~~
.523 2.32 and FHOOS 26.0 at > SO%F 50%F 3.18 3.24 23.0 at > SO%F 50%F 3.40 3.40 26.0 at S
< SO%F 50%F 2.89 2.97 23.0 at* 50%F at S SO%F 3.15 3.1S 3.26 AREVA NP Inc.
ANP~2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 -Cycle Cycle 99 Revision 2 Analysis Reload Safety Analysis Page 8-6 8-6 MCPRpp Limits for Table 8.1 MCPR NSS Insertion Times NSS Times BOC to NEOC BOCto (Continued)
(Continued)
MCPRP MCPR p Operating Power ATRIUM-10 GE14 GE14 Condition (% of rated)
(% rated) Fuel Fuel 100.0 1.46 1.45 1.45 90.0 1.54 1.52 1.52 50 .0 50.0 ---
50.0 1.85 1.84.
1.84.
EOC-RPT-OOS, EOC-RPT -OOS. 40.0 1.90 1.92 40.0 1.90 1.92 TBVOOS, TBVOOS. 26.0 2.26 2.23 26.0 at26.0 2.26 2.23 and PLUOOS > 50%F 3.05 3.11 26.0 at > 50%F 3.05 3.11 23.0 at > 50%F 23.0.at> 3.28 3.27 26.0 at s- 50%F 2.75 2.84 23.0 at s< 50%F 3.00 3.08 100.0 100.0 1.46 1.44 1.44 90.0 1.52 1.50 1.50 50.0 ---
50.0 1.85 1.84 EOC-RPT-OOS, EOC-RPT-OOS. 40.0 1.93 1.96 40.0 1.93 1.96 FHOOS, FHOOS. 26.0 2.31 26.0 2.31 2.29 and PLUOOS 26.0 at > 50%F 2.69 26.0 at > 50%F 2.69 2.80 23.0 at >> 50%F 2.83 2.94 2.94 26.0 at s- 50%F 2.63 2.70 23.0 at S 50%F 2.76 2.85 100.0 100.0 1.49 1.47 1.47 90.0 1.55 1.53 1.53 50.0 ---
50.0 1.85 1.84 1.84 TBVOOS, TBVOOS. 40.0 1.96 1.99 FHOOS, 40.0 26.0 1.96 1.99 FHOOS. 2.35 2.32 and 26.0 at26.0 2.35 2.32 and PLUOOS > 50%F 3.18 3.24 26.0 at > 50%F 3.18 3.24 23.0 23.0 at > 50%F 50%F 3.40 3.40 3.40 26.0 at > 50%F 50%F 3.18 3.24 3.24 23.0 23.0 at at>> 50%F 50%F 3.40 3.40 3.40 26.0 26.0 at <s 50%F 50%F 2.89 2.97 2.97 23.0 23.0 at > 50%F 2.57 2.68 23.0 at > 50%F 2.70 2.80 26.0 at s< 50%F 2.53 2.60 23.0 at s< 50%F 2.65 2.72 100.0 1.50 1.48 1.48 90.0 1.57 1.55
,1.55 50.0 50.0 50.01. 1.84 1.82 1.82 40.0 1.91 1.94 TBVOOS 26.0 2.27 2.25 26.0 at > 50%F 3.05 3.11 3.11 23.0 at > 50%F 3.28 3.27 26.0 at s< 50%F 2.75 . . 2.84 23.0 at s< 50%F 3.00 3.08 100.0 1.47 1.44 1.44 90.0 1.53 1.51 50.0 1.78 1.78 1.77 1.77 50.0 1.84 1.84 1.82 1.82 40.0 1.91 1.91 1.90 1.90 EOC-RPT-OOS 26.0 2.22 2.20 2.20 26.0 at > 50%F 2.57 2.68 2.68 23.0 at > 50%F 2.70 2.80 26.0 at <s 50%F 50%F 2.53 2.60 23.0 at ~~50%F 2.69 2.80 23.0 at > 50%F 50%F 2.83 2.83 2.94 2.94 26.0 at <s 50%F 50%F 2.63 2.63 2.70 23.0 at s< 50%F 2.76 2.85~~
Limits support operation operation with any combination MSRVOOS, up to 22 TIPOOS (or the equivalent combination of 1 MSRVOOS, equivalent number number of TIP channels), and up to 50%50% of the LPRMs out-of-service.
out-of-service. For single-loop operation, operation, MCPRP MCPRp limits will be 0.03 higher.
AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Safety Analysis Page 8-8 8.2 MCPRp Table 8.2. MCPRp Limits for TSSS Insertion TSSS Insertion Times Times BOC BOCtoNEOCto NEOC (Continued)
(Continued)
MCPRPp MCPR Operating Operating Power ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel 100.0 100.0 1.47 1.47 1.44 1.44 90.0 1.53 1.S3 1.51
. 1.S1 50.0 SO.O ---
50.0 SO.O 1.85 1.8S 1.84 1.84 40.0 1.91 1.91 1.90 1.90 PLUOOS 26.0 2.22 2.20 26.0 at > 50%FSO%F 2.57 2.S7 2.68 23.0 at > 50%FSO%F 2.70 2.80 26.0 at :<50%F os; SO%F 2.53 2.S3 2.60 23.0 23.0 at :<os; 50%F SO%F 2.65 2.6S 2.72 100.0 100.0 1.50 1.S0 1.49 1.49 90.0 1.57 1.S7 1.55 1.SS 50.0 SO.O ---
50.0 SO.O 1.84 1.84 1.82 1.82.
EOC-RPT-OOS EOC-RPT-OOS 40.0 1.91 1.91 1.94 1.94 and TBVOOS 26.0 2.27 2.25 2.2S 26.0 at > 50%FSO%F 3.05 3.0S 3.11 3.11 23.0 at > 50%FSO%F 3.28 3.27 26.0 at :<os; SO%F 50%F 2.75 2.7S 2.84 23.0 at:os; at < SO%F50%F 3.00 3.00 3.08 100.0 100.0 1.50 1.S0 1.47 1.47 90.0 1.55 1.SS 1.52 1.S2 50.0 SO.O ---
50.0 SO.O 1.84 1.82 1.82 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.95 1.9S 1.97 1.97 and FHOOS 26.0 26.0 2.32 2.30 26.0 at > SO%F50%F 2.69 2.80 2.80 23.0 at > > SO%F 50%F 2.83 2.94 2.94 26.0 at < SO%F at:os; 50%F 2.63 2.70 23.0 at :< 50%F os; SO%F 2.76 2.85 2.8S 100.0 100.0 1.47 1.44 1.44 90.0 1.53 1.S3 1.51 1.S1 50.0 SO.O ---
50.0 SO.O 1.85 1.8S 1.84 1.84 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.91 1.90 1.90 and PLUOOS and PLUOOS 26.0 26.0 2.22 2.20 2.20 26.0 at 26.0 at > > SO%F 50%F 2.57 2.S7 2.68 2.68 23.0 at > SO%F 23.0 at 50%F 2.70 2.80 2.80 26.0 at <:os; SO%F 26.0 50%F 2.53 2.S3 2.60 2.60 23.0 at :< 50%F os; SO%F 2.65 2.6S 2.72 2.72 AREVA NP Inc.
ANP-2864(NP)
Unit 11 Cycle 9 Browns Ferry Unit Revision 2 Reload Analysis Reload Safety Analysis Page 8-9 Table 8.2 MCPR
-Table MCPRpp Limits Limits for TSSS Insertion Times Times BOC to NEOC BOCto (Continued)
(Continued)
MCPRPp MCPR Operating Power ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel 100.0 100.0 1.53
.1.53 1.50 1.50 90.0 1.58 1.55 1.55 50.0 ---
50.0 1.87 1.85 1.85 TBVOOS TBVOOS 40.0 1.98 2.00
-2.00 and FHOOS 26.0 2.37 2.34 26.0 at > 50%F 3.18 3.24 3.24 23.0 at > 50%F 3.40 3.40 26.0 at S< 50%F 2.89 2.97 23.0 at S< 50%F 3.15 3.26 100.0 100.0 1.50 1.48 1.48 90.0 1.57 1.55 1.55 50.0 ---
50.0 1.85 1.84 1.84 TBVOOS 40.0 1.91 1.91 1.94 1.94 and PLUOOS
-and PLUOOS 26.0 - 2.27 2.25 26.0 at >> 50%F 3.05 3.11 3.11 23.0 at > 50%F 3.28 3.27 26.0 at <S 50%F 2.75 2.84 2.84 23.0 at S< 50%F 3.00 3.08 100.0 100.0 1.50 1.47 1.47 90.0 90.0 1.55 1.55 1.52 1.52 50.0 ---
50.0 1.85 1.84 1.84 FHOOS FHOOS 40.0 1.95 1.97 1.97 and PLUOOS 26.0 2.32 2.30 2.30 26.0 at > 50%F 2.69 2.80 2.80 23.0 at > 50%F 2.83 2.94 2.94 26.0 at <S 50%F 2.63 2.70 2.-70 23.0 at ~~50%F 50%F 3.18 3.24 3.24 23.0 23.0 at at > 50%F 50%F 3.40 3.40 3.40 26.0 26.0 at<~~
~~at'S 50%F 50%F 2.89 2.97 2.97 23.0 23.0 at ~~50%F 3.05 3.11 3.11 23.0 at > 50%F 3.28 3.27~~~~
. 26.0 at s< 50%F 2.75 2.84 23.0 at s< 50%F 3.00 3.08 100.0 1.50 1.47 1.47 90.0 1.55 1.52 1.52 50.0 ---- --
~~50.0 1.85~~
1.85 1.84 1.84 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.95 1.97 FHOOS, 40.0 1.95 1.97 FHOOS, and PLUOOS 26.0 26.0 2.32 2.30 2.30 26.0 at > 50%F 2.69 2.80 2.80 23.0 at > 50%F 2.83 2.94 2.94 26.0 at <s 50%F 2.63 2.70 2.70 23.0 at 50%F 3.18 3.24 3.24 23.0 23.0 at > 50%F 50%F 3.40 3.40 3.40 26.0 26.0 at <s 50%F 50%F 2.89 2.97 2.97 23.0 at5s<50%F 23.0 at 50%F 3.15 3.26 3.26 100.0 100.0 1.53 1.53 1.50 1.50 90.0 1.58 1.58 1.55 1.55 50.0 50.0 --
EOC-RPT-OOS, EOC-RPT-OOS, 50.0 50.0 1.87 1.87 1.85 1.85 TBVOOS, TBVOOS, 40.0 1.98 1.98 2.00 2.00 FHOOS, FHOOS, 26.0 26.0 2.37 2.34 2.34 and PLUOOS PLUOOS 26.0 26.0 at at >> 50%F 50%F 3.18 3.18 3.24 3.24 23.0 23.0 at > 50%F 50%F 3.40 3.40 3.40 3.40 26.0 26.0 at <s 50%F 50%F 2.89 2.97 2.97 23.0 23.0 at 50%F 2.57 2.68 23.0 at > 50%F 23.0 2.70 2.80 26.0 at s< 50%F 2.53 2.60 23.0 at s- 50%F 2.65 2.72 100.0 100.0 1.48 1.49 1.49 90.0 1.54 1.55 1.55 50.0 ---
50.0 1.83 1.81 40.0 1.90 1.92 1.92 TBVOOS 26.0 2.26 2.23 26.0 at > 50%F 3.05 3.11 3.11 23.0 at > 50%F 3.28 3.27 26.0 at s< 50%F 26.0 50%F 2.75 2.84 2.84 23.0 at s< 50%F 3.00 3.08 100.0 100.0 1.44 1.44 1.45 1.45 90.0 1.50 1.52 1.52 50.0 1.76 1.75 1.75 50.0 1.83 1.81 40.0 1.90 1.89 1.89 EOC-RPT-OOS 26.0 26.0 2.21 2.19 2.19 26.0 at> 50%F 26.0 at> 50%F 2.57 2.68 2.68 23.0 at > 50%F 23.0 at 50%F 2.70 2.70 2.80 2.80 26.0 at <
26.0 at s 50%F 50%F 2.53 2.53 2.60 2.60 23.0 at 5s 50%F 23.0 50%F 2.65 2.65 2.72 2.72 100.0 1.46 1.47 1.47 90.0 90.0 1.52 1.52 1.52 50.0 50.0 ---
50.0 50.0 1.83 1.83 1.81 40.0 40.0 1.93 1.96 1.96 FHOOS 26.0 26.0 2.31 2.29 2.29 26.0 26.0 at > 50%F 50%F 2.69 2.80 2.80 23.0 23.0 at > 50%F 50%F 2.83 2.94 2.94 26.0 26.0 at <s 50%F 50%F 2.63 2.70 2.70 23.0 23.0 at 50%F 2.57 2.68 2.68 23.0 at > 50%F 2.70 2.80 2.80 26.0 at s< 50%F 2.53 2.60 23.0 at s< 50%F 2.65 2.72 100.0 100.0 1.48 1.49 1.49 90.0 1.54 1.56 1.56 50.0 ---
50.0 1.83 1.81 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.90 1.92 1.92 and TBVOOS TBVOOS 26.0 2.26 2.23 2.23 26.0 at > 50%F 3.05 3.11 3.11 23.0 at > 50%F 3.28 3.27 3.27 26.0 at <s 50%F 2.75 2.84 2.84 23.0 at s< 50%F 3.00 3.08 3.08 100.0 1.46 1.47 1.47 90.0 1.52 1.53 1.53 50.0 --
50.0 1.83 1.81 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.93 1.93 1.96 1.96 and FHOOS FHOOS 26.0 2.31 2.29 2.29 26.0 at > 50%F 2.69 2.80 23.0 at > 50%F 2.83 2.94 26.0 at S 26;0 s 50%F 2.63 2.70 2.70 23.0 at 50%F 2.57 2.68 23.0 at > 50%F 2.70 2.80 2.80 26.0 at s< 50%F 2.53 2.60 2.60 23.0 at s< 50%F 50%F 2.65 2.72 2.72 AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~Browns Ferry Unit Unit 1 Cycle 9 .... - Revision 2 .~~
Reload Safety Analysis Analysis Page Page 8-13 8-13 Table 8.3 MCPRMCPRpp Limits for NSS Insertion NSS Insertion Times Times BOC to EOCLB BOCto EOCLB (Continued)
~~(Continued)~~
~~MCPRPp MCPR Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%of rated)~~
~~(% Fuel Fuel 100.0 1.50 1.S0 1.50 1.S0 90.0 1.55 1.SS 1.55 1.SS 50.0 SO.O ---~~
50.0 SO.O 1.85 1.8S 1.83 1.83 TBVOOS TBVOOS 40.0 1.96 1.99 1.99 and FHOOS 26.0 2.35 2.3S 2.32 2.32 26.0 at > SO%F 50%F 3.18 3.24 3.24 50%F 23.0 at > SO%F 3.40 3.40 26.0 at S< SO%F 50%F 2.89 2.97 at:<50%F 23.0 at S SO%F 3.15 3.1S 3.26 3.26 100.0 1.48 1.49 1.49 90.0 1.54 1.S4 1.55 1.SS 50.0 SO.O --
50.0 SO.O 1.86 1.84 1.84 TBVOOS TBVOOS 40.0 1.90 1.92 1.92 and PLUOOS PLUOOS 26.0 2.26 2.23 26.0 at > SO%F 50%F 3.05 3.0S 3.11 3.11 .
50%F 23.0 at > SO%F 3.28 3.27 3.27 at<5S SO%F 26.0 at 50%F 2.75 2.7S 2.84 23.0 at S< SO%F 50%F 3.00 3.08 100.0 1.46 1.46 1.47 1.47 90.0 1.52 1.S2 1.52 1.S2 50.0 SO.O ---
50.0 SO.O 1.86 1.86 1.84 1.84 FHOOS FHOOS 40.0 1.93 1.93 1.96 1.96 PLUOOS and PLUOOS 26.0 2.31 2.29 26.0 at > 50%F SO%F 2.69 2.80 23.0 at > SO%F 50%F 2.83 2.94 26.0 at S< 50%F SO%F 2.63 2.70 23.0 at at S< 50%F SO%F 2.76 2.85 2.8S 100.0 1.50 1.S0 1.51 1.S1 90.0 1.55 1.SS 1.57 1.S7 50.0 SO.O ---
50.0 SO.O 1.85 1.8S 1.83 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.96 1.99 40.0 1.96 1.99 TBVOOS, 26.0 2.35 2.32 and FHOOS 26.0
~~2. 2.3S~~
.523 2.32 and FHOOS 26.0 at > 50%F SO%F 3.18 3.24 23.0 at > SO%F 50%F 3.40 3.40 3.40 26.0 at S< 50%F SO%F 2.89 2.97 2.97 23.0 at S< 50%F SO%F . 3.15 3.1S 3.26 AREVA Inc...
AREVA NP Inc
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit Unit 11 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page Page 8-14 8-14 Table 8.3 MCPR MCPRpp Limits for NSS Insertion Times NSS Times BOC to EOCLB BOCto (Continued) .
(Continued)
MCPRpp MCPR Operating Power ATRIUM-10 GE14 GE14 Condition (%of rated)
(% rated) Fuel Fuel 100.0 1.48 1.49 1.49 90.0 1.54 1.54 1.56 50.0 ---
50.0 1.86 1.84 1.84 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.90 1.92 TBVOOS, 40.0
~~2. 1.90~~
~~.622 1.92 TBVOOS,~~
~~26.0 2.26 2.26 2.23 and PLUOOS 26.0 at >> 50%F 3.05 3.11~~
. 23.0 at > 50%F 3.28 3.27 26.0 at s< 50%F 2.75 . 2.84 23.0 at s< 50%F 3.00 3.08 100.0 100.0 1.46 1.46 1.47 90.0 1.52 1.53 50.0 ---
50.0 1.86 1.84 1.84 EOC-RPT-OOS, EOC-RPT~OOS, 40.0 1.93 1.96 FHOOS, 40.0 1.93 1.96 and FHOOS,PLUOOS 26.0 2.31 26.0 at26.0 2.31 2.29 2.29 and PLUOOS > 50%F 2.69 2.80 26.0 at > 50%F 2.69 2.80 23.0 at at> > 50%F 2.83 2.94 2.94.
26.0 at <s 50%F 2.63 2.70 2.70 23.0 at 50%F 3.18 3.24 3.24 23.0 23.0 at > 50%F 3.40 3.40 3.40 26.0 26.0 at > 50%F 50%F 3.18 3.18 3.24 3.24 23.0 at at > 50%F 50%F 3.40 3.40. 3.40 3.40 26.0 26.0 at at S< 50%F 50%F 2.89 2.89 2.97 2.97 23.0 at at S< 50%F 50%F 3.15 3.26 3.26 AREVA AREVA NP NP Inc.
~~Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Ferry Unit 1 Cycle 9 Revision 2 Reload Reload Safety Analysis Analysis Page 8-1S 8-15 Table 8.4 MCPR MCPRpp Limits forfor TSSS Insertion TSSS Insertion Times Times BOC to EOCLB*
~~MCPRp MCPRp Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (% of rated)~~
(% Fuel Fuel 100.0 1.47 1.47 1.48 1.48 90.0 1.53 1.S3 1.S3 1.53 SO.O 50.0 1.78 1.78 1.77 1.77 SO.O 50.0 1.84 1.82 1.82 Base case 40.0 1.91 1.90 1.90 operation operation 26.0 2.22 2.20 2.20 26.0 at > SO%F50%F 2.57 2.S7 2.68 2.68 23.0 at > SO%F50%F 2.70 2.80 2.80 26.0 at S< 50%F SO%F 2.53 2.S3 2.60 2.60 23.0 at S< SO%F 50%F 2.65 2.6S 2.72 2.72 100.0 1.51 1.S1 1.52 1.S2 90.0 1.57 1.S7 1.57 1.S7 SO.O 50.0 ---
50.0 SO.O 1.84 1.84 1.82 1.82 40.0 1.91 1.91 1.94 1.94 TBVOOS 26.0 2.27 2.25 2.2S 26.0 at > 50%FSO%F 3.05 3.OS 3.11 3.11 23.0 at > 50%FSO%F 3.28 3.27 3.27 26.0 26 .. 0 at S< 50%F SO%F 2.75 2.7S 2.84 2.84 23.0 at S< 50%F SO%F 3.00 3.08 100.0 100.0 1.47 1.47 1.48 1.48 90.0 1.53 1.S3 1.53 1.S3 50.0 SO.O 1.78 1.78 1.77 1.77 50.0 SO.O 1.84 1.84 1.82 1.82 40.0 1.91 1.91 1.90 1.90 EOC-RPT-OOS 26.0 2.22 2.20 26.0 at > SO%F50%F 2.57 2.S7 2.68 23.0 at > 50%FSO%F 2.70 2.70 2.80 2.80 26.0 at S< SO%F 50%F 2.53 2.S3 2.60 2.60 23.0 at S< SO%F 23.0 50%F 2.65 2.6S 2.72 2.72 100.0 1.50 1.S0 1.49 1.49 90.0 1.55 1.SS 1.55 1.SS 50.0 SO.O ---
50.0 SO.O 1.84 1.84 1.82 1.82 FHOOS 40.0 1.95 1.9S 1.97 1.97 FHOOS 26.0 2.32 2.30 26.0 at > SO%F50%F 2.69 2.80 23.0 at > SO%F50%F 2.83 2.94 26.0 at <S SO%F 50%F 2.63 2.70 23.0 at S< SO%F 50%F 2.76 2.76 2.85 2.8S Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the
~~Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent equivalent number of TIP channels), and up to SO% 50% of the LPRMs out-of-service.~~
LPRMs out-ot-service. For single-loop single-loop operation, MCPRPp limits will be 0.03 higher.
MCPR AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page 8-16 8-16 Table 8.4 MCPRp MCPRp Limits for Insertion Times TSSS Insertion Times BOC to EOCLB (Continued)
(Continued)
MCPRPp MCPR Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%
(% of rated) Fuel Fuel 100.0 100.0 1.47 1.47 1.48 1.48 90.0 1.53 1.53 1.53 50.0 -- --
50.0 1.86 1.86 1.84 40.0 1.91 1.91 1.90 1.90 PLUQOS PLUOOS 26.0 2.22 26.0 2.22 2.20 26.0 at > 50%F 2.57 2.68 23.0 at at> > 50%F 2.70 2.80 26.0 46.0 at S< 50%F SO%F 2.53 2.60 23.0 at S< 50%F SO%F 2.65 2.6S 2.72 100.0 100.0 1.51 1.52 1.52 90.0 1.57 1.58 1.S8 50.0 SO.O ---
50.0 SO.O 1.84 1.82 1.82 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.91 1.94 1.94 and TBVOOS TBVOOS 26.0 2.27 2.25 26.0 at > 50%F SO%F 3.05 3.11 3.11 23.0 at > 50%F 23.0 SO%F 3.28 3.27 26.0 at S< 50%F 2.75 2.84 23.0 at S< 50%F 3.00 3.08 100.0 1.50 1.49 1.49 90.0 1.55 1.5S 1.55 1.SS 50.0 ---
50.0 SO.O 1.84 1.84 1.82 1.82 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.95 1.95 1.97 1.97 and FHOOS FHOOS 26.0 2.32 2.30 2.30 26.0 at > 50%F
26.0 2.69 2.69 2.80 23.0 at > SO%F 50%F 2.83 2.94 2.94 26.0 at < 50%F S SO%F 2.63 2.70 2.70 23.0 at S< 50%F 2.76 2.85 2.85 100.0 1.47 1.47 1.48 1.48 90.0 1.53 1.53 1.53 1.53 50.0 SO.O ---
50.0 SO.O 1.86 1.86 1.84 1.84 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.91 1.91 1.90 1.90 and PLUOOS PLUOOS 26.0 2.22 2.20 2.20 26.0 at at >> 50%F SO%F 2.57 2.57 2.68 2.68 23.0 at > 50%F SO%F 2.70 2.80 2.80 26.0 at at<5S 50%F SO%F 2.53 2.60 23.0 at S< 50%F SO%F 2.65 2.72 AREVA NP Inc.
AREVA
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit 1 Cycle 9 Revision 2 Reload Reload Safety Analysis Analysis Page 8-17 8-17 Table 8.4 MCPR MCPRpp Limits forfor TSSS Insertion Times TSSS Insertion Times BOC to EOCLB (Continued)
(Continued)
MCPRPp MCPR Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel 100.0 1.53 1.52 1.52 90.0 1.58 1.58 1.58 50.0 SO.O --
50.0 SO.O 1.87 1.85 1.8S TBVOOS TBVOOS 40.0 1.98 1.98 2.00 and FHOOS 26.0 2.37 2.34 26.0 at > SO%F 50%F 3.18 3.24 3.24 50%F 23.0 at> SO%F 3.40 3.40 3.40 26.0 at < 50%F S SO%F 2.89 2.97 23.0 at S< SO%F 50%F 3.15 3.1S 3.26 100.0 1.51 1.S1 1.52 1.S2 90.0 1.57 1.57 1.57 50.0 SO.O ---
50.0 SO.O 1.86 1.86 1.84 1.84 TBVOOS TBVOOS 40.0 1.91 1.91 1.94 1.94 and PLUOOS PLUOOS 26.0 2.27 2.25 2.2S 26.0 at > SO%F 50%F 3.05 3.0S 3.11 3.11 23.0 at > SO%F 50%F 3.28 3.27 26.0 at S< SO%F 50%F 2.75 2.7S 2.84 23.0 at S< 50%F SO%F 3.00 3.08 100.0 100.0 1.50 1.S0 1.49 1.49 90.0 1.55 1.SS 1.55 1.SS 50.0 ---
50.0 SO.O 1.86 1.86 1.84 FHOOS FHOOS 40.0 1.95 1.9S 1.97 1.97 and PLUOOS PLUOOS 26.0 2.32 2.30 2.30 26.0 at > SO%F 50%F 2.69 2.80 23.0 at > 50%F SO%F 2.83 2.94 26.0 at S< SO%F 50%F 2.63 2.70 23.0 at S< SO%F 50%F 2.76 2.85 2.8S 100.0 100.0 1.53 1.S3 1.53 1.S3 90.0 1.58 1.S8 1.58 1.S8 50.0 SO.O --
50.0 SO.O 1.87 1.87 1.85 1.8S EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.98 2.00 40.0 1.98 2.00 TBVOOS, anFOOS, 26.0 2.37 2.34 and FHOOS 26.0 at > 50%F 3.18 26.0 at > SO%F 3.18 3.24 23.0 at > 50%F 3.40 3.40 26.0 at S< SO%F 50%F 2.89
-2.89 2.97 23.0 at S< SO%F 50%F 3.15 3.1S 3.26 3.26 AREVA NP Inc.
ANP-2864(NP)
Ferry Unit Browns Ferry Unit 11 Cycle Cycle 9 Revision 2 Safety Analysis Reload Safety Analysis Page Page 8-18 8-18 Table 8.4 MCPR MCPRpp Limits Limits for for TSSS Insertion Times Times BOC to EOCLB BOCto (Continued)
, (Continued)
MCPRpp MCPR
. Operating Power ATRIUM-10 GE14 GE14 Condition (% of rated)
(% Fuel Fuel 100.0 100.0 1.51 1.52 1.52 90.0 90.0 1.57 1.57 1.58 1.58 50.0 - -
50.0 1.86 1.86 1.84 EOC-RPT-OOS, EOC-RPT -OOS, 40.0 1.91 1.94 TBVOOS, TBVOOS, 26.0 26.0 2.27 2.25 PLUOOS and PLUOOS 26.0 at > 50%F 3.05 3.11 3.11 23.0 at > 50%F 50%F 3.28 3.27.
3.27 26.0 at S< 50%F 50%F 2.75 2.84 23.0 at s< 50%F 50%F 3.00 3.08 100.0 1.50 1.49 1.49 90.0 1.55 1.55 1.55 50.0 ---
50.0 1.86 1.84 1.84 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.95 1.97 FHOOS, 40.0 1.95 1.97 FHOOS, and PLUOOS and PLUOOS 26.0 at26.0
> 50%F 2.32 2.69 2.30 26.0 at:> 50%F 2.69 2.80 2.80 23.0 at >> 50%F 2.83 2.94 2.94 26.0 at <s 50%F 2.63 2.70 2.70 23.0 at 50%F 26.0 'at> 3.18 3.24 3.24 23.0 23.0 at at > 50%F 50%F 3.40 3.40 3.40 26.0 26.0 at S< 50%F 50%F 2.89 2.97 2.97 23.0 23.0 at at S< 50%F 3.15 3.26 100.0 100.0 1.53 1.53 1.53 1.53 90.0 90.0 1.58 1.58 1.58 1.58 50.0 50.0 --
~~EOC-RPT-OOS,,~~
EOC-RPT-OOS, ' 50.0 1.87 1.87 1.85 1.85 TBVOOS, 40.0 1.98 1.98 2.00 2.00 FHOOS, FHOOS, 26.0 26.0 2.37 2.34 2.34 and PLUOOS PLUOOS 26.0 26.0 at at > 50%F 50%F 3.18 3.24 3.24 23.0 at at > 50%F 50%F 3.40 3.40 3.40 26.0 26.0 at at S< 50%F 50%F 2.89 2.89 2.97 2.97 23.0 at at s< 50%F 50%F 3.15 3.26 3.26 AREVA AREVA NP Inc.
~~Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Browns Ferry Unit 1 Cycle 9 . Revision Revision 2 Reload Safety Analysis Analysis Page 8-19 8-19 Table Table 8.5 MCPRMCPRpp Limits for NSS Insertion NSS Insertion Times Times BOC SOC to to FFTRJCoastdown*
FFTRlCoastdown*
~~MCPRpp MCPR Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%~~
~~(% of rated) Fuel Fuel 100.0 1.46 1.47 1.47 90.0 1.52 1.52 1.S2 SO.O 50.0 ---~~
50.0 SO.O 1.83 1.81 Base case 40.0 1.93 1.96 1.96 operation operation 26.0 2.31 2.29 2.29 26.0 at > SO%F 50%F 2.69 2.80 2.80 23.0 at at> > SO%F 50%F 2.83 2.94 2.94 26.0 at s- SO%F 50%F 2.63 . 2.70 2.70 23.0 at < SO%F at::; 50%F 2.76 2.85 2.8S 100.0 1.50 1.S0 1.50 1.S0 90.0 1.55 1.SS 1.55 1.SS 50.0 SO.O ---
50.0 SO.O 1.85 1.8S 1.83 1.83 40.0 1.96 1.99 1.99 TBVOOS 26.0 2.35 2.3S 2.32 2.32 26.0 at > SO%F 50%F 3.18 3.24 23.0 at > SO%F 50%F 3.40 3.40 26.0 at < 50%F s SO%F 2.89 2.97 23.0 at < 50%F s SO%F 3.15 3.1S 3.26 3.26 100.0 1.46 1.46 1.47 1.47 90.0 1.52 1.S2 1.53 1.S3 50.0 SO.O ---
50.0 SO.O 1.83 1.83 1.81 40.0 40.0 1.93 1.93 1.96 1.96 EOC-RPT-OOS40019 EOC-RPT-OOS 26.0 2.31 2.29 26.0 at > SO%F 50%F 2.69 2.80 at > SO%F 23.0 at> 50%F 2.83 2.94 2.94 26.0 at s< 50%F SO%F 2.63 2.70 23.0 at::; SO%F at < 50%F 2.76 2.8S 2.85
~~Limits support operation with any combination of 1 MSRVOOS, MSRVOOS, up to 2 TIPOOS (or the equivalent equivalent number number of TIP channels), and up to SO%~~
50% of the LPRMs out-of-service.
out-of-service. Limits also support operation with FFTR/FHOOS FFTRlFHOOS which bounds bounds operation with feedwater feedwater heaters in-service.
in-service. For single-loop single-loop MCPRPp limits will be 0.03 higher.
operation, MCPR AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Analysis Reload Safety Analysis Page 8-20 Table 8.5 MCPRMCPRpp Limits for NSS Insertion Times NSS Insertion Times FFTR/Coastdown BOC to FFTRlCoastdown (Continued)
(Continued)
MCPR MCPRPp Operating Condition (%Power of rated) ATRIUM-10 ATRIUM-10 Fuel GE14 GE14 Fuel Condition (% of rated) Fuel Fuel 100.0 1.46 1.47 1.47 90.0 1.52 1.52 1.52 50.0 ---
50.0 1.86 1.84 1.84 PLUOOS 40.0 1.93 1.96 1.96 PLUOOS 26.0 26.0 2.31 2.29 2.29 26.0 at at> > 50%F 2.69 2.80 2.80 23.0 at > 50%F 2.83 2.94 2.94 50%F 26.0 at S< SO%F 2.63 2.70 2.70 23'.0 S 50%F 23.0 at < 2.76 2.85 2.85 100.0 1.50 1.S0 1.51 90.0 1.55 1.SS 1.57 1.S7 50.0 SO.O ---
50.0 SO.O 1.85 1.85 1.83 1.83 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.96 1.96 1.99 1.99 and TBVOOS 26.0 26.0 2.35 2.32 2.32 26.0 at > SO%F 50%F 3.18 3.24 3.24 50%F 23.0 at > SO%F 3.40 3.40 3.40 26.0 at S- 50%F 50%F 2.89 2.97 23.0 at S< 50%F 50%F 3.15 3.26 3.26 100.0 100.0 1.46 1.46 1.47 1.47 90.0 1.52 1.S2 . 1.53 1.53 50.0 ---
50.0 SO.O 1.86 1.86 1.84 1.84 EOC-RPT-OOS EOC-RPT-OOS 40.0
.40.0 1.93 .1.96 and PLUOOS 26.0 2.31 2.29 26.0 at > 50%F SO%F 2.69 2.80 2.80 23.0 at > 50%F SO%F 2.83 2.94 26.0 at S< 50%F 2.63 2.70 2.70 23.0 at S< 50%F 2.76 2.8S 2.85 AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 ' . Revision 2 Reload Safety Analysis Analysis Page 8-21 Table 8.5 MCPRp MCPRp Limits for NSS Insertion NSS Insertion Times Times FFTR/Coastdown BOC to FFTRlCoastdown (Continued)
(Continued)
MCPRPp MCPR Operating Power ATRIUM-10 GE14 GE14 Condition (%
(% of rated) Fuel Fuel 100.0 100.0 1.50 1.50 ' 1.50 1.50 90.0 1.55 1.55 ' 1.55 1.55 50.0 --
50.0 1.86 1.84 1.84 TBVOOS TBVOOS 40.0 1.96 1.96 1.99 and PLUOOS PLUOOS 26.0
',26;0 2.35 2.32 26.0 at > 50%F 3.18 3.24 23.0 at > 50%F 3.40 3.40 at*s 50%F 26.0 at 2.89 2.97 23.0 at s< 50%F 3.15 3.26 100.0 100.0 1.50 1.50 1.51 90.0 1.55 1.55 1.57 1.57 50.0 ---
50.0 1.86 1.84' 1.84 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.96 1.99 40.0 1.96 1.99 TBVOOS, TBVOOS, 26.0 2.35 2.32 and PLUQOS 26.0
~~2. 2.35~~
.523 2.32 and PLUOOS 26.0 at >50%F
> 50%F 3.18 3.24 23.0 at > 50%F 3.40 ' 3.40 26.0 at S< 50%F 2.89 2.97 23.0 at s< 50%F 50%F 3.15 3.26 AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns. Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Safety Analysis Analysis Page 8-22 8-22 Table 8.6 MCPRp MCPRp Limits for Insertion Times TSSS Insertion Times FFTR/Coastdown*
BOC to FFTRlCoastdown*
MCPRPp
. MCPR Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel 100.0 1.50 1.50 1.49 90.0 1.55 1.55 1.55 1.55 50.0 . --- --
50.0 1.84 1.84 1.82 Base case 40.0 1.95 1.95 1.97 1.97 operation operation 26.0 2.32 2.30 26.0 at > 50%F 2.69, 2.69- 2.80 23.0 at > 50%F 2.83 2.94 26.0 at s< 50%F 2.63 2.70 23.0 23:0 at s< 50%F 2.76 2.85 100.0 100.0 1.53 1.53 1.52 90.0 1.58 1.58 1.58 50.0 --
50.0 1.87 1.87 1.85 1.85 40.0 1.98 1.98 2.00 TBVOOS 26.0 2.37 2.34 26.0 at > 50%F 3.18 3.24 3.24 at > 50%F 23.0 at> 3.40 3.40 26.0 at s< 50%F 2.89 2.97 23.0 at s< 50%F 3.15 3.26 100.0 100.0 1.50 1.50 1.49 1.49 90.0 1.55 1.55 1.55 1.55 50.0 ---
50.0 1.84 1.82 1.82 40.0 1.95 1.97 1.97 EOC-RPT-OOS 26.0 2.32 . 2.30 26.0 at > 50%F 2.69 2.80 23.0 at > 50%F 2.83 2.94 2.94 26.0 at <
s 50%F 2.63 2.70 2.70 23.0 at <
s 50%F 2.76 2.85 2.85
Limits support support operation operation with any any combination combination of 1 MSRVOOS, MSRVOOS, up to 2 TIPOOS (or the equivalent equivalent number of TIP channels), and up to 50% of the LPRMsLPRMs out-of-service.
out-of-service. Limits also support operation operation with FFTRlFHOOS FFTR/FHOOS which bounds operation operation with feedwater feedwater heaters in-service. For single-loop single-loop MCPRpp limits will be 0.03 higher.
operation, MCPR AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page 8-23 8-23 Table 8.6 MCPR Table MCPRpp Limits for TSSS Insertion TimesTimes BOC to FFTR/Coastdown FFTRlCoastdown (Continued)
(Continued)
MCPRP MCPR p Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (% of rated)
(% Fuel Fuel 100.0 100.0 1.50 1.49 1.49 90.0 1.55 1.55 1.55 50.0 ---
50.0 1.86 1.84 1.84 40.0 1.95 1.97 1.97 PLUOOS PLUOOS 26.0 2.32 2.30 2.30 26.0 at > 50%F 2.69 2.80 2.80 23.0 at > 50%F 2.83 2.94 2.94 26.0 at <S 50%F 2.63 2.70 2.70 23.0 at 50%F 3.18 3.24 3.24 23.0 at > 50%F 3.40 3.40 3.40 26.0 at <S 50%F 2.89 2.97 2.97 at:<50%F 23.0 at s 50%F 3.15 3.26 3.26 100.0 1.50 1.50 1.49 1.49 90.0 1.55 1.55 1.55 1.55 50.0 ---
50.0 1.86 1.86 1.84 1.84 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.95 1.95 1.97 1.97 and PLUOOS PLUOOS 26.0 2.32 2.32 2.30 26.0 at > 50%F 50%F 2.69 2.80 23.0 at > 50%F 50%F 2.83 2.94 26.0 at S< 50%F 50%F 2.63 2.63 2.70 23.0 at S< 50%F 50%F 2.76 2.76 2.85 AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2****
2 Reload Safety Analysis Analysis Page Page 8-24 8-24 Table 8.6 MCPRp MCPRp Limits for TSSS Insertion TSSS Insertion Times Times BOC to FFTRlCoastdown SOC FFTR/Coastdown (Continued)
~~(Continued)~~
~~MCPRpp MCPR Operating Operating Power Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%~~
~~(% of rated) Fuel Fuel 100.0 100.0 1.53 1.53 1.52 1.52 90.0 1.58 1.58 1.58 50.0 --~~
50.0 1.87 1.87 1.85 1.85 TBVOOS TBVOOS 40.0 1.98 1.98 2.00 and PLUOOS 26.0 2.37 2.34 26.0 at >50%F 3.18 .* 3.24 23.0 at > 50%F 3.40 3.40 26.0 at s< 50%F 26.0 at 50%F 2.89 2.89 2.97 at*s 50%F 23.0 at 3.15 3.26 100.0 1.53 1.53 1.53 1.53 90.0 1.58 1.58 1.58 50.0 ---
50.0 1.87 1.87 1.85 1.85 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.98 2.00 40.0 1.98 2.00 TBVOOS, 26.0 2.37 2.34 and PLUOOS 26.0 at26.0
~~> 50%F 2.37 3.18 2.34 3.24 26.0 at > 50%F 3.18 3.24 23.0 at > 50%F 3.40 3.40 .~~
~~26.0 at s< 50%F 2.89 2.97 23.0 at s< 50%F 50%F 3.15 3.26 3.26 AREVA NP Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision.2 Revision*2 Reload Safety Analysis Safety Analysis 8-25 Page 8-25 Table 8.7 Flow-Dependent Flow-Dependent MCPR MCPR Limits Limits
~~-ATRIUM-10~~
~~. ATRIUM-10 and GE14 GE14 Fuel Core Flow Core Flow~~
~~(% of rated)~~
~~(% rated) MCPRff MCPR 30.0 1.61 78.0 1.28 107.0 1.28 AREVA AREVA NP Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~Browns Ferry Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Safety Analysis Reload Safety Analysis Page 8-26 8-26 .~~
~~Table 8.8 ATRIUM-10 Steady-State ATRIUM-10 Steady-State LHGR Limits Limits Peak Pellet Exposure Exposure LHGR LHGR (GWd/MTU)~~
~~(GWd/MTU) (kW/ft)~~
~~(kW/ft) 0.0 13.4 13.4 18.9 18.9 13.4 13.4 74.4 7.1 AREVA NP Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page 8-27 Table Table 8.9 ATRIUM*10 ATRIUM-10 LHGRFAC LHGRFACpp Multipliers Multipliers for for NSSITSSS Insertion NSSITSSS Insertion Times Times All All Cycle 9 Exposures*
~~EOOS Power ATRIUM-10 ATRIUM-10 Condition (%~~
(% rated) LHGRFACp LHGRFAC p 100.0 1.00 77.6 0.82 Base 26.0 26.0 0.62 0.62 case 26.0 at > 50%F 0.52 26.0 at > SO%F 0.S2 operation (TBVIS)t . 50%F 23.0 at > SO%F 0.50 O.SO 26.0 at < 50%F S SO%F 0.55.
~~O.SS.~~
~~23.0 at S< SO%F 50%F 0.54 0.S4 100.0 0.88 26.0 0.60 TBVOOS1 26.0 at > SO%F 50%F 0.43 TBVOOS:I:~~
~~50%F 23.0 at > SO%F 0.41 at5S<50%F.~~
~~26.0 at SO%F* 0.51 0.S1 23.0 at S< 50%F SO%F 0.47 Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent~~
~~Limits support operation with any combination of 1 MSRVOOS, up to 2 TIPOOS (or the equivalent number number of TIP channels), and up to SO%~~
50% of the LPRMs out-of-service.
out-of-service. Base case supports single-loop operation.
tt Limits are applicable for all Limits are applicable for all the the EOOS scenarios presented EOOS scenarios presented in in Table Table 1.1 1.1 except except those those that include that include TBVOOS.
Limits are applicable applicable for all the EOOS scenarios presented in Table 1.1 including including those with TBVOOS.
TBVOOS.
AREVA NP Inc.
AREVA
ANP-2864(NP)
Browns Ferry Unit Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page 8-28 8-28 Table Table 8.10 GE14 LHGRFACp Multipliers for*
LHGRFAC p Multipliers for NSS/TSSS Insertion Times NSSITSSS Insertion Times All Cycle 9 Exposures*
EOOS Power GE14 EOOS Power GE14 Condition (%rated)
(% LHGRFACPp LHGRFAC 100.0 1.00 1.00 77.6 0.79 Base 26.0 26.0 0.57 0.57 case ope case operation 26 at 26 at >> 50%F 50%F 0.46 operation (TBVIS)
(TBVIS)t 23 at > 50%F . 0.42 26 at <s 50%F 0.51 23 at 50%F 0.37 23 at at>> 50%F 0.31 26 at <s 50%F 0.47 23 at 50%F 50%F 2.57 23 at > 50%F 50%F 2.70 26 at s< 50%F 2.53 23 at s< 50%F 2.65 Figure Figure A.1 BOC to NEOC A.1 BOC Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion Times NSS Times Base Case
~~'Base AREVA AREVA NP Inc. Inc~~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~Browns Ferry Unit 1 Cycle 9 Revision Revision 2 ~~~
~~Reload Safety Safety Analysis Analysis Page A-3 A-3 3.0 o]D FWCF FWCF oo LRNB LRNB At:. CRWE CRWE 2.5 2.5~~
+'
~~'EE~~
_J
~~....J 0 0~~
~~C_ 2.0~~
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C-_
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2:
00 o o 1.5 1-o 00 1.0 o0 10 20 30 30 40 50 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Power MCPRp Power MCPRp
(%of rated)
(% Limit Limit 100 100 1.41 90 1.48 1.48 50 SO 1.75 1.7S 50 SO 1.81 40 1.89 1.89 26 2.19 2.19 26 at > 50%F SO%F 2.68 23 at > 50%F SO%F 2.80 26 at S< SO%F 50%F 2.60 23 at S< SO%F 50%F 2.72 Figure A.2 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for MCPR for GE14 Fuel NSS Insertion NSS Times Insertion Times Base Case AREVA AREVA NP Inc. Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page Page A-4 A-4 3.0 3.0 , . - - - - - y - - - - - , - - - , - - - - , - - - , - - - . . . , - - - - - - , - - - - r - - - , - - - , , - - - - - ,
oo3 FWCF o LRNB LRNB A
I:> CRWE CRWE 2.5 [-
~~EE 0~~
~~.J 0 c 2.0 rya.~~
00 0::::
n3 Q..
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1.5 1-1.5
.00 1.0 i i i j i o0 10 20 30 40 50 60 70 80 90 100 110 110 Power (% Rated)
(% Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.44 90 1.50 1.S0 50 SO 1.76 1.76 50 SO 1.83 1.83 40 1.90 1.90 26 2.21 26 at > 50%F SO%F 2.57 2.S7 23 at > 50%F SO%F 2.70 26 at ~< 50%F SO%F 2.53 2.S3 23 at < ~ 50%F SO%F 2.65 2.6S Figure A.3 BOC to EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for ATRIUM-tO ATRIUM-10 Fuel NSS NSS Insertion Insertion Times Times Base Case AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis A-5 Page A-S 3.0 o FWCF o LRNB
"" CRWE 2.5
-+J
'EE
--.J 0 0
Cl. 2.0 C. 0 (Y
0*
0....
U
~
1.5 o
1.0 L - _ - - - L_ _- L ._ _. l . - _ - - - L_ _- L_ _..L......_-----I_ _-.L._ _- ' -_ _L-_--'
o0 10 20 30 40 50 60 70 80 . 90 100 11,0 11,0 Power (%
Power (% Rated)
Power MCPRpp MCPR
(% of rated) Limit 100 100 1.45 1.4S 90 1.51 1.S1 50 SO 1.75 1.7S SO 50 1.81 40 1.89 26 2.19 2.19 26 at > 50%FSO%F 2.68 23 at > 50%FSO%F 2.80 2.80 26 at S< SO%F 50%F 2.60 23 atsat < SO%F 50%F 2.72 2.72 Figure Figure A.4 A.4 BOC BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel NSS NSS Insertion Times Insertion Times Base Case Case AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 2-Revision 2 Analysis Reload Safety Analysis Page A-6 A-6 3.0, 3.0 .------,----r---~-----r--_._----.:....___-___r--__,_--_r_-__,r__-___,
o FWCF FWCF o LRNB LRNB at;. CRWE CRWE 2.5 1-
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t
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0"0 1.5 I-0o .0 I I 1.0 L...-_----L_ _..:..l.-_ _-'--_---L_ _---L..._ _..l..-_----l_ _--L_ _...l.-_ _I....-_---l o0 10 20 30 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRP Power ' MCPRp
(%
(% of rated) rated) Limit
'Limit 100 1.46 1.46 90 1.52 1.S2 50 SO ---
50 1.83 1.83 40 1.93 1.93 26 2.31 26 at > 50%F 2.69 2.69 23 at > SO%F at> 50%F 2.83 2.83 26 at < 50%F at::;; 50%F 2.63
,23 at::;;
23 at < S.D%F 50%F 2.76 2.76 Figure Figure A.5 A.5 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion NSS Insertion Times Times Base Case Case AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Reload Safety Analysis Analysis PageA-7 Page A-7 3.0 .-------,-----.----r------r----.---~-'--___,--___r"--_r_--.____-___,
I I I I I , I II I
\oo FWCF FWCF o LRNB A
t;. CRWE CRWE 2.5
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---l 0 0E 0 0.. 2.0 0 0:::
a-(L U
~
1.5 I-0 o
II I I I I I i I 1.0 1.0 l...-_----'-_ _--'--_ _-'---_--1._ _--L_ _..l..-_---1_ _---L.._ _. . l -_ _l . . . - _ - - I 0
.0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.47 1.47 90 1.52 1.52 50 ---
50 1.81 40 1.96 1.96 26 2.29 26 at at>> 50%F 2.80 23 at at>> 50%F 2.94 26 at <s 50%F 2.70 23 at s< 50%F 2.85 Figure A.6 FFTR/Coastdown A.6 BOC to FFTRICoastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times NSS Insertion Times Case Base Case AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2*-
2 -
Reload Safety Safety Analysis Analysis Page A-8 A-8
~~3.0 3.0 o~~
O3 FWCF FWCF o LRNB LRNB A
A CRWE CRWE 2.5
-+J
'EE 0 0 0
---l 0 c 2.0 0... 0 0::
a_
0...
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1.0 o
0 10 20 30 40 50 60 70 80 90 100 110 110 Power (% Rated)
Power MCPRp Power MCPRp
(%
(% of rated) Limit Limit 100 100 1.47 90 1.53 50 1.78 50 1.84 40 1.91 26 2.22 26 at > 50%F 50%F 2.57 23 at > 50%F 50%F 2.70 26 at s< 50%F 2.53 23 at S< 50%F 2.65 Figure A.7 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 Fuel Insertion Times TSSS Insertion Times Case Base Case AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Cycle 9 Browns Ferry Unit 1 CyCle Revision 2 Revision Reload Reload Safety Analysis Analysis Page A-9 3.0 .-------r-----r---.,-----,------.---......-------,----.,-----r---,------,
Oo FWCF FWCF oo LRNB LRNB A
l!. CRWE 2.5
EE
---l 00 o 0 0.. 2.0 0 0::
Q..
()
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1.5 0 0
o0 1.0 o
0 . 10 20 30 40 50 60 70 80 90 100 110 110 Power (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.44 1.44 90 1.51 50 1.77 1.77 50 1.82 1.82 40 1.90 1.90 26 2.20 26 at > 50%F 50%F 2.68 2.68 23 at >> 50%F 50%F 2.80 2.80 26 at <s 50%F 2.60 2.60 23 at S< 50%F 2.72 2.72 A.8 BOC to NEOC Figure A.a NEOC Power-Dependent Power-Dependent MCPR for Limits for GE14 Fuel TSSS Times TSSS Insertion Times Base Case Base AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Browns Ferry Unit Unit 11 Cycle Cycle 9 Revision Revision 22 Reload Safety Analysis Reload Analysis Page A-10A-10 3.0 o FWCF o LRNB LRNB
""A CRWE CRWE 2.5 F
'E
~~i o 00 0~~
0- 2.0 00 0-0:::
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00 0 1.5 I- I0 0 6 1.0 '--_----'-_ _--'-_ _. l . - _ - - - ' ._ _- L ._ _...l.....-_----l_ _---'-_ _....I.-_ _1 - _ - - - I 0o 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (%(% Rated)
Power MCPRP Power MCPRp
(%
(% of rated) Limit Limit 100 1.47 1.47 90 1.53 1.53 50 1.78 1.78 50 1.84 1.84 40 1.91 26 2.22 2.22 26 at > SO%F 50%F 2.57 2.57 23 at>
at > SO%F 50%F 2.70 2.70 26 at 5s 50%F SO%F 2.53 2.53 23 23 at ~~CRWE 2.5~~
~~-+-'~~
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~~.-J o 0 cL 2.0 a.. 0 0:::~~
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~
~~1.5 1.0 1.0 '--_----'-_ _-'--_ _-'---_----1_ _--'--_ _...I..-_---'_ _---'-_ _....I...-_ _'---_.......J o~~
~~0 10 20 30~~
~~.30 40 50 60 70 80 90 100 100 110 110 Power (%~~
~~Power (% Rated)~~
~~Rated)~~
~~Power MCPRp MCPRp~~
(%
(% of rated) Limit Limit 100 100 1.48 1.48 90 1.53 1.S3 50 SO 1.77 1.77 50 SO 1.82 1.82 40 1.90 1.90 26 2.20 26 at > 50%F SO%F 2.68 23 at at> > 50%F SO%F 2.80 26 at at:5< SO%F 50%F 2.60 23 at < 50%F at:5 SO%F 2.72 Figure A.10 A.1 0 BOC BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for
~~. GE14 Fuel TSSS Insertion TSSS Insertion Times Times Base Case Case AREVA NP Inc.Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~Browns Ferry Unit 1 Cycle 9 Browns ,Revision~~
.Revision 2 Reload Safety Analysis Analysis Page A-12 A-12 3.0 , - - - - - r - - - , - - - - r - - - - - - r - - - - , - - , - - - - - , - - - - , - - - - , - - - , - - - - - .
~~3.0 o FWCF o LRNB,~~
~~'" CRWE 2.5~~
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~~1.5 1.0 0o 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)~~
~~Rated)~~
~~Power MCPRP Power MCPRp~~
~~(%of rated)~~
~~(% Limit Limit 100 1.50 90 1.55 50 ---~~
50 1.84 1.84 40 1.95 1.95 26 2.32 26 at > > 50%F 50%F 2.69 23 at > 50%F 2.83 26 at 26 at s< 50%F 2.63 2.63 23 at s< 50%F 2.76 Figure A.11 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power.Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM*10 TSSS TSSS Insertion Times Times Base Case AREVA NP Inc Inc...
(
~~( ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Revision Reload Reload Safety Analysis Analysis Page A-13 A-13 3.0 , . . . . - - -I - - r - - -I- r - - - , .I- - - - - - -
~~I r----r I ----,--~~
~~I - - - - - ,I - - - , - - -~~
~~I . . . , . - -I - , . .- . . . .I . , - - - - ,~~
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1.5 1.5 1-0I I I I II I0 1.0 o0 10 20 30 40 50 60 70 s0 80 90 100 100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRP Power MCPRp
(% of rated)
(% rated) Limit Limit 100 100 1.49 1.49 90 1.55 1.55 50 ---
50 1.82 1.82 40 1.97 1.97 26 2.30 2.30 26 at > 50%F 2.80 2.80 23 at > 50%F 2.94 2.94 26 at 5s 50%F*
50%F 2.70 2.70 23 at > 50%F 50%F 3.05 3.05 23 23 at > 50%F 3.28 26 26 at s< 50%F 2.75 2.75 23 at at s< 50%F 3.00 3.00 Figure A.13 BOC BOC to NEOCNEOC Power-Dependent MCPR Power-Dependent MCPR Limits for for ATRIUM-10 Fuel ATRIUM-10 NSS NSS Insertion Insertion Times Times TBVOOS-TBVOOS' AREVA AREVA NP NP Inc.
~~Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Browns Revision*2 Revision 2 Reload Safety Analysis Reload Analysis Page A-15A-15 3.5 , . . . . - - - - , - - - - r - - - , . . . . - - - - " T - - - - , - - - - , . - - - - - , - - - - - , - - - - r - - - . . . - - - - - - ,
~~o FWCF o LRNB 3.0 3.0 CRWE~~
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~~0 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)~~
~~Rated)~~
~~Power MCPRP Power MCPRp~~
~~(% of rated) Limit Limit 100 1.44 1.44 90 1.51 50 ---~~
50 1.81 40 1.92 1.92 26 2.23 26 at > 50%F50%F 3.11 3.11 23 at > 50%F50%F 3.27 3.27 26 at s< 50%F 2.84 23 at s< 50%F 3.08 FigureA.14 Figure A.14 BOC BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel GE14 NSS Insertion Times N55 Times TBVOOS TBV005 AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page A-16 A-16 3.5 3.5 I III o
~~D FWCF FWCF o~~
~~0 LRNB LRNB 3.0 3.0 A A CRWE CRWE~~
~~-+oJ 2.5~~
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oo oA A
1.5 AQ I I II I II I 1.0 '--_--'-_ _- L - _ - - - L _ _- ' -_ _' - - _ - - ' - _ _- ' - - _ - - - L _ _- ' -_ _' - - _ - - '
I I I o
0 10 20 30 30 40 50 60 70 70 80 90 100 100 110 110 Power Power (%(% Rated)
Power Power MCPRPp MCPR
(% of rated) Limit Limit 100 100 1.48 1.48 90 1.S4 1.54 50 SO --
SO 50 1.83 1.83 40 1.90 26 2.26 26 at > 50%F SO%F 3.05 3.0S 23 at > 50%F SO%F 3.28 26 at S< SO%F 50%F 2.75 2.7S 23 at -< 50%F S SO%F 3.00 3.00 Figure Figure A.15 A.1S BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Insertion Times TBVOOS TBVOOS AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Reload Safety Analysis Analysis Page A-17 A-17 3.5 r - - - - , - - - , - - - , - - - . - - - , . - - - - - , - - - , - - - , - - - . - - - , . - - - - - - ,
o FWCF o LRNB 3.0 A CRWE CRWE
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1.5 at. A
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o 0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Power. MCPRp Power MCPRp
(% of rated)
(% rated) Limit Limit 100 1.49 1.49 90 1.55 1.55 50 ---
50 1.81 40 1.92 1.92 26 2.23 26 at > 50%F 3.11 3.11 23 at > 500/%F 50%F 3.27 at*s 50%F 26 at 2.84 23 at S< 50%F 3.08 Figure A.16A.16 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel GE14 NSS Insertion Times NSS Times TBVOOS TBVOOS AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page A-18 A-18 4.0 r - - - - - , - - - , - - - - , - - . . . . , . . - - - rI - - - - - I, - - - , -I - - - , - - . . . . , . . - -I - r - - - - - ,
IIIII o FWCF 3.5 o LRNB 3.S
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Rated)
Power MCPRP Power MCPRp
(% of rated)
(% Limit 100 100 1.50 1.50 90 1.55 1.55 50 ---
50 1.85 1.85 40 1.96 1.96 26 2.35 2.35 26 at > 50%F 3.18 3.18 23 atat> > 50%F 50%F 3.40 3.40 26 at s< 50%F 2.89 2.89 23 atat5 s<50%F 50%F 3.15 3.15 Figure Figure A.17 A.17 BOC BOC to FFTR/Coastdown FFTRlCoastdown Power-Dependent MCPR Limits Power-Dependent Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Insertion Times TBVOOS TBVOOS AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-19 Page A-19 4.0 0o FWCF FWCF o LRNB 3.5 3.5 At:;. CRWE CRWE 3.0 3.0
..f-J
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o0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRP Power MCPRp
(% of rated) rated) Limit Limit 100 1.50 1.50 90 1.55 1.55 50 ---
50 1.83 1.83 40 1.99 1.99 26 2.32 2.32 26 at > 50%F 3.24 23 at > 50%F 3.40 26 at SO%F 3.05 3.0S at > 50%F 23 at> SO%F 3.28 26 at S< 50%F SO%F 2.75 2.7S 23 at s< 50%F SO%F 3.00 Figure A.19 Figure A.19 BOC BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-IO Fuel ATRIUM-10 TSSS Times TSSS Insertion Times TBVOOS
~~. TBVOOS AREVA NP Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-21 3.5 3.5 0o FWCF FWCF o LRNB LRNB 3.0 1- aA CRWE CRWE
~~..... 2.5 F-~~
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0 10 20 30 40 50 50 60 60 70 80 90 100 100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRp Power MCPRp
(%
(% of rated) rated) Limit 100 1.48 1.48 90 1.55 1.55 50 50 ---
50 1.82 1.82 40 1.94 1.94 26 2.25 2.25 26 at > 50%F 3.11 3.11 23 at > 50%F 3.27 3.27 26 at <s 50%F 2.84 23 at 50%F SO%F 3.05 3.0S 23 23 at at>> 50%F SO%F 3.28 3.28 at < 50%F 26 at::;; SO%F 2.75 2.7S 23 at 5 50%F 23 at::;; SO%F 3.00 3.00 Figure Figure A.21A.21 BOC BOC toto EOCLB EOCLB Power-Dependent MCPR Power-Dependent MCPR Limits for for ATRIUM*10 Fuel ATRIUM-10 TSSS TSSS Insertion Insertion Times Times TBVOOS TBVOOS AREVA AREVA NP NP Inc.
~~Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 . Revision 2 Reload Safety Analysis Analysis Page A-23 Page A-23 3.5 3.5 O0 FWCF FWCF o0 LRNB LRNB 3.0 3.0 A t;. CRWE CRWE J
~~..... 2.5 2.5~~
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Rated)
. Power MCPRp Power MCPR p
(% of rated)
(% rated) Limit Limit 100 100 1.52 1.52 90 1.57 1.57 50 50 ---
50 1.82 1.82 40 1.94 1.94 26 2.25 2.25 26 at > 50%F 3.11 23 at > 50%F 3.27 3.27 at < 50%F 26 at:5 2.84*
2.84 23 at:5 at < 50%F 3.08 3.08 Figure A.22 A.22 BOC to EOCLBEOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for GE14 Fuel TSSS Insertion TSSS Insertion Times Times TBVOOS TBVOOS AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page A-24 A-24 4.0 I I I I I I I I I o FWCF 3.5 0o LRNB A CRWE 3.0
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Power (% Rated)
Power MCPR MCPRPp
(% of rated)
(% Limit Limit 100 100 1.S3 1.53 90 90 1.58 1.S8 50 :
SO --
50 SO 1.87 1.87 40 40 1.98 1.98 26 26 2.37 2.37 26 at 26 at >> 50%F SO%F 3.18 3.18 23 at 23 at >> 50%F SO%F 3.40 3.40 26 at 26 at S< 50%F SO%F 2.89 2.89 23 at 23 at:<
S 50%F SO%F 3.15 3.1S Figure A.23 BOC to FFTR/Coastdown Figure A.23 BOC to FFTRlCoastdown Power-Dependent MCPR Limits for Power-Dependent MCPR Limits for
. ATRIU ATRIUM-10M-10 Fuel Fuel TSSS Insertion Times TSSS Insertion Times TBMOOS TBVOOS AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page A-25 A-25 4.0 I I I II II oO FWCF 3.5 o LRNB 3.S A
I:>. CRWE 3.0
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Power MCPRP Power MCPRp
(% of rated)
(% Limit Limit 100 1.52 1.52 90 1.58 50 ---
50 1.85 1.85 40 2.00 26 2.34 26 at > 50%F 50%F 3.24 23 at > 50%F 3.40 26 at ~< 50%F 2.97 2.97.
23 at ~< 50%F 3.26 Figure A.24 BOC to FFTR/Coastdown FFTRICoastdown Power-Dependent Power-Dependent MCPR Limits Limits forfor GE14 Fuel TSSS TSSS Insertion TimesTimes TBVOOS TBVOOS AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit Unit11 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-26 3.0 3.0 o FWCF o LRNB r,. CRWE 2.5 2.5
~~EE 0~~
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Power MCPRp Power MCPRp
(%
(% of rated) Limit Limit 100 100 1.43 90 1.50 1.50 50 1.76 1.76 50 1.83 1.83 40 1.90 1.90 26 2.21 26 at>
at > 50%F 2.57 23 at at>> 50%F 2.70 26 at s< 50%F 2.53 23 at S< 50%F 2.65 Figure A.25 A.2S BOC to NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM~10 Fuel NSS Insertion Times NSS Times EOC-RPT-OOS EOC-RPT-005 AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Ferry Unit Unit 11 Cycle Cycle 99 Revision Revision 22 Reload Reload Safety Safety Analysis Analysis Page Page A-27 A-27 3.0 3.0 , - - - - - , - - , - - - - - , - - - - - . - - - , - - - - - , - - , - - - - - , - - - - - . - - - , - - - ,
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0o 10 10 20 20 30 30 40 40 50 50 60 60 70 70 80 80 90 90 100 100 110 110 Power Power (% (% Rated)
Rated)
Power MCPRP Power MCPRp
(%
(% of of rated) rated) Limit Limit 100 100 1.41 1.41 90 90 1.48 1.48 50 SO 1.75 1.7S 50 SO 1.81 1.81 40 40 1.89 1.89 26 26 2.19 2.19 26 26 atat >> 50%F SO%F 2.68 2.68 23 23 at at>> 50%F SO%F 2.80 2.80 26 at 5 50%F 26 at:5 SO%F 2.60 2.60 23 23at < 50%F at:5 SO%F 2.72 2.72 Figure Figure A.26 A.26 BOCBOCto to NEOC NEOC Power-Dependent Power-DependentMCPR MCPR Limits Limits for for -
. GE14 GE14 Fuel Fuel NSS
.NSS Insertion InsertionTimes Times EOC-RPT-OOS EOC-RPT-005 AREVA
.AREVANP NPInc.
Inc.
ANP-2864(NP)
ANP-2864(NP)
Ferry Unit I1 Cycle 9 Browns Ferry " Revision Revision 2
" Reload Reload Safety Analysis Analysis Page A-28 A-28 3.0 . - - - - - , - - , - - - - - - - , - - - - . - - - - - . - - - - - - - , - - , - - - - - - - , - - - - . - - - - - . - - - - - - - ,
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Power MCPRP Power MCPRp
(% of rated)
(% Limit Limit 100 1.44 1.44 90 1.50 1.50 50 1.76 1.76 50 1.83 1.83 40 1.90 1.90 26 2.21 26 at > 50%F50%F 2.57 2.57 at > 50%F 23 at> 2.70 2.70 at < 50%F 26 at::;; 50%F 2.53 2.53 at < 50%F 23 at::;; 50%F 2.65 2.65 Figure A.27 A.27 BOC to EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for ATRIUM-10 ATRIUM-10 Fuel NSS NSS Insertion Times Times EOC-RPT-OOS EOC-RPT -ODS AREVA NP Inc Inc...
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis PageA-29 Page A-29 3.0 .---------.--.----.----.---r__----.--.----.----.--~r__-___,
oO FWCF FWCF o LRNB LRNB a
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Power MCPRP Power MCPRp
(% of rated) Limit Limit 100 1.45 1.45 90 1.52 1.52 50 1.75 1.75 50 1.81 40 1.89 1.89 26 2.19 2.19 26 at > 50%F 50%F 2.68 2.68 23 at>
at > 50%F 50%F 2.80 2.80 26 at S< 50%F 2.60 23 at s< 50%F 2.72 Figure A.28 Figure A.28 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times NSS Times EOC-RPT EOC-RPT-OOS-005 AREVA NP Inc.
AREVA
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 99 Browns Revision 22 Reload Safety Analysis Reload Analysis Page A-30A-30 3.0 , . . - - - - - - - y - - - - r - - - - - - - r - - - - r - - - . - - - - - , - - - - r - - - - - - - r - - - - r - - - , - - - - - - - ,
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Power (% Rated)
Power MCPRp' ,
MCPRp' Power
(% of rated)
(% Limit 100 1.46 90 1.52 1.52 50 --
50 1.83 1.83 40 1.93 1.93 26 2.31 26 at at> 50%F
> 2.69 23 at >> 50%F 2.83 26 at <s 50%F 2.63 23 23 at ~~50%F 2.80 at > 50%F 23 at> 2.94 26 at <s 50%F 50%F 2.70 2.70 23 at <~~
s 50%F 2.85 2.85 Figure A.30 A.30 BOC to FFTRlCoastdownFFTR/Coastdown Power-Dependent MCPR Power-Dependent MCPR Limits for GE14 GEl4 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT-OOS EOC-RPT-OOS AREVA AREVA NP Inc.
(
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page A-32 Page A-32 3.0 o FWCF o LRNB
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~~(% Rated)~~
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(% Limit Limit 100 100 1.47 1.47 90 1.53 1.S3 50 SO 1.78 1.78 50 SO 1.84 1.84 40 1.91 26 2.22 2.22 at > 50%F 26 at> SO%F 2.57 2.S7 23 at >> 50%F SO%F 2.70 26 at S< 50%F SO%F 2.53 2.S3 at < 50%F 23 at:s; SO%F 2.65 2.6S Figure A.31 A.31 BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel TSSS Insertion Times T555 Times EOC-RPT-OOS EOC-RPT-005 AREVA NP Inc.
~~ANP-2864(NP)~~
Browns Ferry Unit 11 Cycle Browns Cycle 99 Revision Revision 22 Reload Safety Analysis Reload Page Page A-33 3.0 o0 FWCF FWCF o0 LRNB LRNB t;. CRWE 2.5
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~~Rated)~~
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(% of rated) rated) Limit Limit 100 100 1.44 1.44 90 1.51 50 1.77 1.77 50 1.82 1.82 40 1.90 1.90 26 2.20 2.20 26 at > 50%F 2.68 2.68 23 at >> 50%F 2.80 2.80 26 at:5 at < 50%F 2.60 2.60*
23 at:<50%F at:5 50%F 2.72 2.72 Figure Figure A.32 A.32 BOCBOC to NEOC NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for GE14 Fuel GE14 TSSS Insertion Times TSSS Insertion Times EOC-RPT-OOS EOC-RPT-OOS AREVA NP AREVA NP Inc.
~~Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-34 A-34 3.0 3.0 0o FWCF FWCF o LRNB LRNB
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o 0 10 20 30 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRP MCPR Power p
(% of rated)
(% Limit Limit 100 1.47 90 1.53 1.S3 50 SO 1.78 1.78 50 SO 1.84 40 1.91 26 2.22 26 at > SO%F 50%F 2.57 2.S7 23 at > SO%F 50%F 2.70 26 at S< SO%F 50%F 2.53 2.S3 23 at 5S 50%F SO%F 2.6S 2.65 Figure A.33 A.33 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 ATRIUM-10 Fuel TSSS Insertion TSSS Insertion Times.
EOC-RPT -OOS EOC-RPT-OOS AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Unit 1 Cycle-9 Browns Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page A-35 3.0 ,-----,----r------.-----,---r-----,----r------.-----,---r------.
3.0 o FWCF o LRNB
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0 10 20 30 30 4-0 40 50 60 70 80 90 100 110 110 Power (%'(% "Rated)
Rated)
Power MCPRp MCPR Power p
(% of rated)
(% Limit Limit 100 100 1.48 1.48 90 1.53 1.53 50 1.77 1.77 50 1.82 1.82 40 1.90 1.90 26 2.20 2.20 26 at >> 50%F 2.68 2.68 23 at > 50%F 2.80 26 26 at5 at <50%F s 50%F .2.60 2.60 23 23 at*
at s 50%F 2.72 2.72 Figure Figure A.34 A.34 BOC BOC to EOCLB EOCLB Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel GE14 TSSS TSSS Insertion Insertion Times Times EOC-RPT-OOS EOC-RPT-005 AREVA AREVA NPNP Inc.
Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Revision Reload Safety Reload Safety Analysis Analysis Page A-36 3.0 r-----.---.----,----r---,-----.---.----,----r---,-----,
o FWCF FWCF oo LRNB LRNB t:. CRWE CRWE 2.5 I
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0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated) rated) Limit Limit 100 1.50 1.50 90 1.55 50 --
50 1.84 40 1.95 26 2.32 26 at > 50%F 2.69 23 at>
at > 50%F 2.83 26 at s 50%F 2.63 23 at ~~50%F 2.80 2.80 23 at > 50%F 2.94 2.94 26 at 5s 50%F 2.70 2.70 23 at~~
~~at > 50%F 2.69 23 at >> 50%F 2.83 26 at <s 50%F 2.63 23 at ~~CRWE 2.5 F-~~~~
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~~(% of rated) Limit 100 1.44 1.44 90 1.50 1.50 50 ---~~
~~50 50 1.81 1.81 40 40 1.96 1.96 26 2.29 2.29 26 at>~~
~~at > 50%F 2.80 23 at >~~
~~23 at > 50%F 50%F 2.94 2.94 26 at:<~~
26 at s 50%F50%F 2.70 2.70 23 at 23 at S< 50%F 50%F 2.85 2.85 Figure A.38 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel NSS Insertion Times Times FHOOS FHOOS AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry-Unit Ferry. Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Analysis Page A-40 A-40 3.0 o FWCF FWCF oo LRNB LRNB
~~" CRWE CRWE 2.5 [-~~
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~~(% of rated)~~
~~(% Limit Limit 100 100 1.46 1.46 90 1.52 1,52 50 --~~
50 1.83 1.83 40 1.93 1.93 26 2.31 at> 50%F 26 at'> 50%F 2.69 2.69 23 at > 50%F 50%F 2.83 2.83 at:::50%F 26 at ~ 50%F 2.63 2.63 23 at <~ 50%F 2.76 2.76 A.39 , BOC to EOCLB Figure A.39 Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 Fuel ATRIUM-10 NSS Times NSS Insertion Times FHOOS FHOOS AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~Browns Ferry Unit 1 Cycle 99* 2*- .~~
~~Revision 2Z Reload Safety Analysis Analysis Page A-41 3.0 3.0 D . FWCF o LRNB t;. CRWE 2.5 2.S~~
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~~Power MCPRp Power MCPRp~~
~~(% of rated) Limit Limit 100 100 1.47 1.47 90 1.52 1.S2 50 SO ---~~
50 SO 1.81 40 1.96 1.96 26 2.29 2.29 26 at > SO%F 50%F 2.80 23 at > SO%F 50%F 2.94 26 at <S SO%F 50%F 2.70 2.70 23 at 50%F 50%F 2.69 50%F 23 at > 50%F 2.83 26 at s< 50%F 2.63 at s<50%F 23 at: 50%F 2.76 Figure A.41 BOC to NEOC Power-Dependent MCPR Limits Power-Dependent Limits for for
~~. ATRIUM-10 Fuel ATRIUM-10 TSSS Insertion T555 Insertion Times Times FH005 FHOOS AREVA NP NP Inc.~~
~~Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-43 A-43 3.0 . - - - - -I. ' - - - -I, - - - , -I - - - - - -I r - - - -I - r - - - ,I - - - - - I- , - - - - - r - - - -
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o 0 10 20 30 40 50 SO 60 70 80 90 100 110 110 Power Power (% (% Rated)
Power MCPRp MCPRp Power
(% of rated) Limit
(% of rated) Limit 100 100 1.47 1.47
,90 ,90 1.52 1.52 50 50 50 50 1.82 1.82 40 1.97 1.97 26 2.30 26 at > 50%F 2.80 23 at >> 50%F 2.94 26 at <~ 50%F 2.70 2.70 23 at <~ 50%F 2.85 Figure A.42 BOC to NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion TSSS Insertion Times Times FHOOS FHOOS AREVA AREVA NP Inc. Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit Unit 11 Cycle 9 Revision Revision 2 Analysis Reload Safety Analysis Page Page A-44 3.0 , . . . . - - - - - - . - - - , - - - - - - - - r - - - , - - - , . . . . . -I- - - - - . - - - , - - - - - - -I - r - - - , - - - , . . . .I. - - - - - ,
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.10 20 30 30 40 50 50 60 70 70 80 90 90 100 110 110 Power (% Rated)
Power Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.50 1.50 90 1.55 1.55 50 50 --
50 1.84 1.84 40 1.95 1.95 26 2.32 2.32 26 at > 50%F 50%F 2.69 2.69 23 23 at > 50%F 50%F 2.83 26 at s< 50%F 2.63 2.63 23 23 atat s< 50%F 2.76 2.76 Figure Figure A.43 A.43 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits Limits for for ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times FHOOS FHOOS AREVA AREVA NP NP Inc.
Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-45 Page 3.0 I I I I I I I I I I o FWCF FWCF o LRNB LRNB A
'" CRWE CRWE 2.5 E
._j o0 00 0_ 2.0 o 0
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Rated)
Power MCPRP MCPRp Power
(% of rated)
(% Limit Limit 100 100 1.49 1.49 90 1.55 1.55 (
50 --- I 50 1.82 1.82 40 1.97 1.97 26 2.30 26 at>
at > 50%F 2.80 2.80 23 at > 50%F 2.94 2.94 26 at ~- 50%F 2.70 2.70 23 at <~ 50%F 2.85 2.85 Figure A.44 BOC EOCLB BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel TSSS TSSS Insertion Times Insertion Times FHOOS FHOOS AREVA AREVA NP Inc.
Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Safety Analysis Analysis Page A-46 A-46 3.0 IIIIII - I _ I I Eo o FWCF FWCF o LRNB LRNB
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Power MCPRP Power MCPRp
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(% Limit Limit 100 100 1.43 1.43 90 1.50 1.S0 50 SO --
50 SO 1.85 1.8S 40 1.90 1.90 26 2.21 26 at > 50%FSO%F 2.57 2.S7 23 at ~t > 50%F SO%F 2.70 26 at at:S<50%F SO%F 2.53 2.S3 23 at S< SO%F 50%F 2.65 2.6S Figure A.45 A.4S BOC to NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Insertion Times PLUOOS PLUOOS AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit Unit 1 Cycle 9 Revision 2 Revision Reload Safety Safety Analysis Analysis Page A-47 A-47 3.0 3.0 o* FWCF o* LRNB A CRWE 2.5 t-
'E
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Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit 100 1.41 90 1.48 1.48 50 ---
50 50 1.84 1.84 40 40 1.89 1.89 26 26 2.19 2.19 26 at > 50%F 2.68 23 at > 50%F 2.80 26 26 at s<
at 50%F 50%F 2.60 2.60 23 at:< 50%F 2.72 23 at s 50%F 2.72 Figure A.46 BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel NSS Insertion NSS Insertion Times Times PLUOOS PLUOOS AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1I Cycle 9 Browns Ferry Revision Revision 2 Reload Reload Safety Safety Analysis Analysis Page A-48 3.0 Oo FWCF o LRNB
~~6 CRWE 2.5 I-~~
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Power Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.44 1.44 90 1.50 1.50 50 --
50 1.86 1.86 40 1.90 1.90 26 2.21 26 at > 50%F 2.57 23 at > 50%F 2.70 at < 50%F 26 at::;; 2.53 _
at < 50%F 23 at::;; 50%F 2.65 Figure A.47 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Times PLUOOS PLUOOS AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
... *Browns Ferry Unit Browns Ferry 9 Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page A-49A-49 3.0 o
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0 10 20 30 30 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRP Power MCPRp
(%
(% of rated) Limit Limit 100 100 1.45 1.45 90 1.51 50 50 ---
50 1.84 1.84 40 1.89 1.89 26 2.19 2.19 26 at >> 50%F 2.68 2.68 23 at >> 50%F 2.80 2.80 26 at <s 50%F 2.60 2.60 23 at ~~. CRWE CRWE 2.5 I-~~
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~~(% of rated)~~
~~(% Limit Limit 100 1.46 90 1.52 1.S2 50 SO --~~
~~50 SO 1.86~~
.1.86 40 1.93 1.93 26 2.31 26 at > 50%F SO%F 2.69 23 at > 50%F SO%F 2.83 26 at S< 50%F SO%F 2.63 23 at S< 50%F SO%F 2.76 2.76 Figure A.49 BOC to FFTRlCoastdownFFTR/Coastdown Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Times PLUOOS PLUOOS AREVA NP Inc.
~~ANP-2864(NP)~~
Browns Ferry' Browns Ferry(Unit 11 Cycle Cycle 99 Revision Revision 22 Reload Safety Analysis Page A-51 3.0 ii I I I I I I I o FWCF o . LRNB 6A, CRWE 2.5 F
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~~Power (% Rated)~~
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~~Power MCPRP Power MCPRp~~
~~(% of rated) Limit Limit 100 100 1.47 1.47 90 1.52 1.52 50 50 ---~~
50 1.84 1.84 40 1.96 1.96 26 2.29 2.29 26 at >> 50%F 2.80 2.80 23 at > 50%F at> 2.94 2.94 26 at 5s 50%F 2.70 2.70 23 23 at s< 50%F 2.85 2.85 Figure Figure A.50 A.SO BOC to FFTR/Coastdown FFTRlCoastdown Power-Dependent MCPR Power-Dependent MCPR Limits for GE14 Fuel NSS NSS Insertion Insertion Times Times PLUOOS PLUOOS U AREVA AREVA NP Inc.
~~Inc .~~
~~..J~~
~~ANP-2864(NP)~~
Browns Ferry Unit Unit 1 Cycle 99 Revision 2 Analysis Reload Safety Analysis Page A-52 Page 3.0 3.0 .--------,---r------r--....,.--.------,---r------r--....,.--.------,
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o 0 10 10 20 30 30 40 50 50 60 70 80 90 100 110 110 Power Power (%(% Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.47 1.47 90 1.53 1.53 50 --
50 1.85 1.85 40 1.91 26 2.22 26 26 at at>> 50%F 2.57 23 at >> 50%F 2.70 26 26 at*
ats 50%F 2.53 23 at*s 50%F 23 at 50%F 2.65 2.65 Figure A.51A.51 BOC to NEOCNEOC Power-Dependent MCPR Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times PLUOOS PLUOOS AREVA AREVA NP NP Inc.
Inc ..
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 . Revision Revision 2 Reload Safety Analysis Analysis Page A-53 3.0 . - - - - - - - , - - - . -IIiIIII
- - - - , - - - - , - - - . - - - - - - - , - - - . - - - - I- , - - - -II, - - - , - - - - - ,
o 0 FWCF FWCF o
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Power (% Rated)
Power MCPRP Power MCPR p
(% of rated) Limit Limit 100 100 1.44 1.44 90 1.51 50 50 --- I 50 1.84 1.84 40 1.90 1.90 26 2.20 2.20 26 at > 50%F 2.68 2.68 23 at > 50%F 2.80 2.80 26 at::;;
at < 50%F 2.60 2.60 at < 50%F 23 at::;; 2.72 2.72 Figure A.52A.52 BOC to NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for GE14 Fuel .
TSSS Insertion TSSS Insertion Times Times PLUOOS PLUOOS AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns FerryFerry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis RE;'lload Analysis Page A-54 A-54 3.0 0 FWCF 0 LRNB Il. CRWE 2.5 2.5
+'
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0o 10 20 30 40 50 60"-
60 70 80 90 100 110 110 Power Power (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.47 1.47 90 1.53 1.53 50 --
50 1.86 1.86 40 1.91 26 2.22 2.22 26 at > 50%F 50%F 2.57 2.57 23 at > 50%F 50%F 2.70 26 at:5 at < 50%F 2.53 23 at at:55 50%F 2.65 Figure A.53 Figure A.53 BOC to EOClB EOCLB Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 TSSS TSSS Insertion Insertion Times Times PLUOOS PlUOOS AREVA NP Inc.
ANP~2864(NP)
ANP-2864(NP)
--Browns Browns Ferry Ferry Unit I1 Cycle 9 Revision Revision 2 Reload Safety Safety Analysis Analysis Page A-55 A-55 3.0 3.0 r - - - - - , - - - . , . - - - - - - , - - - - , - - - - r - - - - - , - - - - r - - - - - , - - - - , - - - - , . - - - - - ,
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Power (% Rated)
Power MCPRp Power MCPRp
(%
(% of rated) Limit Limit 100 100 1.48 1.48 90 1.53 1.53 50 50 ---
50 1.84 1.84 40 1.90 1.90 26 2.20 26 at > 50%F 2.68 2.68 23 at > 50%F 2.80 2.80 26 at <s 50%F 2.60 2.60 23 at <
s 50%F 2.72 2.72 Figure A.54 BOC to EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for GE14 Fuel TSSS Insertion TSSS Insertion Times Times PLUOOS PLUOOS AREVA NP Inc.
AREVA
ANP-2864(NP)
Browns Cycle 99 Browns Ferry Unit 1 Cycle - Revision 2 Revision*2 Analysis Reload Safety Analysis Page A-56 3.0 o0 FWCF FWCF o LRNB LRNB AA CRWE CRWE 2.5 I-E
-j o0 00 C. 2.0 o0 O'f 0L.
0A 0 0
A 1.5 F o A o o A
III I I I II I 1.0 o0 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated) Limit 100 1.50 1.50
. 90 1.55 1.55 50 -----
50 1.86 1.86 40 1.95 1.95 26 2.32 26 at > 50%F 2.69 23 at > 50%F 2.83 26 at <s 50%F 2.63 2.63 23 at ~~50%F 2.80 23 at>~~
at > 50%F 2.94 26 at s< 50%F 2.70 23 at s5 50%F 2.85 Figure Figure A.56 A.56 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel TSSS Times TSSS Insertion Times PLUOOS PLUOOS AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 - . Revision 2 Reload Safety Analysis Analysis Page A-S8 A-58 3.5 3.5 ,.------r---.-----r-----.---.-------r---.-----r-----.---.-----,
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o 0 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 1.46 90 1.S4 1.54 50 SO ---
50 SO 1.83 1.83 40 1.90 26 2.26 26 at at> > SO%F 50%F 3.05 3.0S 23 at > SO%F 50%F 3.28 26 at:
at <50%F s SO%F 2.75 2.7S 23 at 50%F 50%F 3.11 3.11 23 at > 50%F 50%F 3.27 26 at 5~ 50%F 50%F 2.84 23 at ~- 50%F 50%F 3.08 3.08 Figure A.58 A.58 BOC BOC to NEOC Power-Dependent MCPR Limits for Power-Dependent for GE14 GE14 Fuel NSS NSS Insertion Insertion Times Times EOC-RPT-OOS EOC-RPT -OOS and TBVOOS Combined Combined AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 2 Revision 2*
Reload Safety Safety Analysis Analysis Page A-60 A-60 3.5 , - - - - , - - . , - - - - r - - - - , - - - , - - - - , - - . , - - - - r - - - - , - - - , - - - - ,
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~~Power MCPRp Power MCPRp~~
~~(%of rated)~~
~~(% Limit Limit 100 1.48 90 1.54 50 ----~~
50 1.83 1.83 40 1.90 1.90 26 2.26 26 at > 50%F 50%F 3.05 23 at > 50%F 50%F 3.28 at < 50%F 26 at::; 2.75 2.75 at5<50%F 23 at::; 50%F 3.00 A.59 BOC to EOCLB Figure A.59 Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Times EOC-RPT-OOS EOC-RPT-005 and TBVOOS Combined Combined
~~. AREVA NP Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~Browns Ferry Unit 1 Cycle 9 Browns Revision Revision 2 -~~
~~Reload Safety Analysis Analysis Page A-61 3.5 r----.,.----.-------r--...,---r-----.,.----.-------r--...,---r-----,~~
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~~0o 10 20 30 30 40 40 50 60 70 80 90 100 110 110 Power (%~~
~~Power (% Rated)~~
~~Power MCPRp Power MCPRp~~
~~(%of rated)~~
~~(% Limit Limit 100 1.49 1.49 90 1.56 50 ---~~
50 1.81 40 1.92 1.92 26 2.23 26 at > 50%F 3.11 3.11 23 at > 50%F 3.27 26 at5 at <50%F s 50%F 2.84 2.84 23 at <
s 50%F 3.08 Figure Figure A.60 A.GO BOC BOC to EOCLB EOCLB Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel NSS Insertion Times NSS Insertion Times EOC-RPT-OOS EOC-RPT-OOS and TBVOOS TBVOOS Combined Combined AREVA AREVA NP Inc.
~~ANP-2864(NP)~~
~~Brow!1s Ferry Unit 1 Cycle Browns Cycle 9 2- ~~~
Revision 2, Revision Reload Safety Analysis Analysis Page Page A-62 A-62 4:0 4~0 r--~--.---r-----'----.----r-----.---r-----'----.----r-----'
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Power* (% Rated)
Rated)
Power MCPRp MCPRp Power
(% of rated)
(% Limit Limit 100 1.50 1.50 90 1.55 1.55 50 --
50 1.85 1.85 40 1.96 1.96 26 2.35 26 at > 50%F 3.18 3.18 23 at > 50%F 3.40 26 at ~~. CRWE CRWE 3.0~~
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Power (% Rated)
Power MCPRp Power MCPRp
(%
(% of rated) Limit Limit 100 100 1.51 1.S1 90 1.57 1.S7 50 SO --
50 SO 1.83 1.83 40 1.99 1.99 26 2.32 26 at > 50%F SO%F 3.24 23 at > 50%F SO%F 3.40 3.40 at5 26 at S<50%F SO%F 2.97 23 at S< 50%F SO%F 3.26 Figure A.62 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel GE14 NSS NSS Insertion Times Times EOC-RPT-OOS EOC-RPT -OOS and TSVOOS TBVOOS Combined Combined AREVA NP, Inc.
AREVA NP.lnc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Brown§> Revision 2 Reload Analysis Reload Safety Analysis Page A-64 A-64 3.5 Do FWCF FWCF o LRNB 3.0 A CRWE CRWE
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Power (% Rated)
Rated)
Power MCPRP MCPR Power p
(% of rated) Limit Limit 100 1.50 90, 90' 1.57 1.57 50 --
50 1.84 1.84 40 1.91 26 2.27 26 at at>> 50%F 3.05 23 at > 50%F 3.28 26 atS at s 50%F 2.75 23 at s< 50%F 3.00 A.63 BOC to NEOC Figure A.63 Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 Fuel ATRIUM-10 TSSS TSSS Insertion Times Insertion Times EOC-RPT-OOS EOC-RPT -005 and TBVOOS TBVOOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Bro~ns Ferry Unit 1 Cycle 9 Browns R~vision.2 Revision 2 Safety Analysis Reload Safety Analysis Page A-65 A-6S 3.5 , - - - - - , - - , - - - - r - - . . , -IIIIII
- - , - - - - - , - - , - - - - r - - . . , - - - I, - - - .
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Power (% Rated)
Power MCPRp MCPRp Power rated)
(% of rated)
(% Limit Limit 100 1.49 1.49 90 1.SS 1.55 50 SO ---
50 SO 1.82 1.82 40 1.94 1.94 26 2.25 2.2S 50%F 26 at > SO%F 3.11 3.11 at > SO%F 23 at> 50%F 3.27 26 at <S 50%F SO%F 2.84 2.84 23 at
at > 50%F 3.05 23 at >> 50%F 3.28 26 at <S 50%F 2.75 23 at 50%F 3.11*
~~3.11 23 at > 50%F 3.27 3.27.~~
26 at s< 50%F 2.84 23 at s< 50%F 3.08 Figure A.66 BOC to EOCLB EOClB Power-Dependent Power-Dependent MCPR for Limits for GE14 Fuel TSSS TSSS Insertion Times Times EOC-RPT-OOS and TBVOOS*Combined EOC-RPT-OOS TBVOOS Combined AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Ferry Uriit Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page A-68
~~.4.0 IIII- * " I I o0 FWCF FWCF oo LRNB LRNB 3.5 3.S At:. CRWE CRWE 3.0 3.0~~
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0o 10 20 30 40 50 SO 60 70 80 90*
90 100 100 110 110 Power Power (% Rated)
(%Roted)
Power MCPRp Power MCPRp
(% of rated) Limit Limit 100 100 1.53 1.S3 90 1.58 1.S8 50 SO --
50 SO 1.87 1.87 40 1.98 1.98 26 2.37 2.37 26 at > SO%F 50%F 3.18 3.18 23 at > 50%F SO%F 3.40 3.40 26 at S< 50%F SO%F 2.89 2.89 -
at:S_50%F 23 at 50%F 3.15 3.1S Figure A.67 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits Limits for for' ATRIUM-10 ATRIUM-10 Fuel TSSS Insertion Insertion Times Times EOC-RPT-OOS EOC-RPT -OOS and TBVOOSTBVOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety AnalysisAnalysis Page A-69 4.0 o0 FWCF FWCF o LRNB LRNB 3.5 F-A t;. CRWE CRWE 3.0 3.0
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Power MCPRP Power MCPRp
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(% Limit 100 1.53 1.S3 90 1.58 1.S8 50 SO ---
50 SO 1.85 1.8S 40 2.00 26 2.34 2.34 50%F 26 at > SO%F 3.24 3.24 50%F 23 at > SO%F 3.40 3.40 26 at S< 50%F SO%F 2.97 2.97 23 at S< SO%F 50%F 3.26 3.26 Figure A.68 FFTR/Coastdown A.68 BOC to FFTRlCoastdown Power-Dependent MCPR Power-Dependent MCPR Limits for
. GE14 Fuel TSSS Insertion Insertion Times Times EOC-RPT -OOS and TBVOOS EOC-RPT-OOS TBVOOS Combined Combined AREVA AREVA NP Inc. Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Reload Safety Analysis Analysis Page A-70 A-70 3.0 , - - - - - - , - - - r - - - - - , - - . . . - - - - , - - - - - , - - - r - - - - - , - - . . . - - - - , - - - - - ,
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0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
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Power MCPRp Power MCPRp
(% of rated) Limit Limit 100 1.46 90 1.52 1.S2 50 SO --
50 SO 1.83 1.83 40 1.93 1.93 26 2.31 2.31 50%F 26 at > SO%F 2.69 2.69 23 at > SO%F 50%F 2.83 26 at5 <50%F at S SO%F 2.63 23 at S < 50%F SO%F *2.76 2.76 Figure A.69 Figure A.69 BOC BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Insertion TimesTimes EOC-RPT-005 and FHOOS Combined EOC-RPT-OOS AREVA NP Inc.Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1I Cycle 9 , Revision Revision 2 Reload Safety Analysis Analysis Page A-71 Page 3.0 o FWCF o LRNB
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Power MCPRP MCPR Power p
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(% Limit Limit 100 1.44 1.44 90 1.50 1.S0 50 SO ---
50 SO 1.81 40 1.96 1.96 26 2.29 2.29 26 at > 50%F SO%F 2.80 23 at > 50%F SO%F 2.94 at < SO%F 26 ats 50%F 2.70 23 at s< SO%F 50%F 2.85 2.8S Figure Figure A.70 A.70 BOC BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel GE14 NSS Insertion Times NSS Times EOC-RPT -OOS and FHOOS Combined EOC-RPT-OOS AREVA AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 . Revision 2 Reload Safety Analysis Safety Analysis Page A-72 3.0 3.0 o0 FWCF o LRNB I:J. CRWE' CRWE 2.5 1-
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(% of rated) Limit Limit 100 1.46
.90 90 1.52 50 50 ---
50 1.83 40 1.93 26 2.31 26 at > 50%F 2.69 23 at at>> 50%F 2.83 26 at ~< 50%F 2.63 23 at ~< 50%F 2.76 Figure A.71 BOC Figure BOC to EOCLB Power-Dependent MCPR Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 N55 Insertion NSS Insertion Times Times EOC-RPT-OOS EOC-RPT-005 and FH005 FHOOS Combined AREVA NP Inc.
ANP-2864(NP}
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-73 A-73 3.0 , - - - , - - , - - - - - - , -II- - - , - -
I - - , - - - , - - :I - -- - , - - - - - - , - - - - , - - - - , - - - - ,
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o 0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (%
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Power MCPRp Power MCPRp
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(% rated) Limit Limit 100 1.47 1.47 90 1.53 1.53.
50 50 ---
50 1.81 40 1.96 1.96 26 2.29 26 at > 50%F 2.80 23 at>
at > 50%F 2.94 2.94 26 at < 50%F at::; 2.70 2.70 23 at < 50%F at::; 2.85 2.85 Figure A.72A.72 BOCBOC to EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for GE14 Fuel NSS Insertion Times NSS Insertion Times EOC-RPT-005 EOC-RPT-OOS and FHOOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page A-74 Page A-74 3.0 r - - - - - y - - - - , - - - , . - - - r - - - r - - - - - y - - - - , - - - - - , - - - r - - - r - - - - - ,
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50 1.84 SO 1.84 40 40 1.95 1.9S 26 26 2.32 2.32 26 at >.SO%F
>.50%F 2.69 2.69 23 at>
at > SO%F 50%F 2.83 2.83 26 at <
26 at S SO%F50%F 2.63 2.63 23 at 23 at S< 50%F SO%F 2.76 2.76 Figure A.73 BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 Fuel ATRIUM*10 TSSS Insertion Insertion Times Times EOC*RPT EOC-RPT-OOS *OOS and FHOOS Combined Combined
.AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page A-7S Page A-75 3.0 , - - - - , - - - , - - - . . . , - - - - - r - - - , - - - , . . - - - - - , - - - - . - - - - - - r - - - ' - r - - - , . . - - - - ,
o FWCF FWCF o LRNB LRNB A
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0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power Power (% (% Rated)
Power MCPRp MCPR Power p
(% of rated)
(%of Limit Limit 100 100 1.47 1.47 90 1.52 1.S2 SO 50 ---
50 SO 1.82 1.82 40 1.97 1.97 26 2.30 2.30 26 at > SO%F 50%F 2.80 2.80 23 at at> > SO%F 50%F 2.94 26 at at::;< SO%F 50%F 2.70 at::;- SO%F 23 at 50%F 2.8S 2.85 Figure A.74 BOC to NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for GE14 Fuel TSSS Insertion TSSS Insertion Times Times EOC-RPT-OOS EOC-RPT -OOS and FHOOS Combined AREVA NP Inc.
AREVA
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page A-76 3.0 , - - - - , - - - . - - - - , - - - , - - - . - - - - - - , - - - . - - - - , - - - - - , - , - - - . - - - - - ,
oo FWCF FWCF oo LRNB LRNB SA J;. CRWE CRWE 2.5
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Power MCPRp Power MCPR p
(% of rated)
(% Limit Limit 100 1.50 1.S0 90 1.55 1.SS 50 SO --
50 SO 1.84 1.84 40 1.95 1.9S 26 2.32 2.32 26 at > 50%F SO%F 2.69 2.69 23 at > 50%F SO%F 2.83 2.83 26 at S< 50%F SO%F 2.63 2.63 23 at S5 50%F SO%F 2.76 2.76 Figure A.75 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 Fuel ATRIUM-10 TSSS Insertion Times Times EOC-RPT EOC-RPT-OOS -OOS and FHOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page A-77 A-77 3.0 3.0 , - - - - , - - , - - - - - - , - - - - , - - - - , - - - - , - - , - - - - - - , - - - - - , - - - - , - - - ,
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Rated)
Power MCPRp Power MCPRp
(% of rated) Limit Limit 100 1.49 1.49 90 1.55 1.55 50 ---
50 1.82 1.82 40 1.97 1.97 26 2.30 26 at>
at > 50%F 50%F 2.80 23 at > 50%F 2.94 26 at s< 50%F 2.70 23 at s< 50%F 2.85 Figure Figure A.76 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent for I GE14 Fuel TSSS Insertion Times Times EOC-RPT-OOS EOC-RPT -005 and FHOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Reload Safety Analysis Analysis Page A-78 A-78 3.0, r - - - - - , - - , - - - - - - r - - - , - - - - , - - - - - , - - , - - ' - - - - - - - r - - - , - - - - , - - - - - ,
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Rated)
Power MCPRP Power MCPRp
(% of rated)
(% Limit Limit 100 1.43 1.43 90 1.50 1.S0 50 SO ---
50 SO 1.85 1.8S 40 1.90 1.90 26 2.21 26 at > 50%F SO%F 2.57 2.S7 23 at > 50%F SO%F 2.70 26 at5 at S<50%F SO%F 2.53 2.S3 23 at S< SO%F 50%F 2.65 2.6S Figure A.77 A.77 BOC BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Times EOC-RPT-OOS EOC-RPT -005 and PLUOOS PLUOOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Ferry Unit 1 Cycle 9 Browns Ferry Revision 2 Reload Safety Safety Analysis Analysis Page A-79 3.0 , - - - - - r - - - , - - - - - r - - - , - - - , - - - - - - r - - - , - - - - - r - - - , - - - , - - - - - - ,
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Power MCPRP Power MCPR p
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(% of rated) Limit Limit 100 100 1.41 90 1.48 50 ---
50 1.84 40 1.89 26 2.19 2.19 26 at at>> 50%F 2.68 23 at > 50%F 2.80 26 at S< 50%F 2.60 23 at s< 50%F 2.72 A.78 BOC to NEOC Figure A.78 NEOC Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel NSS Insertion NSS Insertion TimesTimes EOC-RPT-OOS EOC-RPT -OOS and PLUOOS PLUOOS Combined Combined AREVA NP Inc.Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Ferry - Revision 2 Revision 2*
Reload Safety Safety Analysis Analysis Page A-80 A-80 3.0 , . - - - - - - - , - - , - - - - - , - - - , - - - , . - - - - - - - , - - , - - - - - , - - - , - - - , . - - - - - - ,
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Power MCPRp Power MCPRp
(% of rated)
(% Limit 100 1.44 90 1.50 50 ---
50 1.86 40 1.90 26 2.21 26 at > 50%F 2.57 23 at > 50%F 2.70 26 at s< 50%F 2.53 23 at s< 50%F 2.65 Figure A.79 A.79 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Times EOC-RPT EOC-RPT-OOS -005 and PLUOOS PLUOOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit Unit 1 Cycle 9 Revision Revision 2 Reload Safety Safety Analysis Analysis Page A-81 3.0 .---__,_--~-___.--.....,_--r__-__,_--~-___.--.....,_--r__-__,
o0 FWCF o LRNB A
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Rated)
Power MCPRp Power MCPR p
(% of rated)
(% Limit Limit 100 100 1.45 1.4S 90 1.52 1.S2 50 SO --- .
50 SO 1.84 1.84 40 1.89 1.89 26 2.19 2.19 26 at > SO%F 50%F 2.68 2.68 23 at > SO%F 50%F 2.80 2.80 26 at <s SO%F 50%F 2.60 2.60 23 at ~~> SO%F 50%F 2.69 23 at >> SO%F 50%F 2.83~~
~~-26 at <S SO%F~~
. *26 50%F 2.63 23 at S< SO%F 50%F 2.76 Figure A.81 A.81 BOC to FFTR/Coastdown FFTRlCoastdown Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 Fuel ATRIUM-10 NSS Insertion Times NSS Insertion Times EOC-RPT-OOS EOC-RPT -005 and PLUOOS Combined Combined AREVA AREVA NP Inc. Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Browns Ferry Unit 1 Cycle Cycle 9 Revision Revision 22 Reload Safety Analysis Reload Analysis Page A-83 3.0 I II I I I I I I I o FWCF o LRNB A
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~~(% Limit Limit 100 100 1.47 1.47 90 90 1.53 1.S3 50 SO ---~~
50 SO 1.84 1.84 40 1.96 1.96 26 2.29 26 26 at > 50%F SO%F 2.80 23 at >> 50%F SO%F 2.94 26 at <S SO%F 50%F 2.70 23 23 at 50%F 2.57 23 at > 50%F 2.70 26 at s< 50%F 2.53 23 at s< 50%F 2.65 Figure A.S3 A.83 BOC to NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times EOC-RPT-005 and PLUOOS EOC-RPT-OOS PLUOOS Combined Combined AREVA NP Inc.
~~AREVA~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit Unit 1 Cycle 9 Revision Revision 2 Reload Reload Safety Analysis Analysis Page'A-8S Page A-85 3.0 , - - - - - - r - - , - - - - - - - , . - - - - r - - - . - - - - - - - - r - - , - - - - - - - , . - - - - r - - - . - - - - - - ,
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~~50 60 60 70 80 90 100 110 110 Power (% (% Rated)~~
~~Rated)~~
~~Power MCPRp Power MCPRp~~
~~(% of rated)~~
~~(% Limit 100 1.44 1044 90 1.51 1.S1 50 SO ---~~
50 SO 1.84 1.84 40 1.90 1.90 26 2.20 26 at > 50%FSO%F 2.68 23 at > SO%F50%F 2.80 26 atat*S 50%F SO%F 2.60 23 atat*S 50%F SO%F 2.72 Figure A.84 BOC Figure BOC to NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for .
~~GE14 Fuel TSSS Insertion TSSS Insertion Times Times EOC-RRT-OOS EOC-RP:T -OOS and PLUOOS Combined Combined~~
/
~~AREVA NP Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Reload Safety Analysis Analysis Page A-86 A-86 3.0 , - - - - - r - - - , . - - - , - - - . - - - - , - - - - - r - - - , . - - - , - - - . - - - - , - - - ,
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o 0 10 20 30 40 50 60 70 80 90 100 110 110 Power (% Rated)
(% Rated)
Power MCPRP Power MCPR p
(% of rated)
(% Limit Limit 100 1.47 1.47 90 1.53 1.S3 50 SO ---
50 SO 1.86 1.86 40 40 1.91 1.91 26 2.22 2.22 26 at > SO%F50%F 2.57 2.S7 23 at > SO%F50%F 2.70 2.70 at < SO%F 26 at:::; 50%F 2.53 2.S3 23 at < SO%F at:::; 50%F 2.65 2.6S Figure A.85 A.a5 BOC BOC to EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for ATRIUM-10 ATRIUM-10 Fuel TSSS Insertion TSSS Insertion Times Times EOC-RPT EOC-RPT-OOS -OOS and PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit 1 Cycle 9 . Revision Revision 2 Reload Analysis Reload Safety Analysis Page A-87 A-87 3.0 3.0 ...-------,--..,----,---....,---.------,--..,----,---....,---.-----,
o FWCF o LRNB
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(% Rated)
Power MCPRP MCPR Power p
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(% of rated) Limit Limit 100 1.48 90 1.53 50 ---
50 1.84 1.84 40 1.90 26 2.20 26 at > 50%F 2.68 23 at > 50%F 2.80 26 at::;;
at < 50%F 2.60 23 at::;;
at < 50%F 2.72 A.86 BOC to EOCLB Figure A.86 Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel GE14 TSSS Insertion Times TSSS Times EOC-RPT-OOS EOC-RPT -005 and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP) .
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Reload Safety Safety Analysis Analysis Page A-88 3.0 o FWCF o LRNB t;. CRWE 2.5
-+-'
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Power MCPRp Power MCPRp
(% of rated)
(% Limit 100 1.S0 1.50 90 1.SS 1.55 50 SO ---
50 SO 1.86 40 1.95 1.9S 26 2.32 at > 50%F 26 at> SO%F 2.69 23 at > 50%F SO%F 2.83 26 at S< SO%F 50%F' 2.63 23 at S< SO%F 50%F 2.76 2.76 Figure A.87 A.87 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel Times TSSS Insertion Times EOC-RPT EOC-RPT-OOS-OOS and PLUOOS PLUOOS Combined Combined '
AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Browns Ferry Unit 11 Cycle Cycle 9 Revision Revision 22 Reload Safety Analysis Reload Analysis Page Page A-89 3.0 o FWCF FWCF o LRNB LRNB "A CRWE CRWE 2.5 E
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(% of rated) rated) Limit Limit 100 100 1.49 1.49 90 1.55 1.55 50 ---
50 1.84
1.84 40 1.97 1.97 26 2.30 2.30 26 at >> 50%F 2.80 2.80 23 at >> 50%F 2.94 2.94 26 at <s 50%F 2.70 2.70 23 23 at 50%F 50%F 3.18 3.18 23 at 23 at >> 50%F 50%F 3.40 3.40 26 26 at: 50%F 3.24 23 at > 50%F 3.40 26 at*s 50%F at 2.97 23 at 50%F 3.18 3.18 23 at > 50%F 3.40 3.40 26 at s< 50%F 2.89 2.89 at:s<50%F 23 at 50%F 3.15 3.15 Figure A.91 BOC Figure SOC to EOCLB EOCLS Power.Dependent Power-Dependent MCPR Limits for for ATRIUM*10 Fuel ATRIUM-10 NSS NSS Insertion Insertion TimesTimes TBVOOS and FHOOS Combined TBVOOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit Browns Unit 1 Cycle 9 Revision -,' .
Revision 2 --
Reload Reload Safety Safety Analysis Analysis Page A-93 Page 4.0 .,------,--,------.----.---y------,---.------.----.---y-----,
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(% Limit 100 1.50 90 1.55 1.55 50 50 ---
50 1.83 1.83 40 1.99 1.99 26 2.32 26 at > 50%F 3.24 3.24 23 at > 50%F 3.40 26 at s< 50%F 2.97 23 at s< 50%F 3.26 .
Figure A.92 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel GE14 NSS Insertion NSS Insertion Times .-
TBVOOS and FHOOS FHOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1I Cycle 9 Browns Revision 2 Reload Safety Analysis Analysis Page A-94 A-94 4.0 ~-----.---r------r---'---r-----.----r------r---'---r------,
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(% Limit Limit 100 1.53 1.53 90 1.58 1.58 50 --
50 1.87 1.87 40 1.98 1.98
, 26 26 2.37 2.37 26 at > 50%F 50%F 3.18 3.18 23 at > 50%F at> 50%F 3.40 3.40 26 at5<50%F at::; 50%F 2.89 2.89 23 at < 50%F at::; 3.15 3.15 Figure A.93 BOG to NEOC A.93 BOC NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-1O ATRIUM-10 Fuel.Fuel TSSS Insertion Insertion Times Times TBVOOS TBVOOS and FHOOS Combined AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns-Ferry Browns-Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Analysis Page A-95 A-95 4.0 r . - - - - - - - , - - - r - - - - - - . - - - , - - - , - - - - - - - , - - - r - - - - - - . - - - , - - - , - - - - - - - ,
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Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 1.50 90 1.55 50 ---
50 1.85 1.85 40 2.00 26 2.34 26 at > 50%F 50%F 3.24 3.24 23 at > 50%F*
50%F 3.40 3.40 26 at 50%F SO%F 3.18 3.18 at > 50%F 23 at> SO%F 3.40 26 at S< 50%F SO%F 2.89 2.89 23 atat5S<50%F SO%F 3.15 3.1S Figure A.95 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-1O Fuel ATRIUM-10 TSSS Insertion Times Times TBVOOS TBVOOS and FHOOS Combined AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Browns Ferry Unit 9 Unit 1 Cycle 9 - Revision 2 Reioad Safety Analysis Reload Page A-97 Page A-97 4.0 IIIIII I I o FWCF FWCF 3.5 oo . LRNB
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50 SO 1.85 1.8S 40 2.00 2.00 26 2.34 2.34 at > SO%F 26 at> 50%F 3.24 23 at > SO%F 50%F 3.40 26 at <S SO%F 50%F 2.97 2.97 23 at S< SO%F 50%F 3.26 Figure A.96 A.96 BOC BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion TSSS Insertion Times Times TBVOOS TBVOOS and FHOOS Combined Combined AREVA AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~-.. Browns Ferry Unit 1 Cycle 9~~
- Browns Revision 22*
Revision Reload Safety Safety Analysis Analysis Page A-98 A-98 3.5 o0 FWCF 0o LRNB 3.0 A 6 CRWE CRWE
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Power MCPRp MCPR Power p rated)
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(% Limit Limit 100 1.46 1.46 90 1.54 1.54 50 . ---
50 1.85 1.85 40 1.90 1.90 26 2.26 26 at > 50%F 50%F 3.05 23 at > 50%F 50%F 3.28 26 at s< 50%F 50%F *2.75 2.75 23 at s< 50%F 50%F 3.00 3.00 Figure A.97 A.97 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS NSS Insertion Times Times TBVOOS TBVOOS and PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit Unit 1 Cycle 9 -- Revision Revision 2 Reload Safety Analysis Analysis Page A-99 A-99 3.5 , - - - - - , - - , - - - - - r - - - , - - - r -IIII 3.S - - - - - , - - , - - - - - r - - - , -I- - r - -I - - - - ,
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Power MCPRp MCPR Power p
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(% Limit 100 1.44 1.44 90 1.51 50 50 ---
50 1.84 1.84 40 1.92 1.92 26 2.23 26 at > 50%F 3.11 3.11 23 at > 50%F 3.27 3.27 26 at s< 50%F 2.84 23at s< 50%F 23,at 3.08 Figure A.98 BOC to NEOC NEOC Power-Dependent MCPR Power-Dependent MCPIR Limits for for GE14 Fuel GE14 NSS Insertion Times Times TBVOOS and PlUOOS TBVOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 . Revision 2 .
Reload Safety Analysis Safety Analysis Page A-100 A-100 3.S 3.5 , - - - - - . , - - - - . - - - - - - . - - - - , - - - , - - - - - . , - - - - . - - - - - - . - - - - , - - - . - - - - - ,
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Power MCPRp Power MCPRp
(% of rated) Limit Limit 100 1.48 1.48 90 1.54 1.54 50 ---
50 1.86 1.86 40 1.90 1.90 26 2.26 26 at > 50%F 3.05 23 at > 50%F 50%F 3.28 3.28 26 at ~< 50%F 2.75 23 at ~< 50%F 3.00 Figure A.99 A.99 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion NSS Insertion Times Times TBVOOS TBVOOS and PLUOOS PLUOOS Combined Combined AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 - Revision 2 Analysis Reload Safety Analysis Page A-101 3.5 oo FWCF FWCF o LRNB 3.0 A CRWE CRWE
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Power MCPRp Power MCPRp
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(% rated) Limit Limit 100 1.49 1.49 90 1.55 1.SS 50 SO ---
50 SO 1.84 1.84 40 1.92 1.92 26 2.23 2.23 26 at > SO%F 50%F 3.11 23 at > SO%F 50%F 3.27 26 at S< 50%F SO%F 2.84 2.84 23 at S< 50%F SO%F 3.08 3.08 A.fOO BOC Figure A.100 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for GE14 Fuel NSS Insertion NSS Insertion Times Times TBVOOS TBVOOS and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
AREVA
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns *. Revision 2 Reload Safety Analysis Reload Analysis . Page A-102 4.0 '--~--.---"------r----.--.----.----'--"------r----.--.----'
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(% of rated) Limit 100 1.50 1.50 90 1.55 1.55 50 ---
50 1.86 1.86 40 1.96 1.96 26 2.35 26 at > 50%F 3.18 3.18 23 at > 50%F 50%F 3.40 3.40 26 at s< 50%F 2.89 at5 23 at s<50%F 50%F 3.15 3.15 Figure Figure A.101 A.101 . BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion Times NSS Insertion Times TBVOOS TBVOOS and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 . Revision 2 Reload Safety Safety Analysis Analysis Page A-103A-103 4.0 o FWCF o LRNB 3.5 3.S 6 CRWE 3.0
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Power MCPRP MCPR Power p
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(% Limit Limit 100 100 1.50 90 1.55 1.55 50 ----
50 1.84 1.84 40 1.99 1.99 26 2.32 26 at > 50%F 3.24 23 at > 50%F 3.40 26 at:s;;
at* 50%F 2.97 23 at < 50%F at:s;; 3.26 Figure Figure A.102A.102 BOC to FFTR/Coastdown FFTRICoastdown Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel NSS Insertion NSS Insertion TimesTimes TBVOOS TBVOOS and PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 2* 2.
Reload Safety Safety Analysis Analysis Page A-104A-104 3.5 II II IIII o FWCF o LRNB LRNB 3.0 A/;. CRWE CRWE
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(% Rated)
Power MCPRP Power MCPRp
(% of rated) rated) Limit Limit 100 100 1.50 1.50 90 1.57 1.57 50 ---
50 1.85 1.85 40 1.91 26 2.27 2.27 26 at > 50%F 3.05 23 at > 50%F 3.28 26 at <s 50%F 2.75.
23 at SO%F50%F 3.1.1 23 at > SO%F50%F 3.27 at:S<50%F 26 at SO%F 2.84 23 at S< 50%F SO%F 3.08 3.08 Figure Figure A.104 BOC to NEOC NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Insertion Times Times TBVOOS TBVOOS and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
~~AREVA Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~Browns Ferry Unit 1 Cycle 9 Revision 2~~
.Reload Analysis Reload Safety Analysis Page A-106 Page 3.5 3.5 I II I I o0 FWCF FWCF
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50 1.86 1.86 40 1.91 26 2.27 2.27 26 at > 50%F 3.05 23 at > 50%F 3.28 26 at s< 50%F 2.75 23 at s< 50%F 3.00 Figure A.105 A.105 BOC to EOClB EOCLB Power-Dependent Power-Dependent MCPR limits Limits for ATRIUM-10 Fuel ATRIUM-10 Insertion Times TSSS Insertion Times TBVOOS and PlUOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit Unit 1 Cycle 99 Revision 2 Analysis Reload Safety Analysis Page Page A-107 3.5 3.5 , - - - - , - - . . , - - - - , - - - - , - - - , - - - - , - - . . , - - - - , - - - - , - - - , - - - - ,
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~~90. 100 .110~~
.110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(%
(% of rated) Limit Limit 100 100 1.52 1.52 90 1.57 1.57 50 ---
50 1.84 1.84 40 40 1.94 1.94 26 2.25 2.25 26 at > 50%F 3.11 3.11 23 at > 50%F 3.27 3.27 26 at <s 50%F 50%F 2.84 2.84 23 at > 50%F 3.18 3.18 23 at > 50%F 3.40 3.40 26 at s< 50%F 50%F 2.89 at:S<50%F 23 at 50%F 3.15 3.15 A.107 Figure A.1 07 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 Fuel ATRIUM-10 TSSS Insertion Insertion Times Times TBVOOS TBVOOS and PLUOOS Combined PLUOOS Combined AREVA NP Inc.
~~AREVA~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page Page A-109 4.0 o FWCF FWCF 3.5 o LRNB 3.S A
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Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 1.52 1.S2 90 1.58 1.S8 50 SO ---
50 SO 1.85 1.8S 40 2.00 26 2.34 26 at > 50%F SO%F 3.24 23 at > 50%F 23 SO%F 3.40 26 at S< 50%F SO%F 2.97 23'at SO%F 23 at S< 50%F 3.26 Figure Figure A.108 BOC to FFTRICoastdown FFTR/Coastdown Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel Times TSSS Insertion Times TBVOOS TBVOOS and PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Ferry Unit 1 Cycle 9 Revision-2 Revision 2.__
Reload Reload Safety Analysis Analysis Page A-110 Page A-1 10 3.0 ,----r-'---.------,-----.---,----r--.------,-----.---.-----,
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Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 1.46 90 1.52 50 ---
50 1.85 1.85 40 1.93 26 2.31 26 at > 50%F 50%F 2.69 23 at>
at > 50%F 50%F 2.83 26 at s< 50%F 50%F 2.63 23 at s< 50%F 50%F 2.76 Figure A.109 A.109 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion Times NSS Times FHOOS FHOOS and PLUOOS Combined PLUOOS Combined AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns . Revision Revision 2 Reload Safety Analysis Reload Analysis Page A-111 A-111 3.0 3.0 , . . - - - - . , - - - , - - - - - , - - - - , - - - y - - - - - . , - - - , - - - - - , - - - - , - - - y - - - - - - ,
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Power MCPRP MCPR Power p
(% of rated)
(% Limit Limit 100 1.44 1.44 90 1.50 1.50 50 ---
50 1.84 1.84 40 1.96 26 2.29 26 at > 50%F 50%F 2.80 23 at > 50%F 50%F 2.94 26 at s< 50%F 50%F 2.70 23 at S< 50%F 50%F 2.85 2.85 Figure A.110 A.110 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel Insertion Times NSS Insertion Times FHOOS and and PLUOOS PLUOOS Combined AREVA AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Browns Ferry Unit Unit 1 I Cycle 99 Revision 2 Reload Safety Analysis Page A-1 A-112 12 3.0 3.0 o
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50 1.86 1.86 40 1.93 1.93 26 2.31 26 at >'50%F
>"50%F 2.69 23 at > 50%F 2.83 at::;<50%F 26 at5 50%F 2.63 23 at < 50%F at::; 2.76 2.76 A.111 BOC to EOCLB Figure A.111 EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion NSS Insertion Times Times FHOOS and PLUOOS Combined Combined AREVA NP Inc.
AREVA
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Reload Safety Safety Analysis Analysis Page A-113 A-1 13 3.0 ,----,-----,---....-----,----,---,-------,---....-----,---.....,---,-------,
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(% of rated) Limit Limit 100 100 1.47 1.47 90 1.52 1.S2 50 SO ---
50 SO 1.84 40 1.96 1.96 26 2.29 26 at>
at > SO%F 50%F 2.80 23 at > 50%F SO%F 2.94 26 at S< SO%F 50%F 2.70 23 at S< SO%F 50%F 2.85 2.8S Figure A.112 BOC to EOCLB Figure Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel NSS Insertion Times NSS Times FHOOS and PLUOOS PLUOOS Combined AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Unit Unit 1 Cycle 9 Revision 22 Analysis Reload Safety Analysis Page Page A-114 A-1 14 3.0 3.0 . . . - - - - - - , - - - - , - - - - , - - , - - - - , - - - - , - - - - , - - - - , - - , - - - - , - - - - - ,
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Power MCPRp Power MCPRp
(% of rated) Limit Limit 100 100 1.50 1.50 90 1.55 1.55 50 ---
50 1.85 1.85 40 1.95 1.95 26 2.32 2.32 26 at > 50%F 2.69 2.69 23 at >>50%F 50%F 2.83 2.83 26 at at!S< 50%F 2.63 2.63 23 23 at at!S< 50%F 2.76 2.76 Figure A.113 Figure A.113 BOC BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for ATRIUM-1O ATRIUM*10 Fuel TSSS Insertion Insertion Times Times FHOOS and PLUOOS and PLUOOS Combined Combined AREVA AREVA NP NP Inc.
Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Revision Reload Safety Analysis Reload Analysis Page A-115 A-115 3.0 3.0 ....-----,----,------,.---,---,.-----,---...,..-----,.---,---,.-----,
I I I I I I I I I I
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o 0 10 20 30 40 50 60 70 80 90 100 110 110 Power Power (%(% Rated)
Power MCPRP Power MCPRp
(% of rated)
(% Limit Limit 100 1.47 1.47 90 1.52 1.52 50 ---
50 1.84 1.84 40 1.97 1.97 26 2.30 26 at>
at > 50%F 2.80 23 23 at at >> 50%F 50%F 2.94 26 at5 at s<50%F 50%F 2.70 23 at:5 at < 50%F 2.85 Figure A.114 BOC to NEOC Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel TSSS Insertion Times Times FHOOS and PLUOOSPLUOOS Combined Combined AREVA NP Inc. Inc.
ANP-2864(NP)
ANP-2864(NP)
*Browns Ferry Unit Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Page A-1 16 A-116 3.0 o FWCF o LRNB LRNB A
A CRWE CRWE 2.5 k
+'
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0... 2.0 F 0:::
CL 0
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III I I I I I I I 1.0 0o 10, 10 20 30 30 40 50 60 70 80 90 100 110 110 Power Power (% Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.50 1.50 90 1.55 1.55 50 ---
50 1.86 1.86 40 1.95 1.95 26 2.32 2.32 26 at > 50%F 2.69 23 at > 50%F 2.83 26 at <s 50%F 2.63 2.63 23 at S< 50%F 2.76 Figure A.115 A.11S BOC to EOCLB EOClB Power-Dependent Power-Dependent MCPR MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Times Insertion Times FHOOS and PlUOOS Combined PLUOOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Reload Safety Analysis Analysis Page A-117 Page A-1 17 3.0 3.0 .-----~--.,..___-___,_---.----,...__'-~--.,..___-___,_--_._--r__-_.
I I I I I II I I I o0 FWCF FWCF o0 LRNB "A CRWE CRWE 2.5 k
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1.0 0o 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRP Power MCPR p
(% of rated)
(% Limit 100 1.49 1.49 90 1.55 1.55 50 50 ---
50 1.84 1.84 40 40 1.97 1.97 26 2.30 2.30 26 at > 50%F 2.80 2.80 23 at >> 50%F 2.94 26 at s< 50%F 50%F 2.70 23 at ~~50%F 3.18 3.18 23 at at>> 50%F 50%F 3.40 3.40 26 at s< 50%F 2.89 2.89 23 at:~~
at s<50%F 50%F 3.15 3.15 Figure A.117 BOC to NEOC NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT -005, TBVOOS, and FHOOS Combined Combined AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-119 A-1 19 4.0 , - - - - , - - . . , - - - - , - - - - , - - - , - - - - , - - . . , - - - -I , - - - -
IIIIII I
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o 0 10 20 30 40 50 60 70 80
~~80. 90 100 100 110 110 Power (% (% Rated)~~
Rated)
Power MCPR -
Power MCPRp
(% of rated) Limit 100 1.47 1.47 90 1.53 1.53 50 ---
50 50 1.83 1.83 40 40 1.99 1.99 26 2.32 26 2.32 50%F 26 at > 50%F 3*.24 2.24 23 at > 50%F 50%F 3.40 26 at:< 50%F 26 at s 50%F 2.97 2.97 23 at 23 at:< 50%F S 50%F 3.26 3.26 Figure A.118 BOC to NEOC Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel NSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -005, TBVOOS, TBVOOS, and FHOOS FHOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Browns Ferry Unit 1I Cycle Cycle 9 Revision 2 Revision Reload Safety Analysis Page A-120 4.0 , - - - - - r - - - , . - - - - , - - - - , - - - , - - - - - r - - - , . - - - - , - - - - , - - - , - - - - ,
oO3 . FWCF FWCF 3.5 3.5 o LRNB
'" CRWE CRWE 3.0
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AA 1.5 1.0 i i i i i o0 10 20 30 30 40 50 60 70 BO 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.50 1.50 90 1.55 1.55 50 --
50 1.85 1.85 40 1.96 1.96 26 2.35 2.35 26 at>
at > 50%F 50%F 3.18 3.18 23 at > 50%F 50%F 3.40 26 at ~ < 50%F 2.89 2.89 23 at at5~<50%F 50%F 3.15 3.15 Figure A.119 A.119 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS N55 Insertion Times Insertion Times EOC-RPT-OOS, EOC-RPT-005, TBV005, TBVOOS, and FHOOS Combined FH005 Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 I Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-121 4.0 4.0 o
O] FWCF FWCF o LRNB LRNB 3.5 3.5
&J;. CRWE CRWE 3.0 3.0
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l...-_---1..._ _-'--_---L_ _-1...._ _.L...-_---1...
~~_-'--_---L_ _-1...._ _.L...-_---I I~~
o0 10 10 20 30 40 50 60 60 70 80 90 100 '110 110 Power (%
Power (% Rated)
Rated) .
Power MCPRp Power MCPRp
(% of rated) Limit Limit I
100 100 1.51 90 1.57 1.57 50 ---
50 1.83 1.83 40 1.99 26 2.32 26 at > 50%F 3.24 23 at>
at > 50%F 3.40 atS~ 50%F 26 at 2.97 23 at ~< 50%F 3.26 Figure A.120 BOC to EOCLB Power-Dependent MCPR.Limits Power-Dependent MCPR Limits for for GE14 Fuel NSS Insertion Insertion Times Times EOC-RPT -005, EOC-RPT-OOS, TBVOOS, and FHOOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 -
Analysis Reload Safety Analysis Page A-122 4.0 o FWCF FWCF
. 3.5 o LRNB 3.5
'"& CRWE 3.0
-+J
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0
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0 1.5
'" 9 g I I I II I I 1.0 ' - - _ - . 1 -_ _-'--_---'-_ _--'-_ _' - - _ - . 1 -_ _-'--_---'-_ _--'-_ _'--_...;....1 o
0 10 20 30 30 40 50 60 60 70 80 90 100 110 110 Power (%(% Rated)
Rated)
Power MCPRP Power MCPR p
(% of rated) Limit Limit 100 100 1.53 1.S3 90 1.58 1.S8 50 SO ---
50 SO 1.87 1.87 40 1.98 1.98 26 2.37 26 at>
at > SO%F 50%F 3.18 3.18 50%F 23 at > SO%F 3.40 26 at S< SO%F 50%F 2.89 at5S<50%F 23 at SO%F 3.15 3.1S Figure A.121A.121 BOC BOC to NEOC NEOC Power-Dependent Power*Dependent MCPR Limits for ATRIUM-10 .Fuel ATRIUM*10.Fuel Insertion Times TSSS Insertion Times EOC-RPT-OOS, EOC*RPT *OOS, TBVOOS, TBVOOS, and FHOOS Combined Combined
. AREVA AREVA NP Inc.
ANP-2864(NP)
Unit-1 Cycle 9 Browns Ferry Unit--1 Revision 2 Revision Reload Safety Safety Analysis Analysis Page A-123 A-123 4.0 r------,---.------,-----r---,-------,---.------,-----r---,-----,
oO3 FWCF
~.5 3.5 o LRNB LRNB A, CRWE 3.0
~~EEJ~~
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Power MCPRp MCPR Power p
(% of rated)
(% Limit Limit 100 1.50 1.S0 90 1.55 1.SS 50 SO ---
50 SO 1.85 1.8S 40 2.00 26 2.34 2.34 26 at > SO%F 50%F 3.24 23 at>
at > SO%F 50%F 3.40 26 at S< SO%F 50%F 2.97 23 at S< SO%F 50%F 3.26 Figure A.122 A.122 BOC to NEOC Power-Dependent Power-Dependent MCPR Limits for for .
GE14 Fuel TSSS Insertion TSSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and FHOOS Combined Combined AREVA AREVA NP Inc.
ANP-2864(NP)
Browns-Ferry Unit 1 Cycle
Browns.Ferry Cycle 9 Revision Revision 22 Reload Safety Analysis Reload Analysis ,Page Page A-124 4.0 I III o0 FWCF 3.5 o0 LRNB 3.S A CRWE 3.0
'EE
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0 10 20 30 30 40 SO 50 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 1.53 90 90 1.58 1.58 50 --
50 1.87 1.87 40 1.98 1.98 26 2.37 26 at>
at > 50%F 3.18 3.18 23 at > 50%F 3.40 26 at <s 50%F 50%F 2.89 23 at5 at <50%F s 50%F 3.15 3.15 Figure A.123 A.123 BOCBOC to EOCLB EOClB Power-Dependent MCPR Power-Dependent MCPR Limits for for ATRIUM-10 Fuel ATRIUM-10 Insertion Times TSSS Insertion Times EOC-RPT-OOS, EOC-RPT-005, TBVOOS, and FHOOS TBVOOS, and FHOOS CombinedCombined AREVA AREVA NP Inc.Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page A-125 A-12S 4.0 ,-----,----y------.---,---,-----,----y------.---,---,-----.
0 D FWCF FWCF 3.5 o LRNB A
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0 10 20 20 30 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRP Power MCPRp
(% of rated)
(% Limit Limit 100 1.53 1.S3 90 1.S8 1.58 50 SO ---
50 SO 1.85 1.8S 40 2.00 26 2.34 26 at > SO%F 50%F 3.24 at > SO%F 23 at> 50%F 3.40 26 at S< SO%F 50%F 2.97 2.97 23 at S< SO%F 50%F 3.26 Figure A.124 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel Insertion Times TSSS Insertion Times EOC-RPT-OOS, TBVOOS, EOC-RPT -OOS, TBVOOS, and FHOOS Combined Combined AREVA NP Inc.
AREVA
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit Unit 11 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page A-126 3.5 ,....---,----r------r---.---..-----,---...,..-----r---.---..-----,
o FWCF FWCF o LRNB LRNB 3.0 1-3.0 A CRWE CRWE
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0 10 20 30 30 40 50 60 . 70 80 90
.90 100 110 110 Power (% (% Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.46 1.46 90 1.54 1.54 50 ---
50 1.85 1.85 40 1.90 1.90 26 2.26 26 at >> 50%F 3.05 3.05 23 at > 50%F 3.28 26 at <s 50%F
26 2.75 23 at 50%F 3.11 3.11 23 at > 50%F 50%F 3.27 26 at s5 50%F 50%F 2.84 23 at s- 50%F 50%F 3.08 A.126 BOC to NEOC Figure A.126 Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times NSS Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOeS, TBVOOS, and PLUOOS PLUeOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Page A-128 A-128 3.5 , - - - - , - - - . - - - - - - r - - - , -
II
--,.-----.- II
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0 10 20 30 40 50 0 6 .60 5 0 70 80 90 100 100 110 110 Power (%(% Rated)
Rated)
Power MCPRP Power MCPRp
(% of rated)
(% Limit 100 1.48 1.48 90 1.54 50 ---
50 -1.86
'1.86 40 1.90 1.90 26 2.26 26 at > 50%F 3.05 23 at 236at > 50%F 50%F 3.28 26 at ~< 50%F 2.75 23 at ~< 50%F 3.00 A.127 BOC to EOCLB Figure A.127 Power-Dependent MCPR Limits for Power.Dependent for
, ATRIUM-10 ATRIUM*10 Fuel NSS NSS Insertion Times Times EOC-RPT-OOS, EOC*RPT*OOS, TBVOOS, and PLUOOS CombinedCombined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Safety Analysis Reload Analysis Page A-129
~~3.5 3.5 . - - - - , - - - , - - - - - - r - - - ' - r - - - . - - - - - , - - - , - - - - - - r - - - , - - - . - - - - - - ,~~
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Rated)
Power MCPRp Power MCPRp
(%of rated)
(% Limit Limit 100 1.49 1.49 90 1.56 1.56 50 ---
50 1.84 40 1.92 1.92 26 2.23 26 at>
at > 50%F 3.11 3.11 at > 50%F 23 at> 50%F 3.27 26 at s< 50%F 2.84 23 at S< 50%F 3.08 3.08 Figure A.128A.128 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel NSS Insertion Times NSS Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and PLUOOS PLUOOS Combined AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-130 Page A-130 4.0 o0 FWCF FWCF o0 LRNB 3.5 3.5 A CRWE CRWE 3.0 3.0
-:L,
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0 10 20 30 30 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(%of rated) Limit Limit 100 1.50 1.50 90 1.55 1.55 50 ---
50 1.86 1.86 40 1.96 1.96 26 2.35 26 at > 50%F 3.18 3.18 23 at > 50%F 3.40 26 at at5<50%F s 50%F 2.89 23 at at5<50%F s 50%F 3.15 3.15 FFTR/Coastdown Figure A.129 BOC to FFTRlCoastdown Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and and PLUOOS Combined Combined AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 I Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page Page A-131 4.0 r-----r---..,.__-~--_,_--,__-__.--..,.__-~--_,_--,__-__.
o0 FWCF FWCF o LRNB LRNB 3.5 l>. CRWE CRWE 3.0 3.0
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90 100 100 110 110
. Power Power (%(% Rated)
Rated)
Power MCPRP Power MCPRp
(% of rated)
(% Limit 100 1.51 1.S1 90 1.57 1.S7 50 SO ---
50 SO 1.84 1.84 40 1.99 26 2.32 26 at >> SO%F 50%F 3.24 23 at >> SO%F 50%F 3.40 26 at < SO%F at:5 50%F 2.97 23 at < SO%F at:5 50%F 3.26 Figure A.130 A.130 BOC BOC to FFTR/Coastdown FFTRlCoastdown Power-Dependent MCPR Power-Dependent MCPR Limits for for GE14 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT -005, TBVOOS, EOC-RPT-OOS, TBVOOS, and PLUOOS Combined Combined AREVA NP Inc. Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Safety Analysis Reload Analysis Page A-132 A-132 3.5 r-----r--....-----.---r---,-----r---....-----.---r---,-----,
o O FWCF FWCF o LRNB 3.0 A CRWE
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III I I I I I II 1.0 0o 10 20 30 40 . 50 60 70 60 90 100 110 110 Power (%(% Rated)
Rated)
Power MCPRP Power MCPRp
(% of rated)
(% Limit Limit 100 1.50 1.S0 90 1.57 1.S7 50 SO ---
50 SO 1.85 1.8S 40 1.91 26 2.27 26 at > 50%F SO%F 3.05 3.0S 23 at > 50%F SO%F 3.28 3.28 at* SO%F 26 ats 50%F 2.75 2.7S at5 23 at s<50%F SO%F 3.00 Figure A.131 BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 Fuel ATRIUM-10 TSSS Insertion Times Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns-Ferry Browns-Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-133
.3.5 3.5 oD FWCF FWCF o LRNB LRNB 3.0 ý- & CRWE
-+-'
2.5 F
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0 10 20 30 30 40 50 60 60 70 80 90 100 100 110 110 Power (% Rated)
(% Rated)
Power MCPRp Power MCPRp
(% of rated) rated) Limit Limit 100 1.49 1.49 90 1.55 1.55 50 50 ---
50 1.84 1.84 40 1.94 1.94 26 2.25 2.25 at > 50%F 26 at> 3.11 3.11 at > 50%F 23 at> 3.27 26 at s< 50%F 2.84 2.84 23 at s< 50%F 3.08 3.08 Figure A.132 A.132 BOCBOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel Insertion Times TSSS Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and PLUOOS Combined Combined AREVA NP.lnc.
AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Reload Safety Analysis Analysis Page A-134 Page 3.5 3.5 ....-----,.--,.--.......------,-----.---r-----,.--.......------.,.---,---r-----,
II , III o1 o FWCF FWCF o LRNB LRNB 3.0 1- A CRWE CRWE o+J 2.5 F-
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Rated)
Power MCPRP Power MCPRp
(% of rated) Limit Limit 100 1.51 90 1.57 1.57 50 ---
50 1.86 1.86 40 1.91 26 2.27 26 at > 50%F 3.05 23 at > 50%F 3.28 3.28 26 at <s 50%F 50%F 2.75 2.75 23 at SO%F 26 at> 50%F 3.11 3.11 50%F 23 at > SO%F 3.27 3.27 at*S SO%F 26 at 50%F 2.84 2.84 23 at S< 50%F SO%F 3.08 Figure A.134 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for GEt4 Fuel GEI4 TSSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and PLUOOS Combined Combined AREVA NP Inc.
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Reload Analysis . Page A-136 4.0 . - - - - - - - r - - - , - - - - - , - - - . . - - - y - - - - - - r - - - , - - - - - , - - - . . - - - y - - - - - ,
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0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (%
Power Rated)
(% Rated)
Power MCPRp MCPRp Power
(% of rated) Limit Limit
(% of rated) 100 100 1.53 1.53 90 90 1.58 1.58 50 ---
50 ---
50 50 1.87 1.87 40 1.98 1.98 26 2.37 2.37 26 at > 50%F 3.18 3.18 23 at>
at > 50%F 3.40 26 at:;;
at < 50%F 2.89 23 at:;;
at < 50%F 3.15 3.15 Figure A.135 BOC BOC to FFTR/Coastdown FFTRlCoastdown Power-Dependent Power-Dependent MCPR Limits for .
ATRIUM-10 Fuel ATRIUM-10 TSSS Insertion Times Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, and PLUOOS PLUOOS CombinedCombined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Analysis Reload Safety Analysis Page Page A-137 4.0 . , - - - - - , - - - , - - - - - - r - - - - , - - - - . - - - - - - - , - - - , - - - - ' - - T - - - - , - - - - . - - - - - - ,
o1 o FWCF FWCF o LRNB LRNB 3.5 A
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0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated) rated)* Limit Limit 100 100 1.53 1.53 90 1.58 1.58 50 ----
50 1.85 1.85 40 2.00 2.00 26 2.34 2.34 26 at 26*at 50%F
> 3.24 23 at >> 50%F 3.40 26 at < 50%F at;S; 2.97 2.97 23 at at > 50%F SO%F 2.69 23 at > 50%FSO%F 2.83 at < SO%F 26 at:s; 50%F 2.63 at < SO%F 23 at:s; 50%F 2.76 Figure A.137 A.137 BOC to NEOC .,
Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 ATRIUM-10 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, FHOOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page A-139 A-139 3.0 , - - - - - , - - - , - - - - - , - - - - r - - - . - - - - - - - , - - - , - - - - - , - - - - r - - - . - - - - - - ,
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~~o0 10 20 30 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)~~
~~Rated)~~
~~Power MCPRp MCPR Power p~~
~~(% of rated) rated) Limit Limit 100 1.44 1.44 90 1.50 1.50 50 ---~~
50 1.84 1.84 40 1.96 1.96 26 2.29 2.29 26 at > 50%F 2.80 23 at > 50%F 2.94 2.94 26 at at*s 50%F 2.70 2.70 23 at s< 50%F 50%F 2.85 2.85 Figure A.138 BOC to NEOC Figure Power-Dependent Power-Dependent MCPR MCPR Limits for GE14 Fuel NSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT *005, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
~~AREVA Inc.~~
~~ANP-2864(NP)~~
Ferry-Unit Browns Ferry Unit 1 Cycle 99 Revision 2 Reload Safety Analysis Page A-140 3.0 , - - - - r - - , - - - - - - - - r 3.0 I - - - - rI- - - , - - - - - r - - , - - - - : - - - - - r - - - - r - - - , - - - - ' - ,
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III I I I I I I I 1.0 o0 10 20 30 40 50 60 70 80 90. 100 100 110 110 Power (% (% Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 "100 1.46 1.46 90 1.52 1.52 50 ---
50 1.86 1.86 40 40 1.93 1.93 26 26 2.31 2.31 26 at > 50%F 50%F 2.69 2.69 23 at > 50%F 50%F 2.83 2.83 at < 50%F 26 at:s; 2.63 2.63 23 at:s; at5<50%F 50%F 2.76 2.76 Figure A.139A.139 BOC to to EOCLB EOCLB Power-Dependent Power.Dependent MCPR MCPR Limits Limits for for ATRIUM-10 ATRIUM*10 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT-OOS, FHOOS, EOC*RPT*005, FHOOS, and PLUOOS and PLUOOS Combined Combined AREVA AREVA NP NP Inc.
ANP-2864(NP)
ANP-2864(NP) .
Browns Ferry Unit Browns Unit. 1 Cycle 9 Revision 2, 2,
Reload Analysis Reload Safety Analysis Page Page A-141 3.0 o
I FWCF FWCF o LRNB 6A CRWE 2.5 -
E
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1.5 I- 0 I I I I I I0 1.0 ' - _ - - L . ._ _...L...-_----1._ _--L-_ _I - _ - - L . ._ _...L...-_----1._ _--L-_ _I - _ - - - l o0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (%(% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 1.47 1.47 90 1.53 1.S3 50 SO ---
50 SO 1.84 1.84 40 1.96 26 2.29 2& at 50%F 26&,at > SO%F 2.80 23 at > 50%F SO%F 2.94 26 at s< 50%F SO%F 2.70 2.70 23 at s< 50%F SO%F 2.85 2.8S Figure A.140 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel NSS Insertion Times NSS Times EOC-RPT-OOS, EOC-RPT -OOS, FHOOS, and PLUOOS Combined Combined NP Inc.
AREVA NPlnc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 -Revision Revision 2 Reload Safety Analysis Analysis Page A-142 A-142*
3.0 3.0 o FWCF FWCF o
0 LRNB LRNB A
I:>. CRWE CRWE 2.5 I-EE
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o0 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit 100 1.50 90 1.55 50 ---
50 1.85 1.85 40 1.95 1.95 26 2.32 26 at > 50%F 2.69 23 at > 50%F 2.83 26 at ~< 50%F 2.63 23 at ~< 50%F 2.76 Figure A.141 BOC to NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel TSSS Insertion Times TSSS Times EOC-RPT-OOS, EOC-RPT -OOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision*2 Revision 2 Reload Safety Analysis Analysis Page A-143 A-143 3.0 3.0 0o FWCF FWCF oo LRNB LRNB
&6 CRWE CRWE 2.5 1-
E
-t E
.....J 0o 0 '0
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~~a. 2.0 F o b7 0::: 00 a..~~
o
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1.5 F 0 0 III I I I I I I I 1.0 '--_--'-_ _....I..-_----'-_ _--L-_ _L - _ - - ' -_ _....I..-_----'-_ _--L-_ _L-_~
o0 10 10 20 30 30 40 50 60 70 80 80 90 100 110 110 Power (% (% Rated)
Power MCPRP Power MCPRp
(% of rated)
(% rated) Limit Limit 100 100 1.47 1.47 90 1.52 1.52 50 ---
50 1.84 1.84 40 1.97 1.97 26 2.30 2.30 26 at >> 50%F 2.80 23 at > 50%F 2.94 26 at <s 50%F 2.70 23 at ~~SO%F50%F 2.69~~
~~.2.69 23 at>at > SO%F.~~
50%F 2.83 2.83 26 at <S SO%F 50%F 2.63 2.63 23 23.at at S< SO%F 50%F 2.76 2.76 Figure A.143 BOC to EOCLB Power.Dependent Power-Dependent MCPR Limits for ATRIUM-10 ATRIUM*10 Fuel TSSS TSSS Insertion Insertion Times Times EOC-RPT-OOS, EOC*RPT *005, FHOOS,FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
~~AREVA~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Analysis Page A-145 3.0 o FWCF o LRNB r,. CRWE 2.5 2.5
~~+-'~~
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~~o 0 10 10 20 30 30 40 50 60 70 80 90 100 110 110 Power Power (% (% Rated)~~
~~Rated)~~
~~Power MCPRP Power MCPRp~~
(%
~~(% of rated) Limit Limit 100 100 1.49 1.49 90 1.55 1.55 50 ---~~
~~50 1.84 1.84 40 1.97 1.97 26 2.30 2.30 26 at > 50%F 2.80 23 at > 50%F 2.94 26 at at:s;~~
< 50%F 2.70 23 at < 50%F at:s; 2.85 Figure A.144 BOC to EOCLB Figure EOCLB Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel TSSS TSSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, FHOOS, and PLUOOS Combined PLUOOS Combined AREVA NP inc.Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
~~Browns*Ferry Unit 1 Cycle 9~~
. Browns-Ferry Revision 2 Revision Reload Safety Reload Safety Analysis Analysis Page A-146 A-146 4.0 r - - - - , - - - . , . - - - , - -
II
~~- - r - - - ,I - - - - ,~~
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~~oo] FWCF 3.5 3.5 o LRNB AA CRWE 3.0~~
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0 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRP MCPRp Power
(%of rated)
(% Limit Limit 100 1.49 1.49 90 1.55 1.55 50 ---
50 1.85 1.85 40 1.96 1.96 26 2.35 26 at>at > 50%F 3:18 3:18 23 at > 50%F 3.40 26 at s< 50%F 2.89 23 at*at S 50%F 3.15 3.15 Figure A.145A.14S BOC BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion NSS Times Insertion Times TBVOOS, FHOOS, and PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Analysis Reload Safety Analysis Page A-147 A-147 4.0 4.0 , - . . . , - - - - - , - - . . , - - - - - - r - - - - . - - - , - - - - - , - - . . , - - - - - - r - - - - , - - - , - - - ,
o FWCF 3.5 3.S o LRNB A CRWE 3.0
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o 0 10 20 30 30 40 50 SO 60 70 80 90 100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRp Power MCPR p
(%
(% of rated) Limit Limit 100 100 1.47 1.47 90 1.53 1.53 50 ---
50 50 1.84 1.84 40 40 1.99 1.99 26 2.32 2.32 26 at>
at > 50%F 3.24 23 at > 50%F 3.40 3.40 26 at <s 50%F 2.97 2.97 23 23 at 50%F 3.18 3.18 23 at > 50%F 3.40 26 at s< 50%F 2.89 23 at at*s 50%F 3.15 3.15 Figure A.147 BOC to EOCLB Figure EOCLB Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined Combined AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Browns Ferry Ferry Unit 1 Cycle 9 Revision 2 Revision Reload Safety Analysis Analysis Page A-149 4.0 ,----,---.,...-----,.---,---,....---,---.,...-----,.---,---,....----,
~~o0 FWCF 3.5 o LRNB I!. CRWE 3.0~~
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~~I I~~
~~_L...-_--'~~
~~o 0 10 20 30 40 50 50 60 70 80 90 100 110 110~~
~~.- Power Power (% (% Rated)~~
~~Power MCPRp Power MCPRp~~
~~(% of rated) Limit Limit 100 1.50 90 1.55 1.55 50 ---~~
50 1.84 1.84 40 1.99 1.99 26 2.32 26 at > 50%F 3.24 23 at > 50%F 3.40 26 at ~< 50%F 2.97 23 at ~- 50%F 3.26 Figure Figure A.148 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent
~~. GE14 Fuel Insertion-Times NSS Insertion*Times TBVOOS, FHOOS, and PLUOOS Combined PLUOOS Combined~~
~~. AREVA NP Inc.~~
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety AnalysisAnalysis Page A-1S0 A-150 4.0 , - - - - - , - - , - - - - - - - , - - - - , - - - , - - - - - , - - , - - - - - - - , - - - - , - - - , - - - - - ,
oO FWCF 3.5 3.5 o LRNB A*
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o0 10 20 30 .40
~~40 50 60 70 . 80 80 90 100 100 110 110 Power (% (% Rated)~~
Rated)
Power MCPRp Power MCPRp
(% of rated) Limit Limit 100 1.53 1.53 90 1.58 1.S8 50 SO ---
50 SO 1.87 1.87 40 40 1.98 1.98 26 26 2.37 2.37 26 at > 50%F 3.18 26 at > SO%F 3.18 23 at 23 at >> SO%F 50%F 3.40 3.40 26 at S< 50%F SO%F 2.89 23 at at*S 50%FSO%F 3.15 3.15 Figure A.149 A.149 BOCBOC to NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for ATRIUM-10 ATRIUM-10 Fuel Insertion Times TSSS Insertion Times TBVOOS, TBVOOS, FHOOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
AREVA Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 . - Revision 2 Revision Analysis Reload Safety Analysis Page A-151 4~0 4:.0 o FWCF FWCF o LRNB LRNB 3.5 3.5 A
I:. CRWE CRWE 3.0 3.0
-+-'
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~
o 00 0
2.0 2.0 0 A 0 1.5 1.S o
1.0 '--_--'-_ _---'---_---'-_ _--'-_ _-'--_--'-_ _---'---_---'-_ _--'-_ _-'--_---'
o0 10 20 30 40 50 SO 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated) rated) Limit Limit 100 100 1.50 1.50 90 1.55 1.55 50 ---
50 1.85 1.85 40 2.00 2.00 26 2.34 2.34 26 at >> 50%F 3.24 23 at >> 50%F 3.40 26 at::;
at < 50%F 2.97 2.97 23 at::;
at < 50%F 3.26 Figure A.1S0 Figure A.150 BOC to NEOCNEOC Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel Insertion Times TSSS Insertion Times TBVOOS, TBVOOS, FHOOS,FHOOS, and PLUOOS Combined Combined AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 22 Analysis Reload Safety Analysis Page A-1S2 A- 152 4.0 . - - - - , - - - , - - - - - r - - , . - - - , - - - , - - - , - - - - - r - - , . - - - , - - - - - ,
4.0 o FWCF FWCF o LRNB 3.5 A
fj. CRWE CRWE 3.0 3.0
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I I I I 1.0 1.0 '--_--L._-,---'--_---'-_ _'--_--L. _--'-_ _l....-_-'
o 0 10 20 30 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.53 1.S3 90 1.58 1.S8 50 SO ---
50 SO 1.87 1.87 40 1.98 1.98 26 2.37 2.37 26 at at>> SO%F 50%F 3.18 3.18 23 at at>> SO%F 50%F 3.40 26 at <S SO%F 50%F 2.89 2.89 23 23 at:
at <50%F S SO%F 3.15 3.1S Figure Figure A.151 A.1S1 BOC BOC to EOCLB EOCLB Power-Dependent MCPR Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times TBVOOS, TBVOOS, FHOOS,FHOOS, and PLUOOS PLUOOS CombinedCombined AREVA AREVA NP NP Inc.
Inc.
ANP-2864(NP)
Browns Ferry Unit 1 Cycle Browns Cycle 9 Revision Revision 22 Reload Safety Analysis Reload Analysis Page Page A-153 A- 153 4.0 oE FWCF FWCF o LRNB 3.5 J;. CRWE CRWE 3.0
-<.J
'E
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1.5 I I I I I I I I I I 1.0 '--_---'-_ _-'--_---'-_ _--'-_ _'--_---'-_ _-'--_---'-_ _--'-_ _'--_---'
o0 10 20 30 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPR p
(% of rated) rated) Limit Limit 100 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.85 1.85 40 2.00 26 2.34 2.34 26 at > 50%F 3.24 3.24 23 at > 50%F 3.40 3.40 26 at s< 50%F 2.97 2.97 I' 23 at 5s 50%F 3.26 3.26 Figure Figure A.152 A.1S2 BOC to EOCLBEOCLB Power-Dependent Power-Dependent MCPR MCPR Limits Limits for GE14 Fuel GE14 TSSS Insertion Times TSSS Insertion Times TBVOOS, FHOOS, and TBVOOS, FHOOS, and PLUOOS Combined PLUOOS Combined AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1* 1-Cycle 9 Revision 2 Reload Safety Safety Analysis Analysis Page A-154 A-154 4.0 I t t I I I oo FWCF FWCF o LRNB LRNB 3.5 AA CRWE CRWE 3.0 E
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o 0 10 20 30 40 50 6070 60 70 -80
~~80 90 100 110 110 Power Power (% Rated)~~
Power MCPRp Power MCPRp
(%
(% of rated) Limit Limit 100 100 1.49 1.49 90 1.55 1.55 50 ---
50 1.85 1.85 40 1.96 1.96 26 2.35 26 at > 50%F 3.18 3.18 23 at at>> 50%F 3.40 26 at S< 50%F 2.89 23 at5 at s<50%F 50%F 3.15 3.15 Figure A.153 Figure A.1S3 BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, FHOOS,* FHOOS, and PLUOOS Combined Combined NP Inc.
AREVA NPlnc.
ANP-2864(NP)
Browns Ferry Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Safety Analysis Analysis Page A-1SS A- 155 4.0 , - - - , - - - , . - - -.1-I r - - - , - - - , - - - , - - - , . - - - - r - - - , - - - , - - - ,
o FWCF o LRNB LRN8 3.5 r:. CRWE 3.0
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Rated)
Power MCPRP Power MCPRp rated)
(% of rated) Limit Limit 100 1.47 1.47 90 1.53 1.S3 50 SO ---
50 SO 1.84 1.84 40 40 1.99 1.99 26 2.32 2.32 26 at > SO%F 50%F 3.24 3.24 23 at 23 at >> SO%F 50%F 3.40 3.40 26 at 26 at S< SO%F 50%F 2.97 2.97 23 at 23 at S< 50%F SO%F 3.26 3.26 Figure A.154 A.154 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for GE14 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, FHOOS,FHOOS, and PLUOOS PLUOOS Combined AREVA AREVA NP Inc. Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns FerryFerry Unit 1 Cycle 9 ..- Revision 2 Reload Safety Analysis Analysis Page A-156 A-156 4.0 o: FWCF FWCF o LRNB
.LRNB 3.5 I:. CRWE CRWE 3.0
EE
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1.5 o 0I:. 6 o 9 1.0 '--_---'-_----'-'--_----1.
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o 0 10 20 30 30 40 50 60 70 70 80
80. 90 100 100 110 110 Power (% Rated)*
(% Rated)
Power MCPRP Power MCPRp
(% of rated) rated) Limit Limit 100 100 1.50 1.50 90 1.55 1.55 50 ---
50 1.86 1.86 40 1.96 1.96 26 2.35 2.35 26 at > 50%F 3.18 3.18 23 at > 50%F 3.40 26 at 50%F SO%F 3.24 3.24 23 at > 50%F SO%F 3.40 3.40 at*S 50%F 26 at SO%F 2.97 23 at S<50%F 3.26 Figure A.1S6 A.156 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel GE14 Insertion Times NSS Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
~~ANP-2864(NP)~~
~~ANP-2864(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-158 A-1S8 4.0 no FWCF FWCF oo LRNB LRNB 3.5 3.5 A* CRWE CRWE 3.0 3.0
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o 8A'
~~1.5 i i i i i i i 1.0 ~_--'- _ _...L.-_---l._ _- ' -_ _L..-_--'-_ _. . . L . - _ - - - l . - - - , - _ - ' -_ _L..-_--'~~
o0 10 20 30 40 50 60 60 70 80 90 100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(%of Limit Limit 100 100 1.53 1.S3 90 1.58 1.S8 50 SO 50 SO 1.87 1.87 40 1.98 1.98 26 2.37 2.37 26 at >> SO%F 50%F 3.18 3.18 23 at > 50%F
> SO%F 3.40 3.40 26 at <S SO%F 50%F 2.89 2.89 23 at5 at <50%F S SO%F 3.15 3.1S Figure Figure A.157 A.157 BOC to NEOC NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for ATRIUM-10 ATRIUM-10 Fuel TSSS Insertion TSSS Insertion Times Times EOC-RPT-005, TBVOOS, EOC-RPT-OOS, TBVOOS, FHOOS, PLUOOS Combined and PLUOOS Combined AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry UnitUnit 1 Cycle 9 Revision 2 Revision Reload Reload Safety Analysis Analysis Page A-159 4.0 , - - - , - - , . - - - , - - - , - - - - r - - - , - - , . - - - , - - - , - - - - r - - - - ,
o FWCF 3.5 o LRNB I:> CRWE 3.0 EE
--.J 0_ 2.5 Q.
~
of n..
0~
u
~
2.0 1.5 1.0 0o 10 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp MCPR Power
(% of rated). Limit p Limit
(% of rated) .
100 100 1.50 1.50 90 90 1.55 1.55 50--
50 ---
50 50 1.85 1.85 40 2.00 26 2.34 26 at > 50%F 50%F 3.24 23 at > 50%F 50%F 3.40 26 at s< 50%F 2.97 at*s 50%F 23 at 50%F 3.26 Figure A.158 A.158 BOCBOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel TSSS Insertion Times TSSS Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-160 4.0 . - - - - - - - , - - , . - - - - - - - r - - - - , - - - - , - r - - - - - - ' r - - , . - - - - - - - r - - - - , - - - r - - - - - ,
o O FWCF FWCF o LRNB LRNB 3.5 3.S A
~~b. CRWE CRWE 3.0~~
'EE
....J 0.. 2.S 2.5 a:::
n..
u
2:
0 0 2.0 2.0 0 A
1.5 1.S o A
,1.0 11.0 ~_--'- _ III_..l....-_----1._ _--'--_ I I I I I I
_' - - - _ - - - ' -_ _..l....-_----L_ _--'--_ _' - - - _ - - - '
I o0 10 20 30 40 50 SO 60 60 70 80 90 100 100 110 110 Power (% Rated)
Power Rated)
Power MCPRP Power MCPRp
(% of rated)
(% rated) Limit Limit 100 1.S3 1.53 90 1.58 1.S8 SO 50 ---
50 SO 1.87 1.87 40 1.98 1.98 26 2.37 2.37 26 at > 50%F SP%F 3.18 3.18 23 at > 50%F SO%F 3.40 at < 50%F 26 ats SO%F 2.89 2.89 23 atat*s 50%F SO%F 3.15 3.1S Figure A.159 BOC BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR MCPR Limits for ATRIUM-10 Fuel Insertion Times TSSS Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, FHOOS, FHOOS, and PLUOOS Combined Combined AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit Unit, 1 Cycle 9 --- Revision 22 Reload Safety Analysis Analysis Page A-161 A4.0 04.0 0 FWCF 3.5 0 LRNB A CRWE 3.0 3.0
'E
-t
~~.::J 0.. 2.5 0:::~~
0..
0~
0:2
~
o 0 2.0 0 1.5 1.0 L . . . - _ - - , - I -_ _-'--_---L_ _- ' -_ _'--_.-...l..._ _-'--_---L_ _--'-_ _' - - _ - - '
0o 10 10 20 30 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% rated) Limit Limit 100 100 1.53 1.S3 90 1.58 1.S8 50 SO ---
50 SO 1.85 1.8S 40 2.00 26 2.34 26 at >> SO%F 50%F 3.24 23 at at>> SO%F 50%F 3.40 at:S<50%F 26 at SO%F 2.97 23 at ats< SO%F 50%F 3.26 Figure A.160 BOC to EOCLB Power-Dependent Power-Dep~ndent MCPR Limits forfor GE14 Fuel TSSS TSSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, FHOOS, and PLUOOS Combined AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Safety Analysis Reload Analysis Page A-162 Page 1.4 1.4 r - - - - , - - . . . - - - - - , - - - - - - . - - - - , - - - - - - , - - . . . , - - - - , - - - - - - . - - - - , - - - - - - ,
oO FWCF o LRNB LRNB 1.2
-i-J
'E
~~t 1.0 0~~
....J 00 0 0..
C-)
U l.L 0 n:: 0 0 0
(.)
r
.8
.8 0 8 0
....J e o 0
.6 0
.4
.4 ~_~ _ _ _~__~_ _~____L -_ _~_ _~_ _~_ _~_ _ _L-_~
o0 10 20 30 40 50 60 70 70 80 90 100 100 110 110 Power (% Rated) Rated)
Power LHGRFACP Pow~r LHGRFAC p
(% of rated) rated) Multiplier Multiplier 100 1.00 77.6 0.82 26 0.62 26 at > 50%F 0.52 26 at > 50%F 0.52 23 23 at >
at > 50%F 50%F 0.50 0.50 26 26 at:<
at s 50%F 50%F 0.55 0.55 23 23 at s< 50%F at 50%F 0.54 0.54 Figure A.161 All Exposures Exposures Power-Dependent Power-Dependent LHGR Multipliers Multipliers for for ATRIUM-10 ATRIUM-10 Fuel NSSITSSS Insertion Times NSSITSSS Times EOOS with TBV In-Service In-Service AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision 2 Reload Safety Analysis Analysis Page A-163 A-163 1.5 ,------,---.------r---,-----,r----,---..-----r--.....-----.--....,
I I II Io n Required LHGRFAC LHGRF AC I 1.25 1.25
+-'
1.0
E
--.J
-j a.
ca.
o I I 3
3 U
0 .75 LL o3 13 0L 0::
C-'
r:
--.J
-j
.5
.25
.0
.0 ~_~ __ ~_~ __ ~_~ _ _- L_ _ ~_~ _ _~_~_ _ _~
o0 10 20 30 40 50 . 60 70 80 90 100 100 110 110 Power (%
(% Rated)
Rated)
Power LHGRFACp LHGRFAC p
(% of rated) rated) Multiplier Multiplier 100 1.00 77.6 0.79 26 0.57 26 at > 50%F 0.46 23 at > 50%F 0.42 26 at <
at:5 50%F 0.51 23 at*
at:5 50%F 0.50 Figure A.162 A.162 All Exposures Exposures Power-Dependent LHGR Multipliers Power-Dependent for Multipliers for GE14 Fuel NSSITSSS Insertion Times NSSITSSS Insertion Times EOOS with TBV In-Service In-Service AREVA NP Inc.
AREVA
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Revision Revision 2 Reload Safety Analysis Page A-164 1.4 1.4 , - - - - - - - r - - - , - - - , - - - - - , - - - - , - - - - r - - - - - - r - - - - - r - - - - , - - - - , - - - - - - ,
o FWCF o LRNB 1.2 E 1.0 1.0 0 0
-.J l 0 0 D-oC_
LL 0:::
() .8
.8 0
r:
-J
-l o 0
.6
.4 0o 10 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power LHGRFACpp LHGRFAC
(%
(% of rated) Multiplier Multiplier 100 0.88 26 0.60 26 at > 50%F 50%F 0.43 23 at > 50%F 0.41 26 at*
at::s; 50%F 0.51 23 at :5 50%F at::s; 0.47 0.47 Figure A.163 All All Exposures Exposures Power-Dependent Power-Dependent LHGR Multipliers LHGR Multipliers for ATRIUM-10 ATRIUM-10 Fuel NSSITSSS Insertion NSSrtSSS Insertion Times Times EOOS with TBVOOS TBVOOS AREVA AREVA NP Inc.
ANP-2864(NP)
ANP-2864(NP)
Browns Ferry Unit 1 Cycle 9 Browns Revision 2 Reload Safety Analysis Analysis Page A-165 1.5 r - - - - , - - - , - - - - - - r - - , . . , - - - - , -i - - r - -I- , - - - -I - - , - - -
i
- , - - -i - - - - r -
i
[]
o Required Required LHGRFAC LHGRF AC I 1.25 1.0
+'
'E2 0
--.J c-0...
UC.)
U- .75 0
<<LL_
l1..
0 0 0::: 0 0
I3-I
--.J
.5
.25
.25
".0
.0 L...-_--'-_I I _-'---_----'-_
I _-I" - _ - - 'I_ _-'--_ I I
_.L...-_--'-_ I I
_-'--_----I. I_ _--'
1 0o 10 20 30 40 50 60 60 70 70 . 80 80 90 90 100 100 110 110 Power (%
Power (% Rated)
Rated)
Power LHGRFACP Power LHGRFAC p
(% of rated) Multiplier Multiplier 100 100 0.97 77.6 0.77 26 0.54 26 at > 50%F50%F 0.37 23 at > 50%F 0.31 26 at s< 50%F 50%F .0.47
0.47 at*s 50%F 23 at 50%F 0.44 Figure A.164 All All Exposures Exposures Power-Dependent LHGR Power-Dependent LHGR Multipliers Multipliers for GE14 Fuel GE14 NSS/TSSS NSSITSSS Insertion Times Times EOOS with TBVOOS TBVOOS AREVA NP Inc.
~~AREVA~~

ML093140265

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