Text

ANP-2863(NP), Rev. 0, Browns Ferry Unit 1 Cycle 9 Reload Safety Analysis for 105% Oltp.
	ML093350653
Person / Time
Site:	Browns Ferry
Issue date:	11/30/2009
From:	; AREVA NP
To:	; Office of Nuclear Reactor Regulation
References
	ANP-2863(NP), Rev 0
	Download: ML093350653 (300)
	v • d • e

ATTACHMENT ATTACHMENT 13 (105% OLTP)

Browns Ferry Nuclear Plant (BFN)

I Unit 1 Technical Specifications Specifications (TS) Change 467-S Revision Revision of Technical Technical Specifications Specifications to allow utilization utilization of AREVA AREVA NP NP fuel and associated associated analysis methodologies methodologies Reload Safety Reload Safety Analysis Report Attached is the non proprietary proprietary version of the Reload Safety Analysis.report Analysis report for 105%

105%

OL TP conditions.

OLTP

ANP-2863(NP)

, , Revision 0 I; "

Browns Ferry Unit 1 Cycle 9 ,

'J I Reload Safety Analysis for 105% OL Reload OLTPTP A November 2009 '

November A.R"EVA

AREVA NP Inc.

ANP-2863(NP)

Revision 00 Revision Browns Ferry Unit 1 Cycle 9 Reload Safety Safety Analysis for 105%

105% OLTP OLTP

\ .

. I*'

AREVA NP Inc.

ANP-2863(NP)

AN P-2863(NP)

Browns Ferry Unit 1I Cycle 9 Browns Revision 0

. Revision Reload Safety Analysis Reload OLTP Analysis for 105% OL TP i Page i' Natur~ of Changes Nature Changes Item Page Description and Justification

1. All This is the initial release. .

.,'i NP Inc.

AREVA NPlnc.

ANP-2863(NP)

Browns Ferry Unit Browns Unit 1I Cycle Cycle 9 Revision 0

. Revision O' Analysis for Reload Safety Analysis Reload 05% OLTP for*1105% OLTP Page ii Page ii Contents Contents 1.0 Introduction .........................................................................................................

Introduction ............................................ ......

..,..........1-1 2.0 D isposition of Events Disposition Events.........

......... :..................................... ....................................................... 2-1 3.0 MMechanical Design A echanical Design Analysis I........................ ~ ..............................

nalysis ................................... .................... :........... 3-1 4.0 Thermal-Hydraulic Therm al-Hydraulic Design Design Analysis ..................................... ............................ ;.......... ~.4-1

..................................... ,........................................ 4-1 4.1 Thermal-Hydraulic Design Thermal-Hydraulic Design and and Compatibility Compatibility ........................

.................................................... .4-1 4-1 4.2 Safety Lim it M Safety Limit MCPR ..... ~ ......... ~ ..................... :............................. :, .......... 4-1 CPR Analysis ...............................................................................

4.3 Core Hydrodynamic Stability Core Hydrodynamic ........................ ,......... ,.... :......................................4-2 Stability ................................... 4-2 5.0 Anticipated O Anticipated perational Occurrences Operational ........................................................................... ~ ..... 5-1 Occurrences .......................................................................

5.1 S T ransients .............................................................................................

ystem Transients System ................................., ............................................................ 5-1 5.1.1 Load Load Rejection Rejection No Bypass (LRNB) (LRNB) ............... I........................... 5-3 5.1.2 Turbine ..........................

Turbine Trip No Bypass (TTNB) ........................................................... 5-3 5.1.3 Feedwater Feedwater Controller Controller Failure Failure (FWCF) .................................................

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

, : 5.1.4 Loss of Feedwater Loss Feedwater Heating Heating ............... :.................................................. 5-5 5.1.5 Control Rod Withdrawal Control Withdrawal Error ..............................................................

......................................................... 5-5 I, 5.2 Slow-Flow Slow Flow Runup Analysis .................................

Analysis ................................................... :............................: ....:5-6 5-6

J. '

5.3 Out-of-Service Scenarios Equipment Out-of-Service Scenarios ......................... ,............................ :..........5-7

.................................. 5-7 5.3.1 TBVOOS ..................................................................................

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

EOC-RPT-OOS .................................................................................... 5-8

,.5-:-8*

5 .3 .3 . FHOOS 5.3.3 FHO OS ..................................................................................................

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

. 5.3.4 P LU O O S .......................................................................

PLUOOS . ................................................. ,....................... 5-9 5.3.5 Combined Combined EOC-RPT-OOS EOC-RPT-OOS and TBVOOS TBVOOS ............................................

........................................ 5-9 I

I I

5.3.6

5.3.6 Combined Combined EOC-RPT-OOS EOC-RPT-OOS and FHOOS .........................................

.............................................. ,.... 5-9 5-9

I I

5.3.7 Combined Combined EOC-RPT-OOS EOC-RPT-OOS and PLUOOS .......................... ..........................................

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

.......................................... 5-9 5.3.9 . Combined

5.3.9 Combined TBVOOS TBVOOS and PLUOOS PLUOOS ....................................................

.................................................... 5-10 5-10

I

( t 5.3.10 5.3: 10' Combined FHOOS FHOOS and PLUOOS PLUOOS ......................................................

...................................................... 5-10 5-1 0 5.3.11 Combined EOC-RPT-OOS, EOC-RPT-OOS, TBVOOS, and FHOOS FHOOS .....................

.... 5-10 5-10 5,3.12' Combined EOC~RPT-OOS, 5.3.12 Combined EOC-RPT-OOS, TBVOOS, and PLUOOS ........................ 5-10 PLUOOS ........................ 5-10

, ' 5:3.13 Combined Combined EOC~RPT-OOS,EOC-RPT-OOS, FHOOS, arid and PLUOOS .......................... 5-10 PLUOOS .......................... 5-10 5.3.14 . Combined Combined TBVOOS, FHOOS, and PLUOOS ..... ...... :................................

,........................... 5-11 t

I, i

5.3.15 Combined Combined EOC-RPT-OOS,EOC-RPT-OOS, TBVOOS, FHOOS, and P LU OO S ...........................................................

PLUOOS ~ ...................... *... *..... ,.5-11

............................................................................................ 5-11 5.3.16 Single-Loop O peration .......................................................................

5.3.16 Single-Loop Operation .................................. ;.~ ........................... ,...... 5:-11 5-1l 5.4 Licensing PowerPow er Shape ..........................

.......................................................... 5-1 5-122 6.0 Accidents ........

Postulated Accidents Postulated ................................................ ..........................................

...... :................................. :......... /.: ........................................ ........ 6-1 6:

6.11 . Loss-of-Coolant-Accident ............ .........................

Loss-of-Coolant-Accident (LOCA) ...................................................................... 6-1 6.2 6.2 Drop Accident (CRDA) ........................

. Control Rod DropAccident ..............................:.... : .. :..................... :............ 6-2 6.3 Fuel and Fuel and Equipment Handling Accident ........ ..............................................................

....... , ................................: ........... 6-3 6.4 Fuel.Loading Fuel Loading Error (Infrequent (Infrequent Event) ......................... ~ ...................... ;............... 6-3 6.4.1. . Mislocated Fuel 6.4.1 M islocated Fuel Bundle .................. ~ ..................................................... 6-3 6.4.2 M isoriented 6.4.2' Misoriented Fuel Bundle ...................................................................

................................................ ,................. :: ... 6-3 7.0 7.0* Special An:alyses Special* ; .......................... ~ ... *..:...... *..... :: .................. :....... :............................. ~ ....... 7-1.

A nalyses .................................................................................................... 7-1 Overpressurization Analysis ......

7.1 ' ASME Overpressurization ...................................................................

,..................... ~ .......... ;....................... ,.. ~ .. 7-1 NP Inc.

AREVA NPlnc.'

. AREVA

ANP-2863(NP)

. Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% OL OLTP TP Page iiiiii 7.2 ATWS ATW S Event Evaluation ....................................................................................

.................................................................................... : 7-2 7-2 7.2.1 ATWS Overpressurization ........................

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

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

.......................................................................... 7-4 7-4 7 .4 7.4 F uel Criticality Fuel C riticality ..................................................................................... ................ 7-4

..................................................................................................... 7-4 8.0 Operating Limits andCOLR and COLR Input Input ..................................................................................

..................................... 8-1 8 .1 8.1 MC P R Lim MCPR Limitsits ......................................................................................................

...................................................................................................... 8-1 8.2 8 .2 LHGR Limits LH G R Lim its ........................................................................................................

........................................................ .............................................. 8-1 8.3 MAPLHGR MAPLHGR Limits ...................................................................................

....................................... :............ .... 8-2 8-2 9.0 9 .0 References .....................................................................................................................9-1 Refe re nces .....................................................................................................................

Appendix A Operating Operating Limits and Results Comparisons Comparisons ...................... ;............................. A-1 Tables Tables 1.1 EOD EO D and EOOSEOOS Operating O perating Conditions ..........................................................................

.......................................................................... 1-2 2.1 Disposition of Events Summary Summary for Browns Ferry Unit 1 ..............................................

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

.................. 2-13

.4.1 Fuel- and Plant-Related Fuel- Uncertainties for Safety Limit MCPR Analyses ........................

Plant-Related Uncertainties 4-4

............ ;......... .4-4 4.2 Summary for Safety Results Summary ....................................................... ;... 4-5 Safety Limit MCPR Analyses ...................................................

44.3

.3 OPRM O P R M Setpoints ................................................................................;............................ 4-6 S etpoints ............................................................................................................ 4-6 4.4 Endpoints for Browns Ferry Unit 1 Cycle 9 ...........................................................

BSP Endpoints ......................................................... 4-7

.4-7 5.1 Exposure Basis for Browns

. Exposure Browns Ferry Unit 1 Cycle 9 Transient Transient Analysis. .......................... 5-13 Analysis ........................... 5-13

\

' 5.2 Scram Speed Insertion Tim Times ...................................... 5-14 es .....................................................................................

............................................ 5-14 5.3 NEOC Base Case LRNB Transient .......................................... ...................... 5-15 Transient Results .................................................................. 5-15 5.4 EOCLB Base Case LRNB Transient Results Results ........................................

............................ :...................... 5-16 5-16 5.5 NEOC Base Case FWCF Transient Results ............................ ;................................... 5-17

................................................................ 5-17 5.6 ..............................................................

EOCLB Base Case FWCF Transient Results .............................................................. 5-18 5-18

i 5.7 Feedwater Heating Transient Analysis Results ...............................................

Loss of Feedwater ............................................... 5-19 5-19 5.8 Control Rod Withdrawal Withdrawal Error ~CPR ACPR Results ...............................................................

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

Operability Requirements........ ............................................... ;......... 5-21 5.10 Flow-Dependent MCPR Flow-Dependent ............................................................................~~ .....5-22 MCPR Results ............................................................................. 5-22 5.11 Licensing Basis Core Average Axial Power Profile ........................

Profile ........ ;....... ;.................................... 5-23 7.1 ASME Overpressurization ......................... I......................................

Overpressurization Analysis Results ........................................................... 7-5

~ ....... 7-5 7.2 Overpressurization Analysis Results .........

ATWS Overpressurization ;.......................... ~ ... ~ ....... ,....... ;.: ....... 7-6

............................................... 7-6 AREVA NP Inc; AREVA Inc.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Browns Revision 0 Revision Reload Reload Safety Analysis for 105% OL OLTPTP Page iv Pageiv 7.3 [ .........

] .....*................. ;.7-7 7-7 8.1 MCPRp Limits for NSS Insertion MCPRp .................................................. 8-3 Insertion Times BOC to NEOC ..................................................

8.2 MCPRp Limits for TSSS Insertion MCPRp Insertion Times BOC to NEOC ................................................

................................................ 8 8-7 8.3 MCPRp Limits for NSS Insertion MCPRp Insertion Times BOC to EOCLB .........................................

......................... ~ .... 8-11 8-11 8.4 MCPRp Limits for TSSS Insertion Times BOC to EOCLB MCPRp EOCLB ............................................

.................... 8-15 8-15 8.5 MCPRp Limits for NSS Insertion MCPRp Insertion Times BOC to FFTR/Coastdown FFTRlCoastdown ..............................

.............................. 8-19 8-19 8.6 MCPRp Limits for TSSS Insertion Times BOC to FFTR/Coastdown MCPRp FFTRlCoastdown ............................

............................ 8-22 8.7 Flow-Dependent MCPR Limits ATRIUM-10 Flow-Dependent ATRIUM-10 and GEI4 GE14 Fuel. ....................................... 8-25 Fuel ........................................

8.8 ATRIUM-10 Steady-State Steady-State LHGR Limits ......................................................................

...................................................................... 8-26 8.9 ATRIUM-10 LHGRFACp LHGRFAC p Multipliers Multipliers for NSS/TSSS NSS/TSSS Insertion Times All Cycle C ycle 9 E Exposures xposures .......................................................................................................

....................................................................................................... 8-27 8.10 GE14 LHGRFAC LHGRFACpp Multipliers Multipliers for NSS/TSSS Insertion Insertion Times All Cycle 9 Exposures Ex po su re s ........................................................ :......................... ,............................ :.... 8-28

.................................................................................................................... 8 -2 8 8.11 ATRIUM-10 ATRIUM-10 LHGRFACf LHGRFACf Multipliers Multipliers All Cycle 9 Exposures ..........................................

.......................................... 8-29 8.12 GE14 LHGRFAC LHGRFACff Multipliers Multipliers All Cycle 99 Exposures ...................................................

................................................... 8-30 8-30 8.13 - ATRIUM-10 ATRIUM-10 MAPLHGR MAPLHGR Limits .........................................................

...................................... :....................... ;... 8-31 Figures Figures 1.1 Browns Ferry Power/Flow Browns Power/Flow Map Map - 105% 105% OL OLTP .............................................................

TP .............................................................. 1-3 4.1' .

4.1 Core-wide Core-wide Radial Power Histogram Histogram for Limiting TLO Exposure .................................... .4-8 Exposure ................................... 4-8 4.2 Core-wide Radial Power Histogram Core-wide .............................. ..... .4-9 Histogram for Limiting SLO Exposure ........................*.......... 4-9 5.1 EOCLB EOCLB LRNB at 1 1OOP/1 00P/105F 05F - TSSS Key Parameters Parameters .... ;................................. :;I........

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

........ 5-24 5.2*

5.2 EOCLB LRNB at 100P/105F EOCLB 1OOP/105F - TSSS Sensed Water Level ..................................... ................... ;... 5-25 5.3 EOCLB EOCLB LRNB at 100P/105F 10OP/105F - TSSS Vessel Pressures .............................................

Pre~sures ............................................. 5-26 f:

5.4 EOCLB FWCF at 100P/105F EOCLB 1OOP/105F -TSSS .....................

- TSSS Key Parameters .......................................... 5-27

.... 5-27*

5.5 5:5 EOCLB FWCF at 100P/105F EOCLB 1OOP/1 05F - TSSS Sensed .................. ~ ............ :...... 5-28 Sensed Water Level ....................

5.6.

5.6* EOCLB FWCF at 100P/105F ....................

10OP/105F - TSSS Vessel Pressures ............................................ 5-29 7.1 MSIV MSIV Closure Overpressurization Evenfat Closure Overpressurization 102P/105F - Key Parameters ..................

Eventat 102P/105F ................... 7-8 7.2 7:2 MSIV MSIV Closure Overpressurization Event at 1 Closure Overpressurization 02P/1 05F - Sensed Water*

102P/105F Water L e v e l.....................................

Level I.........................................................................................

.......................... ........*..................................................... :.......................... .-........... 7-9 7 -9 7.3 MSIV Closure MSIV Overpressurization Event at 1 Closure Overpressurization 02P/105F - Vessel 102P/105F Pressures P ressures .......... .... ;..................... .-......~ ...................

.......................I:................................

. .................................... .... ;.... 7-10 7-10 7.4 MSIV Closure MSIV Overpressurization Event at 1 Closure Overpressurization 102P/1 02P/105F 05F - Safety/Relief Valve Flow Rates Rates ............ ,........... ; ... ~ .................. ,..............................................

........................................................ ...................... ::.; ... .-.... 7-11 7,..11 AREVA NP Inc.

Inc.

ANP-2863(NP)

ANP-2863{NP)

Browns Ferry Unit 1 Cycle 9 Revision Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP Page vv 7.5 Overpressurization Event at 100P/81 PRFO ATWS Overpressurization 1OOP/81 F F - Key Parameters Parameters ....................

.................... 7-12 7-12 7.6 Overpressurization Event at 100P/81 PRFO ATWS Overpressurization 1OOP/81 FF - Sensed Water Level Le ...................... ;..............................................................................................

ve l.................................. . ...................................................... :....... 7-13

.............. ................... 7-13 7.7 Overpressurization Event at 100P/81 PRFO ATWS Overpressurization 1OOP/81 F - Vessel Vessel Pressures Pressures .............

............. .-.... 7-14 7-14 7.8 PRFO ATWS Overpressurization Overpressurization Event at 100P/81F 1OOP/81 F - SafetY/Relief Safety/Relief Valve Valve Flow R Rates .........................................................................................................7-15 ates ......................................................................................................... 7-15 Inc.

AREVA NP Inc:

ANP-2863(NP)

Browns Ferry Unit 1.

I Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP Page vi Nomenclature Nomenclature 2PT two pump trip trip ADS ADS automatic depressurization system automatic depressurization AOT abnormal operational abnormal operational transient transient APLHGR APLHGR average average planar generation rate planar linear heat generation ARO all control control rods out ASME ASME American Society of Mechanical Engineers Mechanical Engineers AST alternate alternate source term ATWS ATWS anticipated transient anticipated transient without scram ATWS-PRFO ATWS-PRFO anticipated anticipated transient transient without scram pressure regulator regulator failure open ATWS-RPT ATWS-RPT anticipated anticipated transient transient without scram scram recirculation pump triptrip .

BF1 Browns Browns Ferry Unit 1

. BLEU BLEU blended blended low enriched enriched uranium uranium BOC BOC beginning-of-cycle beginning-of-cycle BPWS BPWS banked withdrawal sequence banked position withdrawal sequence BSP BSP backup backup stability protection BWR BWR boiling water reactor BWROG BWROG Boiling Water Reactor Owners Group Owners Group CAD containment atmosphere containment atmosphere dilution dilution CFR CFR Code of Federal Federal Regulations Regulations COLR COLR core operating operating limits report CPR critical power ratio ratio CRDA control rod drop accident accident CRWE CRWE . control rod withdrawal error DIVOM delta-over-initial CPR versus oscillation delta-over-initial magnitude oscillation magnitude ECCS ECCS emergency core cooling system

I

. EFPD effective full-power fUll-power days EFPH effective full-power hours full-power hours EFPY effective full-power years

'effective full-power years EOC EOC end-of-cycle end-of-cycle EOCLB end-of-cycle licensing end-of-cycle licensing basis basis EOC-RPT-OOS EOC-RPT -OOS end-of-cycle recirculation end-of-cycle recirculation pump trip out-of-service out-of-service EOD extended operating domain EOFP EOFP end of full power

!,-< EOOS EOOS equipment out-of-service out-of-service EPU extended power uprate poweruprate

, . FFTR final feedwater temperature temperature reduction

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

ANP-2863(NP)

Browns Ferry Unit 1 Cycle Cycle 9 . Revision Revision 0 Page vii

.. Page Reload Safety Analysis for 105%

105% OL TP OLTP Nomenclature Nomenclature (Continued)

(Continued)

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

LFWH loss of feedwater heating heating LHGR LHGR* linear linear heat generation generation rate LHGRFACff LHGRFAC flow-dependent linear heat generation flow-dependent generation rate multipliers multipliers LHGRFACPp LHGRFAC power-dependent linear heat generation power-dependent generation rate multipliers multipliers LOCA . loss-of-coolant accident loss-of-coolant accident LOFW LOFW loss of feedwater flow LPRM local power power range monitor monitor LRNB LRNB generator load rejection' generator rejection with no bypass bypass

/

, MAPLHGR MAPLHGR maximum maximum average planar linear linear heat generation generation rate-MCPR MCPR minimum minimum critical power ratio power ratio .

MCPRf MCPRf flow-dependent minimum critical power ratio flow-dependent ratio MCPRpp MCPR power-dependent power-dependent minimum minimum critical power ratio power ratio MELLLA MELLLA maximum maximum extended load line limit analysis.

load line limit analysis MSIV MSIV main steam isolation valve isolation valve MSRV main steam relief valvevalve _

MSRVOOS MSRVOOS main steam relief valve out-of-service out-of-service '

NEOC NEOC near. end-of-cycle near: end-of-cycle NSS NSS nominal nominal scram speed NRC NRC Nuclear Nuclear Regulatory Regulatory Commission, Commission, U.S.

OLMCPR OLMCPR operating limit minimum critical power ratio power ratio OLTP OLTP original licensed thermal power OPRM oscillation power range monitor

., Pbypass Pbypass . power power below which direct scram on TSV/TCV closure is bypassed PCT peak cladding temperature .

PLU unbalance.,

power load unbalance*

PLUOOS PLUOOS power load unbalance unbalance out-of-service out-of-service

., I PRFO PRFO pressure pressure regulator failure open

!~ ,

f' RBM (control) rod block block monitor monitor RHR RHR residual heat removal RPT,..

RPT recirculation pump trip' recirculation' trip AREVA NP Inc.

ANP-2863(NP)

'. Browns Ferry Unit 1 Cycle 9 0 Revision 0 Safety Analysis for 105%

Reload Safety 105% OL OLTP TP Page viii Nomenclature

. Nomenclature (Continued)

(Continued)

SLC standby liquid control SLCS standby liquid control system SLMCPR safety satety limit minimum critical power ratio power ratio SLO single-loop operation operation SS 55 steady state steady TBVOOS TBV005 turbine bypass valves out-of-service out-ot-service TBV turbine bypass valves valves TCV TCV turbine control valve valve TIP traversing incore incore probe probe TIPOOS TIP005 traversing incore incore prpbe probe out-ot-service out-of-service TLO .' two-loop operation TSSS technical specifications specifications scram speed

.1 TSV T5V turbine stop valve valve TTNB turbine trip with no bypass bypass TVA Tennessee Valley Tennessee Valley Authority ACPR ilCPR* change change in critical power ratio I'

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J AREVA NP Inc.

ANP-2863(NP) .

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 . Revision 0 Reload Safety Analysis for 105%

105% OL TP OLTP 1-1 Page 1-1 1.0 1.0 Introduction Introduction Reload licensing licensing analyses results generated generated by AREVA NP Inc.* are presented in support of cycle operation.

operation. The analyses analyses reported in this document document were performed using methodologies methodologies approved for generic application to boiling water reactors. The Nuclear previously approved Nuclear Regulatory Commission, Commission, U.S. (NRC) technical technical limitations associated with the application limitations associated application of the approved approved methodologies have have been satisfied satisfied by these analyses.

272 fresh including 272 The core consists of a total of 764 fuel assemblies, including ATRIUMTM-10t fresh ATRIUMTM-10t assemblies assemblies and 492 irradiated GE14 assemblies. Licensing Licensing analyses analyses support the core design design presented in Reference Reference 1.

(

Reload licensing analyses were performed licensing analyses performed for potentially limiting events and analyses identified in Section 2. Results of analyses analyses are used to establish establish the Technical Specifications/COLR Specifications/COLR limits limits and ensure design design and licensing licensing criteria are met. Design and safety analyses analyses are based on both operational assumptions and plant parameters operational assumptions parameters provided by the utility. The results of the reload licensing power/flow map presented licensing analysis support operation for the power/flow presented in Figure 1.1 and also support operation with the equipment support operation equipment out-of-service out-of-service (EOOS) scenarios presented presented in Table 1.1.

1.1.

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

t*

t ATRIUM is a trademark ATRIUM isa trademark of AREVA NP.

J AREVA NP Inc.

AREVA

ANP-2863(NP)

Browns Ferry Unit 1I Cycle 9 Revision Revision 0 Reload Safety Analysis Analysis for 105%

105% .OL

.OLTPTP Page Page 1-2 Table 1.1 EOD and EOOS EOOS Operating Conditions Conditions Extended Operating Domain Extended Operating Domain Conditions (EOD) Conditions Increased core flow (ICF)

Increased Maximum extended Maximum extended load line limit analysis (MELLLA)

Combined Combined final tinal feedwater temperature reduction teedwater temperature reduction (FFTR) /

coastdown Equipment Out-ot-Service Equipment Out-of-Service Conditions*

(EOOS) Conditions*

Turbine bypass valves out-ot-service out-of-service (TBVOOS)

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

t

, ' out-ot-service (EOC-RPT-OOS)

I'

' Feedwater heaters out-of-service Feedwater out-ot-service (FHOOS)

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

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

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

(SLO)

,i I' ,

. '~

SLOSLO may may be be combined combined with with all all of of the the other EOOS conditions. Base other EOOS Base case and and each EOOS EOOS condition condition in combination is supported in with 1 MSRVOOS, combination 'with MSRVOOS, up to 2 traversing incore probe (TIP) machines machines out-of-

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

out-of-service. ' .

AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Unit 1 I Cycle 9 Revision O. 0 Reload Safety Analysis for 105% 105% OL OLTP TP Page 1-3 1..:3 140~--~------~----~--------~~----------~----------------------~----~

140 Power/Flow Points 130 . A 130 lOOP/81F B lOOP/lOOF 120 120 c: lOOP/105F 110 110

-=

~IOO 100 II> 90

~

a=

~

=

-; 80 80

...a II>

.c::I 70 Eo<

'0

....II> +/-60 60

=-

~ 50 50 40 Minim~m Flow Control Line!

Ii 30 30 20 20 Minirrium Power Line 10 ........ ... . . . . . . . . ..L ...................................... L. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . : . . . . . . . . . . . I 0

0 10 20 30 40 50 60 70 80 90 100 110 120 120 Core Flow (% (% of Rated)

Figure 1.1 Browns Ferry Power/Flow Power/Flow Map Map-- 105% OL OLTP TP AREVA AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Unit 1.1.Cycle Cycle 9 Revision Revision 0 Reload Safety Analysis for 105%

105% OLOLTPTP Page 2-1 2.0 Disposition Disposition of Events Events '.

The objective is to identify limiting limiting events for analysis, supporting supporting operation with ATRIUM-10 ATRIUM-10 fuel. Events and analyses identified as potentially analyses identified limiting are either potentially limiting either evaluated generically generically for the the introduction introduction of AREVA fuel or on a cycle-specific cycle-specific basis.

The first step is to identify the licensing licensing basis of the plant. Included Included in the licensing licensing basis are descriptions postulated events/analyses descriptions of the postulated events/analyses and the associated associated criteria. Fuel-related Fuel-related system design criteria must be met, ensuring regulatory compliance and safe operation. The licensing regulatory compliance licensing contained in the Final Safety Analysis basis, related to fuel and applicable for reload analysis, is contained Analysis Report Report (FSAR),

(FSAR), the Technical Technical Specifications, Specifications, Core Operating Operating Limits Reports (COLR), and other other reload analysis reports.

This report supports supports 105%

105% OL OLTP TP operation, which is the power level currently currently supported the supported in the FSAR and Technical Specifications.

Specifications. EPU analyses analyses and documents documents were considered considered in support I .

of the disposition of events review (References (References 33, 34, 35, 36, and 39). The conclusions conclusions of the the review were the same for both 105% 105% OLTP OLTP and 120%

120% OLTPOLTP operation.

operation.

The main steam turbine for Unit 1 has been modified for 120% 120% OLTP operation.

operation. The same same turbine modifications modifications have not yet occurred for Units 2 and 3 to support EPU. For 105%OLTP EPU. For 105% OLTP operation, the only significant operation, significant difference difference for the reload licensing analyses analyses due to the turbine turbine modifications modifications is the position of the turbine control valve (TCV). The turbine modificationsmodifications result in the TCV being less open for a given steam flow. This in turn results in an increase in severity for pressurization pressurization events with closure of the TCV; for example, the load rejection event. The The TCV position is explicitly modeled in the reload analyses analyses for limiting limiting events events that have have TCV closure and is based on the 120% 120% OL OLTP TP modifications. The turbine modifications modifications do not

. change the conclusion of the disposition of events for BF1 105% 105% OLTP OLTP operation.

Except Except for core loading and the turbine modifications modifications previously previously discussed, discussed, all three Browns Browns Ferry Units (1, 2, and 3) are essentially essentially the same because core operational operational conditions, modeled modeled

.I

geometry, safety system performance, parameters are identical.

performance, and ECCS parameters identical. A review of

., geometry between geometry between Units 1, 2, and 3 determined determined the only significant difference difference was the the recirculation piping for Unit 3 (Unit 3 has undergone recirculation undergone a recirculation recirculation header header and riser Differences in recirculation piping for Unit 3 do not r~sult replacement). Differences result in.

in any modifications modifications to the recirculation recirculation piping model used in the analyses (simplification (simplification of the recirculation recirculation piping piping distinguish the differences).

model does not distinguish differences). The review of differen'ces differences between units concluded concluded AREVA AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 Revision d

. Reload Safety Analysis for 105% 105% OLOLTP TP Page 2-2 Page 2-2 .

. none of the analyses, or dispositions in Reference Reference 34, needed to be revised revised for Unit 1.

Differences in core design between units are addressed cycle~specific basis.

addressed on a cycle-specific AREVA reviewed all fuel-related fuel-related design criteria, events, and analyses identifiedidentified in thethe.licensing licensing basis. In In many cases, when operating operating limits are established to ensure acceptable ensure acceptable consequences consequences of an abnormal operational transient transient (AOT) or accident, the fuel-related fuel-related aspects of the system design criteria are met. All fuel-related events were reviewe~

fuel-related events reviewed and dispositioned dispositioned into one of the following categories:

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

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

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

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

current analysis '

! 2. Address event event each consequences of the event are potentially each reload. The consequences potentially limiting and

,, need to be addressed addressed each reload. '

,r I '

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

,( ,

I' a. The analysis is performed performed using conservative conservative bounding assumptions and inputs inputs r

~

such that the initial reload results will remain applicable for future reloads remain applicable reloads of the the

!:' i same fuel design. . . . ' ". . .

b. Results from the first reload will be be used to quantitatively demonstrate demonstrate that the the results remain applicable applicable for future reloads of the same fuel design because the design because the

,I i consequences are benign or bound by those of consequences are benign or bound by those of another event. another event.

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

considered.

i' i : A disposition summary is presented in 'Table disposition of events summary 2.1. The disposition Table 2.1. disposition summary summary presents a list of the events events and analyses, the corresponding corresponding FSAR section, the disposition status, and any

1

. applicable comments. In each comment, the basis applicable basis. of the disposition disposition is categorized categorized as:

- FSAR analysis analysis (which may Reference 34).

may include Reference 1 :

- Generic Generic analysis. A independent of plant type. . .

bounding analysis that is independent Abounding , .

- . Plant specific analysis. The analysis is based on Browns Ferry (independent of unit) 'and. and i'

( , is bounding bounding for cycle-to-cycle cycle-to-cycle variations. .. ,': . . ' .' "

I,

Cycle specific analysis. The analysis is specific and Cyde~

to the Unit and, specific tothe Cycle.

The disposition for the EOOS scenariosscenarios are are summarized summarized in Table 2.2. ICF and MELLLA MELLLA operation operation regions regions of the power/flow power/flow map are included included in the disposition disposition results presented in Table 2.1. 2.1. Methodology Methodology and evaluation evaluation models models used for the the ..

cycle specific analyses are provided provided in Table 2.3. OverpressLirization Overpressurization cmalysesare analyses are

,I:

j"r, . performed performed withwith the theNRC NRC approved approved code COTRANSA2 COTRANSA2 (References, 12 and 41). 41). "..':.

AREVA NP Inc.

AREVA NPlnc:

ANP-2863(NP)

Browns Ferry Unit 1 Cycle Cycle 9 '. Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP . Page 2-3 2-3 Table 2.1 Disposition of Events Summary of Events for Browns Ferry Unit 1. 1.

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

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

Demonstrate design criteria are met.

design criteria 1 I 3.6 design Nuclear design Nuclear Address event each Cycle specific specific analysis.

reload

. reload Refer to Reference 1'for the analysis,

1 (

I Refer to Reference nor the analysis, acceptance acceptance criteria, methodology and .

criteria, methodology evaluation model.

evaluation Demonstrate design Demonstrate design criteria are met.

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

hydraulic design design reload Demonstrate design Demonstrate design criteria criteria are met. Fuel are met. Fuel

~~ I hydraulic design design and compatibility'results compatibility. results

'l

: provided in the Thermal-Hydraulic are provided Thermal-Hydraulic Design report. Refer to Reference Reference 3 for the analysis, acceptance acceptance criteria,,'

criteria, methodology and evaluation model.

methodology Other model. Other cycle cycle specific criteria are presented presented in thisthis report, i.e., operating limits.

Le., thermal operating I: 3.8 Standby liquid Address event each Cycle specific specific analysis.

control system system reload Analysis performed performed each reload to verify

. adequate adequate SLCS shutdown shutdown capacity.

I. :'

Ii

\ ..

AREVA NP Inc.,

Inc.

ANP-2863(NP)

Revision Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Safety Analysis for 105%

105% OLTP OLTP Page 2-4 '

Table 2.1 Disposition of Events Summary for Browns Ferry Unit I1 (Continued)

(Continued)

FSAR Section Event IAnalysis

/Analysis Disposition Status

'Disposition Comments Comments 4.2 Reactor Reactor vessel and analyses No further analyses Reference 34.

FSAR analysis and Reference appurtenances appurtenances required required The vessel fluence irradiation is primarily f1uence irradiation primarily mechanical design mechanical dependent dependent upon the effective power effective full power years years (EFPY), power distribution, power power distribution, power level, and fuel management management scheme. The The neutron spectrum neutron spectrum of the ATRIUM-10 ATRIUM-10 fuel is sufficiently similar to the spectrum licensing basis evaluation of applied in the licensing the vessel irradiation irradiation limits. The void, power distributions, distributions, and the fission spectrum for ATRIUM-10 ATRIUM-10 fuel are not significantly impacted significantly BLEU. An impacted by BLEU.

evaluation of ATRIUM-10 BLEU fuel flux flux concluded that the GE EPU analyses analyses

~.

remained bounding.

remained bounding. The introduction introduction of ATRIUM-10 ATRIUM-10 fuel with or without BLEU will have an insignificant insignificant effect on the fluence f1uence (E > 1.0 MeV) at the reactor reactor vessel wall and internals.

t.

? .-

AREVA NP Inc~

Inc.

ANP-2863(NP)

Browns Browns Ferry Ferry Unit Unit 1 Cycle 9 Revision 0

'Revision Reload Safety Analysis for 105% OL OLTPTP Page Page 2-5 2-5 Table 2.1 Disposition of Table2.1 Events Summary of Events for Browns Ferry UnitUnit11 (Continued)

(Continued)

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

pressure relief reload plant specific analysis (LOCA).

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

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

5.2 Primary No further analyses FSAR analysis and Reference 34.

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

5.3 Secondary No further analyses FSAR analysis and Reference 34.

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

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

LOCA is a potentially limiting accident.

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

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

7.5 Neutron Address event each Plant specific and cycle specific analysis.

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

AREVA NP Inc. '

ANP-2863(NP)

ANP-2863(NP}

Browns Ferry Unit 1 Cycle 9 Ferry Unit .* Revision Revision 0 Reload Reload Safety Analysis Analysis for 105% OLOLTP TP : Page Page 2-6 2-6 Table Table 2.1 Disposition of Events Summary for Browns Ferry Unit 1 (Continued)

(Continued)

FSAR FSAR Section Event./Analysis Event! Analysis Disposition Disposition Status Status Comments Comments 7.19 Anticipated Anticipated Address Address event eacheach Cycle specific analysis.

transient without reload scram Analyses are performed to demonstrate Analyses demonstrate that the peak vessel pressure for the the limiting ATWS event event is less' less than 120% of design pressure.

pressure. Long term A ATWS TWS analyses remain analyses remain applicable applicable for ATRIUM-ATRIUM-10 (Section 7.2.2).

10 8.10 blackout Station blackout No further analyses analyses FSAR analysis analysis and Reference Reference 34.

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

. perform in a manner analogous with fuel of current and I

I! previous designs.

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

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

evaluation model.

, . Evaluated Evaluated for new fuel storage storage racks.

Confirm applicability each reload:,

reload.

10.3 Spent fuel storage storage Address for initial Plant specific specific analysis.

reload

" , Refer to Reference Reference 25 for the analysis,

~ I acceptance criteria, methodology, and acceptance and evaluation model.

' J Evaluated for spent fuel storage Evaluated storage racks.

Confirm applicability each reload.

}

10.11 10.11 Fire protection Address for initial for initial' Plant specific specific analysis.

systems systems reload reload Appendix R criteria are met for ATRIUM-

~"

.I Appendix R criteria are met for ATRIUM-10 10 fuel. This issue is addressed in

. ), . Reference 37 Reference 37..

,. 14.5.2.1 Generator trip No further analyses FSAR analysis and Reference 34.

" 14.5.2.1 Generator trip No further analyses FSAR analysis and Reference 34.

(TCV fast (TCV fast closure) closure) required required Bound by the generator trip with turbine

~ .

Bound by the generator trip with turbine I'

, bypass valve failure.

! I AREVA NP Inc.

ANP-2863(NP)

ANP-2863(NP}

Browns Browns Ferry Unit 1. 1 Cycle 9 Revision 0 Revision Reload Safety Analysis for 105%

105% OL OLTPTP Page 2-7 2-7 Table Table 2.1 Events Summary 2.1 Disposition of Events for Browns Ferry Unit 1 (Continued)

(Continued)

FSAR Section Event /Analysis Disposition Status Comments 14.5.2.2 Generator trip Address event each Cycle specific analysis.

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

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

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

14.5.2.3 Loss of condenser No further analyses FSAR analysis.

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

14.5.2.4 Turbine trip (TSV No further analyses FSAR analysis.

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

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

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

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

valves failure reload following turbine Generally bound by the generator trip with trip (TTNB), low turbine bypass valve failure. If 14.5.2.5 is power bound by generator trip with turbine bypass valve failure, then 14.5.2.6 is also bound.

14.5.2.7 Main steam No further analyses FSAR analysis and Reference 34.

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

14.5.2.8 Pressure regulator No further analyses FSAR analysis and Reference 34.

failure (downscale) required Eliminated as an AOT by the installation of

- a digital fault-tolerant main turbine electro-hydraulic control system.

,., :i

. i, AREVA AREVA NP Inc.

Inc.

. j

. ANP-2863(NP)

ANP-2863(NP)

Browns Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Reload Safety OLTP Safety Analysis for 105% OLTP Page 2-8 2-8 Table 2.1 Disposition of Events Summary Browns Ferry Unit 1 for Browns (Continued)

(Continued)

FSAR Section Event /Analysis Disposition Status Comments 14.5.3.1 Loss of feedwater Address event each Cycle specific analysis.

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

14.5.3.2 Shutdown cooling No further analyses FSAR analysis.

(RHR) malfunction requiredB

- decreasing Benign event.

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

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

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

14.5.4.1 Continuous rod Address event each Cycle specific analysis.

withdrawal during reload power range This event is a potentially limiting AOT.

operation 14.5.4.2 Continuous rod No further analyses FSAR analysis.

withdrawal during required reactor startup Benign event.

14.5.4.3 Control rod No further analyses FSAR analysis.

removal error required during refueling 'This event it not credible.

14.5.4.4 Fuel assembly No further analyses FSAR analysis.

insertion error required during refueling Thisevent it not credible.

Mislocated or Address event each Generic analysis.

misoriented fuel reload assembly AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Ferry Unit 1 Cycle 9 , Revision 0 Reload Safety Safety Analysis for 105%

105% OLTP OLTP Page 2-9 Table 2.1 Disposition Disposition of Events Summary for Browns Ferry Unit 11*

(Continued)

FSAR Section Event /Analysis IAnalysis Disposition Status Comments Comments 14.5.5.1 14.5.5.1 Pressure regulator Address event each FSAR analysis and cycle specific analysis.

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

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

14.5.5.2 14.5.5.2 Inadvertent Inadvertent No further analysis FSAR analysis.

opening opening of a required MSRV (IORV)

MSRV(IORV) Benign event.

14.5.5.3 14.5.5.3 Loss of feedwater feedwater No further analysis FSAR analysis.

flow (LOFW) required Benign event.

event.

Benign

~ i 14.5.5.4 14.5.5.4 Loss of auxiliary auxiliary No further analyses FSAR analysis.

power

required Benign event.

Benign event.

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

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

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

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

14.5.6.3 14.5.6.3 Trip of two No further analyses . FSAR analysis.

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

14.5.6.4 Recirculation Recirculation No further analysis FSAR analysis.

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

AREVA NP Inc.

ANP-2863(NP)

ANP-2863(NP) ,

Browns Ferry Unit 1 I Cycle 9 Revision 0 Revision Reload Reload Safety Analysis for 105% OL OLTPTP 2-10 Page 2-10 Table 2.1 Disposition of Events Summary for Browns Ferry Unit 1 (Continued)

(Continued)

FSAR FSAR Section /Analysis Event IAnalysis Disposition Status Comments Comments 14.5.7.1 14.5.7.1 Recirculation flow Recirculation ' Address event each Cycle specific analysis.

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

reload.

14.5.7.2 Startup of idle No further analysis FSAR analysis.

recirculation loop recirculation required Benign event.

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

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

event is a potentially maximum demand 14.5.8.2 Feedwater Feedwater Address event each Cycle specific specific analysis.

" ' controller failure reload

!, (FWCF) - This event potentially limiting AOT.

event is a potentially I, I maximum demand demand with EOC-RPT-OOS 14.5.8.3 14.5.8.3 Feedwater Address event each Cycle specific specific analysis.

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

event is a potentially maximum demand demand with TBVOOS with TBVOOS 14.5.9 1.4.5.9 Loss of habitability No further analyses FSAR analysis.

'/ '

of the control room required This is postulated postulated as a special event to demonstrate the ability to safely shutdown 1;,

" , the reactor from outside the control room.

<~ ;

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

accident accident (CRDA) reload Consequences of the CRDA are ,evaluated

, Consequences evaluated to confirm that thaUhethe acceptance acceptance criteria are

,I' satisfied.

, AREVA NPNP Inc~

Inc.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Revision 0 Revision 105% OLTP Reload Safety Analysis for 105% OLTP Page Page 2-11 2-11 Table 2.1 Disposition Disposition of Events Summary S.ummary for Browns Ferry Unit 1 (Continued)

(Continued)

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

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

LOCA heatup analysis for reload-reload' fuel is evaluated evaluated for follow-on reloads to address address

,, neutronic design.

changes in neutronic

,~ :

14.6.4 14.6.4 Refueling accident accident Address event each specific analysis.

Plant speCific reload Refer to Reference Reference 27 for the analysis, acceptance criteria, methodology acceptance methodology and

, .' evaluation evaluation model. . .

i

~ :

Consequences Consequences of the refueling accident' accident.

. are evaluated evaluated to confirm that the the acceptance criteria are satisfied.

. acceptance satisfied.

(' .

, , 14.6.5 14.6.5 Main Main steam line No further analysis Reference 34.

FSAR analysis and Reference

'j}

break accident break accident required J'

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

criteria .

Radiological dose consequences

. Radiological consequences have been performed utilizing AST in accordance withwith 10 CFR 50.67. The The consequences of the event consequences event are not a function of fuel type since no fuel failures offuel failures calculated to occur.

are calculated The dose is a occ;:ur. The function of the radionuclide inventory in theradionuclide the coolant coolant itself prior to the event.

AREVA NP Inc.

AREVANP

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% TP OLTP . Page 2-12 2-12 2.2 Disposition of Operating Table 2.2' Operating Flexibility and and EOOS Options on EOOS Options on Limiting Events Events Option Affected Limiting Comments Comments Events/Analyses Events/Analyses One MSRV ASME Overpressurization Overpressurization This scenario is included included as part of the base, base Out-of-Service Out-of-Service case condition for the events/analyses events/analyses FWCF identified.

identified.

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

SLMCPR

.i" (

, ' The SLO SLMCPR is addressed addressed each

,I, reload.

, 1 Feedwater Final Feedwater FWCF This scenario is included in each reload included in reload for

,I, Temperature Temperature Reduction each each of these events/analyses.

these events/analyses.

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

(BSP)

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

I' (TBVOOS) ,

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

LRNB LRNB i,

TTNB TINB'

,I'

, Power load unbalance LRNB LRNB The LRNB LRNB event with PLUOOS is evaluated out-of-service out-of-service each reload.

'i'

! ; (PLUOOS)

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

I AREVA NP Inc.

ANP-2863(NP)

ANP-2863(NP}

Browns Ferry Unit 11. Cycle 9 Revision 0 105% OLTP Reload Safety Analysis for 105% OLTP . Page 2-13 2-13 Table 2.3 Methodology Evaluation Models for Cycle Specific Methodology and Evaluation Specific Analyses Reload Analyses Analysis Analysis FSAR Methodology Methodology Evaluation Evaluation Acceptance Acceptance Criteria and Section Event /Analysis IAnalysis Reference Reference Model Model Comments Comments 3.7 Thermal and 4 SAFLlM2 SAFLIM2 SLMCPR criteria: < 0.1% 0.1 % fuel hydraulic design 12 COTRANSA2 rods experience experience boiling boiling 12 COTRANSA2 transition.

13 XCOBRA XCOBRA Transient criteria: Power and Transient criteria: Power and 14 XCOBRA-T XCOBRA-T flow dependent dependent MCPR and 16 RODE)(2 LHGR operating LHGR operating limits limits 16 RODEX2 established to meet meet the fuel failure criteria.

3.8 Standby liquid Standby 15 CAS MO-4 CASMO-4 SLCS criteria: Shutdown Shutdown margin margin control control system IMICROBURN-

/MICROBURN- of at least least 0.88% Llklk.

Ak/k.

B2 B2

J \ 4.4 4:4 Nuclear system Nuclear 12 COTRANSA2 COTRANSA2 Analyses for ASME and A TWS ATWS pressure relief overpressurization.

overpressurization.

system system ASME overpressurization ASME overpressurization l (

') 1 criteria: Maximum Maximum vessel I

i pressure pressure limit of 1375 pSlgpsig and maximum pressure limit of maximum dome pressure 1325 psig.

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

6.0 Emergency core Emergency 38 HUXY HUXY LOCA criteria: 10CFR50.46.

LOCA 10CFR50.46.

cooling cooling systems EXEM BWR-2000 Methodology.

EXEM BWR-2000 Methodology.

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

7.5 Neutron 7 STAIF Long term stability solution monitoring system 8 RAMONA5-FA Option III criteria: OPRM monitoring system 8 RAMONA5-FA setpoints do not result in setpoints do not result in' 9 CASMO-41/

CASMO-4 exceeding OLMCPR limits.

exceeding MICROBURN-MICROBURN-10 B2 CRWE criteria: Power CRWE Power B2 dependent MCPR and LHGR dependent MCPR and LHGR 11 operating limits established to operating limits established to '

15 meet meet the fuel failure criteria.

30 30 Backup stability protection.

protection criteria: Stability boundaries that acceptable

. do not exceed acceptable global, regional and channel decay decay ratios as defined defined by thethe STAIF STAIF methodology.

methodology.

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ANP-2863(NP)

Browns Ferry Browns Ferry Unit Unit 1 Cycle Cycle 99 Revision Revision 0 Reload Safety Reload Safety Analysis Analysis for 105%

105% OLTP OLTP Page Page 2-14 2-14 Table Table 2.3 Methodology and 2.3 Methodology and Evaluation Models for Cycle Evaluation Models Cycle Specific Specific Reload Reload Analyses Analyses (Continued)

(Continued)

Analysis Analysis FSAR FSAR Methodology Methodology Evaluation Evaluation Acceptance Criteria and Acceptance Section Event /Analysis IAnalysis Reference.

Reference Model Model Comments Comments 7.19 Anticipated Anticipated 12 COTRANSA2 COTRANSA2 ATWS overpressurization ATWS overpressurization transient without transient without Maximum vessel criteria: Maximum scram scram pressure 1500 psig.

pressure limit of 1500 psig.

ATWS peak pressure ATWS pressure only.

14.5.2.2 14.5.2.2 Generator trip Generator 12 12 COTRANSA2 COTRANSA2 Transient criteria:

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

failure 16 RODEX2 14.5.2.2.4 14.5.2.2.4 LRNB with with EOC- 12 12 COTRANSA2 COTRANSA2 Transient criteria: Power criteria: Power RPT-OOS RPT-06s 13 XCOBRA dependent dependent MCPRMCPR and and LHGR LHGR .

13 XCOBRA ill' operating limits established operating established to to

.,1. 14 14 XCOBRA-T XCOBRA-T meet the fuel meet the fuel failure criteria..

failure criteria 16 RODEX2 RODEX2

f:

14.5.2.5 Turbine bypass Turbine 12 COTRANSA2 COTRANSA2 Transient criteria: Power Power

, valves failure 13 XCOBRA dependent dependent MCPRMCPR and LHGR LHGR

(

13 XCOBRA

, I following turbine operating operating limits established to trip (TTNB),

(TINB). high 14 XCOBRA-T XCOBRA-T meet

. the fuel failure. criteria:

criteria.'

power 16 16 RODEX2 RODEX2 14.5.2.6 14.5.2.6 Turbine Turbine bypass 12 COTRANSA2 COTRANSA2 Transient criteria: Power Power valves failure 13 XCOBRA dependent dependent MCPR~CPR and LHGR LHGR 13 XCOBRA following turbine .operating operating limits established to trip (TTNB),

(TINB). low 14 XC 0 BRA-T XCOBRA-T meet the fuel failure criteria.

power 16 16 RODEX2 RODEX2 14.5.3.1 Loss of feedwater 15 CASM04 CASMO-4 Transient criteria: Power (LFWH) heater (LFWH) 18 IMICROBURN-

/MICROBURN- dependent MCPRMCPR and .LHGR LHGR 18 B2 operating limits established to .

the fuel meet the meet fuel failure failure criteria criteria 14.5.4.1 Continuous rod 15 15 CASM04 CASMO-4 CRWE CRWE criteria:

criteria: Power Power

,! (, IMICROBURN- dependent MCPR dependent MCPR and LHGR LHGR .

withdrawal withdrawal during /MICROBURN-power range B2 B2- operating limits established to operation operation' meet the fuel failure criteria criteria Mislocated or 15 15 CASMO-4 Mislocated/misoriented criteria:

Mislocated/misoriented criteria: .

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

NP Inc.

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Browns Ferry UnitUnit 1 Cycle 9 'Revision Revision 0 Reload Safety Safety Analysis for 105% OLTP OLTP Page Page 2-15 2-15 Table 2.3 Methodology Methodology and Evaluation Evaluation Models for Cycle Specific Specific Reload Reload Analyses (Continued)

(Continued)

Analysis Analysis FSAR Methodology Methodology Evaluation '

Evaluation Acceptance Acceptance Criteria and Section Event /Analysis IAnalysis Reference Reference Model Model Comments Comments 14.5.17.1 14.5.7.1 Recirculation flow Recirculation 14 CAS M0-4 CASMO-4 Transient criteria: Flow control failure ~- 15 IMICROBURN-

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

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

16 RODEX2 RODEX2 14.5.8.2 Feedwater Feedwater 12 COTRANSA2 COTRANSA2 Transient criteria: Power

~ ,

controller failure 13 XCOBRA dependent MCPR and LHGR dependent MCPR LHGR

1. t 13 XCOBRA

j

.I (FWCF) - operating operating limits established to maximum demand 14 XCOBRA-T XCOBRA-T meet the fuel failure criteria.

I'

',I I

with EOC-RPT- 16 16 RODEX2 RODEX2

.! 'I' OOS OOS

'~ : 14.5.8.3

,14.5.8.3 Feedwater Feedwater 12 COTRANSA2 COTRANSA2 Transient criteria: Power Power

~ ; (FWCF) - failure controller 13 13 XCOBRA '

XCOBRA dependent MCPR and dependent MCPR andLHGR LHGR operating limits established to '

'operating I' (FWCF) -

maximum demand 14 XCOBRA-T XCOBRA-T meet the fuel failure criteria.

'~ ':

, with TBVOOS 16 16 RODEX2 RODEX2

I 14.6.2 14.6.2 Control rod drop 15 CAS MO-4 CASMO-4 CRDA criteria: Maximum Maximum accident (CRDA) accident IMICROBURN-

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

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

LOCA 10CFR50.46.

accident (LOCA).

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

BWR-2000 Methodology.

.~ ;'

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

,I I ~, .

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Browns Browns Ferry Unit 1I Cycle 9 Revision 0 OLTP Reload Safety Analysis for 105% OL TP Page 3-1 3.0 Mechanical Design Analysis Mechanical Analysis Mechanical exposure limits for ATRIUM-10 Mechanical design exposure ATRIUM-10 fuel are presented Reference 2. The presented in Reference The maximum maximum exposure limits for the ATRIUM-10 ATRIUM-10 reload reload fuel are:

54.0 GWd/MTU 54,0 GWd/MTU average average assembly exposure assembly exposure 62.0 GWd/MTU GWd/MTU rod average exposure (full-length fuel rods) average exposure Maximum Maximum exposure limits for GE14 fuel assemblies remain unchanged from that presented in in Reference 26.

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

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

satisfied.

, I AREVA AREVA NP Inc.

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Ferry Unit 1I Cycle 9 Browns Ferry " Revision 0" Revision 0 Reload Safety Analysis for 105% OL OLTP TP . Page Page 4-1 4.0 Thermal-Hydraulic Thermal-Hydraulic Design Analysis Analysis 4.1 Thermal-HydraulicDesign Thermal-Hydraulic Design and Compatibility Compatibility Results of thermal-hydraulic Results thermal-hydraulic characterization compatibility analyses characterization and compatibility analyses are presented in in Reference 3. Analysis results demonstrate Reference demonstrate the thermal-hydraulic thermal-hydraulic design and compatibility compatibility criteria are satisfied for the transition transition core consisting ATRIUM-10 and GE14 fuel.

consisting of ATRIUM-10 fuel.

4.2 Safety Limit MCPR Analysis The safety limit MCPR 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 expected to experience during experience boiling transition during normal operation, operation, or an abnormal operational operational transient transient (AOT). The SLMCPR for all fuel was was determined using the methodology described in Reference determined Reference 4. The analysis performed with analysis was performed distribution conservatively a power distribution representing expected reactor conservatively representing reactor operation operation throughout throughoutthethe cycle.

.1 \

SLMCPR analysis' SLMCPR analysis'used used the SPCB critical power power correlation* additive additive constants and additive additive uncertainty for ATRIUM-10 fuel described constant uncertainty described in References References 5 and 31 Addendum.

Addendum. The,The SPCB additive constants and additive additive constant uncertainty uncertainty for the coresident coresident GE14 fuel were developed using the indirect approach described in Reference developed Reference 6.

. ,i

[ ..

Determination of the SLMCPR Determination SLMCPR explicitly includes the effects of channel channel bow relying on thethe following assumptions: no fuel channels used for more than one fuel bundle lifetime, and and ,

, assembly average average burnup remains less than 55 GWd/MTU for central central ATRIUM-10 and GE14 GE14

, fuel types. The channel bow local peaking uncertainty uncertainty is a function of the nominal and bowed

. I local peaking factors and the standard deviation of the channel bow. bow.

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

The radial power uncertainty used in the analysis includes the effects analysis includes effects of up to 40% of the TIP TIP out-of-service, up to 50% of the LPRMs out-of-service, channels out-of-service, out-of-service, and a 2500 EFPH LPRM 2500 EFPH

>

interval. Radial power factor calibration interval. factor distributions, corresponding corresponding to Table 4.2 results, are shown in Figures 4.1 and 4.2.

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 Repqrt 2007-'

3653 regarding the CPR test loop power error. Analyses incorporate testloop incorporate the revised ATRIUM-1 0 additive' ATRIUM-10additive' constants. Reference

. ,constants. Reference 31 was approved approved by the NRC in in the final safety evaluation Reference 42.

evaluation of Reference AREVA NP Inc.

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Ferry Unit Browns Ferry Browns Cycle 99 Unit 11Cycle Revision 00 Revision Reload Safety Reload Analysis for Safety Analysis for 105%

105% OLTP OLTP Page Page 4-2 4-2 Analysis results support Analysis results operation (TLO) two-loop operation support two-loop SLMCPR of (TLO) SLMCPR of 1.09 1.09 and single~loop operation and single-loop operation.

SLMCPR of (SLO) SLMCPR (SLO) of 1.11. Analysis results 1.11. Analysis including the results including SLMCPR and the SLMCPR and the percentage of the percentage of rods rods expected to expected boiling transition experience boiling to experience transition are summarized in are summarized in Table Table 4.2.

4.2.

4.3 4.3 Hydrodynamic Stability Core Hydrodynamic Browns Ferry has BrownsFerry implemented BWROG ha~ implemented BWROG Long Long Term Stability Solution Term Stability Option III Solution Option III (Oscillation (Oscillation Power Range Power Monitor-OPRM). Reload Range Monitor-OPRM). validation has Reload validation performed in been performed has been accordance with in accordance with Reference 7.

Reference The stability

7. The Operating Limit based Operating stabilitY based (OLMCPR) is MCPR (OLMCPR)

Limit MCPR provided for is provided for two two conditions as conditions function of as aa function OPRM amplitude of OPRM setpoint in amplitude setpoint Table 4.3.

in Table 4.3. The two conditions The two conditions evaluated evaluated are for aa postulated are for oscillation at postulated oscillation 4S% core at 45% flow steady core flow operation (SS) state operation steady state (SS) and following aa two and following two recirculation pump recirculation pump trip (2PT) from trip (2PT) limiting full the limiting from the operation state power operation full power state point. Power- and point. Power- and Flow-Flow-dependent dependent limits provide adequate limits provide adequate protection against violation protection against violation of of the SLMCPR for the SLMCPR for postulated postulated V*

. I

'I \

instability as reactor instability reactor as long long asas the limit is operating limit the operating greater than is greater than or equal to or equal specified value the specified to the value for for

\

selected OPRM the selected the OPRM setpoint. supporting EOOS Setpoints supporting setpoint. Setpoints conditions are operating conditions EOOS operating provided in are provided in

i \ Table Table 4.3.

4.3 .

I' .

" Evaluations by Evaluations by General Electric (GE)

General Electric have shown (GE) have shown that the generic that the generic DIVOM curves specified DIVOM curves specified in in Reference 77 may Reference may not conservative for be conservative not be for current current plant conditions for operating conditions plant operating for plants plants which which

, have implemented have Option Ill.

Stability Option implemented Stability III. The non-conservatism was The non-conservatism addressed by was addressed by performing performing I

calculations for calculations the relative for the change in relative change CPR as in CPR function of as aa function of the calculated hot the calculated channel oscillation hot channel oscillation I'

magnitude Analyses were (HCOM). Analyses magnitude (HCOM). performed with were performed with the RAMONAS-FA code the RAMONA5-FA code in accordance with in accordance with Reference 30.

Reference 30. The code is The code coupled neutronic-thermal-hydraulic is aa coupled three-:dimensional transient neutronic-thermal-hydraulic three-dimensional transient model for model for the purpose of the purpose determining the of determining the relationship between the relationship between the relative change in relative change ACPR and in .~CPR and the the HCOM HCOM on on aa plant plant specific specific basis.

basis. TheThe method method was was developed developed consistent consistent withwith thethe recommendations of recommendations the BWROG of the BWROG in Reference 8.

in.Reference Generation of

8. Generation of plant-specific DIVOM data plant-specific DIVOM data isis consistent with consistent the BWROG with.the resolution of BWROG resolution of the non-conservatism as the non-conservatism provided in as provided Reference 9.

in Reference 9. The The stability-based OLMCPRs were stability-based OLMCPRs calculated using were calculated using thethe most calculated change limiting calculated most limiting change in in relative relative

I I

ACPR

~CPRfor for a given oscillation magnitude.

given oscillation magnitude .

I In cases where In cases where the the OPRM system, is OPRM system is declared inoperable, Backup declared inoperable, Backup Stability Protection (BSP)

Stability Protection (BSP) is is provided in provided accordance with in accordance Reference 10.

with Reference BSP curves

10. BSP curves havehave been evaluated using been evaluated using STAIF STAIF (Reference (Reference 11) 11) to determine endpoints to determine decay ratio meeting decay endpoints meeting ratio criteria for the criteria for BSP Base the BSP Base Minimal Mirimal, (scram region)

Region II (scram Region and Base region) and Base Minimal Region, II Minimal Region, (controlled entry II (controlled region). Stability entry region). Stability AREVA AREVA NP Inc.Inc..

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Browns Ferry Unit 1 ,Cycle Cycle 9 Revision 0 Revision Reload Safety Analysis for 1105% OLTP 05% OL TP Page 4-3 boundaries based on these endpoints endpoints can then be determined determined using the generic shape shape generating function from Reference Reference 10. Analyses have been performed performed to support support operation operation for both nominal, nominal, and reduced reduced feedwater feedwater temperature temperature conditions (both FFTR and FHOOS).

acceptance criteria for the BSP endpoints The STAIF acceptance endpoints are global decay ratios < 0.85, and, decay ratios::; and channel decay ratios regional and channel < 0.80. Endpoints ratios::; Endpoints for the BSP regions provided provided in Table 4.4 4.4 have global global decay ratios < 0.85, and regional and channel ratios::; ratios < 0.80.

channel decay ratios::;

, I

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AREVA NP Inc.

e 'I ANP-2863(NP)

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Browns Ferry Unit 1 Cycle 9 : Revision Revision 0 Reload Safety Safety Analysis for 105% OLTP OLTP Page 4-4

'Page 4-4 Table 4.1 Fuel- and Plant-Related Plant-Related Uncertainties for Uncertainties for Safety Limit MCPR Analyses MCPR Analyses Parameter Parameter , Uncertainty Uncertainty Fuel-RelatedUncertainties Fuel-Related Uncertainties I

) I

'I'

~ I

,j' I Plant-RelatedUncertainties Plant-Related Uncertainties

, L Feedwater flow rate Feedwater rate 1.8%

1 Feedwater temperature Feedwater temperature 0.8%

I '

Core pressure pressure 0.7%

I, '

I'.' I, 1: ; Total core flow rate 1\ ~

1 TLo TLO 2.5%

" SLO 6.0%

" I '

~, i

[ ]I.

AREVA Np"nc:

NP Inc.

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Browns Ferry Unit I1 Cycle 9 Browns Ferry 'Revision Revision 0 Reload Safety Analysis for 105% OL OLTP TP Page 4-5 Page Table 4.2 Results Results Summary for for Safety Safety Limit MCPR Analyses Analyses Percentage Percentage SLMCPR of Rods in Boiling Boiling Transition TLO - 1.09 TLO-1.09 0.086 SLO -1.11

- 1.11 0.069

, I I.

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Browns Ferry Unit 1 Cycle 9

.Browns Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP .. Page 4-6 Table 4.3 OPRM Setpoints Setpoints OPRM OLMCPR OLMCPR OPRM OLMCPR OLMCPR Setpoint 5etpoint (SS)

(55) . (2PT) 1.05 1.18 1.15 1.15 1.06 1.06 1.20 1.20 1.17 1.17 1.07 1.07 1.22 1.22 1.19 1.19 1.08 1.08 1.24 1.24 1.21 1.09 1.09 1.26 1.26 1.23 1.23

., . 1.10 1.28 1.25 1.25 1.11 1.11 1.30 1.30 1.26 1.26

~ 1.12 1.32 1.32 1.29 1.29

j

)

i 1.13 1.34

.1.34 1.31

\'. t 1.14 1.14 1.36 1.36 1.33 1.33 1.15 1.39 .

1.39 1.35 1.35

i Rated Power Power

. Off-Rated OLMCPR as OLMCPRas Acceptance Acceptance OLMCPR in described in Criteria Criteria at 45% Flow Section 8.0 5ection 8;0 AREVA NP Inc~

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Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 Revision Reload, Reload Safety Analysis for 105%

105% OL TP OLTP Page 4-7 Table 4.4 BSP Endpoints Endpoints for Browns Ferry Unit I1 Cycle 9 Feedwater Feedwater Temperature Temperature

. , Operation End Point Power Power Flow Flow Mode Mode Region Designation Designation (% rated) '(%

(% rated)

,: .t Nominal Nominal Scram Scram IA 65.22 41.50

'~ I Nominal Nominal Scram IB 43.88 29.00

~~ ;

Nominal Nominal Controlled Controlled IIA 73.46 50.00

!I i entry I

I ~

i;

,I' Nominal Nominal, Controlled Controlled liB 1iB 30.72 29.00 29.00" ji' entry FFTR/

FFTRI Scram IA 69.63 46.00 46.00

1, FHOOS FHOOS FFTR/

FFTRI Scram IB 40.00 29.00 FHOOS FHOOS FFTR/ '

FFTRI Controlled Controlled IIA 73.46 50.00 FHOOS entry I'

FFTR/

FFTR/' Controlled Controlled liB 1iB 30.72 29.00

, I FHOOS

'FHOOS entry I.

~!

AREVA AREVA NP Inc.

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. r*.'

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Browns Ferry Unit 1 Cycle 9 .*Revision Revision 0 Reload Safety Safety Analysis for 105% OLTP OLTP Page 4-8 200 200 175 I-150 150 C/l I

.!1 Cl

"'C 125 125 c -

l CD -

'+-

0 100 100 r-Q)

..c E

l 75 zZ - r-50 r-r- - r-25 - t--

- r-0 I I I I I ~ ~II

'~ , .0 .1.1 .2 .3 .4 .5 .6 .7 .8 .9 1.0 1.1 1.2 1.3 1.3 1.4 1.5 1.5 1.6 1.6 Radial Power Radial Power Peaking Figure 4.1 Core-wide Core-wide Radial Power Histogram for Limiting Limiting TLO Exposure

, (

.' i

.[ .

JI I i'

AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105%

105% OLOLTPTP Page 4-9 200 200 175 175 150 150 en Q)

=acC 125 125

3

~

M m

'+-

0 100 100 Q)

..c - -

E 75 75

~

Z -

50 50 r- f-25 25 f-0

.0 .1

.1 FFf IT

.2 .3 .4

.4 rllT-f r-f

.5 .6 .7 .8 .9 1.0 1.0 1.1 1.2 1.2 1.3 1.4 1.4 . 1.5 1.6 1.6 Peaking Radial Power Peaking Figure 4.2 Core-wide Core-wide Radial Radial Power Histogram for Limiting SLO Exposure I.~

, \

~ I I

I' AREVA AREVA NP Inc. Inc..

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Browns Ferry Unit 1 Cycle 9 .' Revision Revision 0 Reload Safety Analysis for 105% OL OLTP TP Page5-1 Page 5-1 .

5.0 Anticipated Operational Occurrences Operational Occurrences This section describes the analyses performed performed toto determine determine the power- and flow-dependent.

flow-dependent MCPR MCPR operating operating limits for base case operation.

operation.

COTRANSA2 (Reference COTRANSA2 XCOBRA'-T (Reference 13), XCOBRA (Reference 12), XCOBRA-T XCOBRA (Reference (Reference 14), and and CASMO-4/MICROBURN-B2 (Reference CASMO-4/MICROBURN-B2 (Reference 15) are the major codes used in the thermal limits limits analyses as described analyses in the AREVA described inthe THERMEX methodology report (Reference 14)

AREVA THERMEX 14) and neutronics methodology (Reference 15). COTRANSA2 is a system transient methodoiogy report (Reference transient simulation code, which includes includes an axial one-dimensional one-dimensional neutronics neutronics model that captures the effects effects of associated with the systemtransients.

power shifts associated axial power XCOBRA-T is a transient thermal-system transients. XCOBRA-T hydraulics code used in the analysis analysis of thermal margins for the limiting fuel assembly. XCOBRA is used in steady-state steady-state analyses.

analyses. The SPCB critical power correlation* (References 5 and 31) 31) is (i I

" , used to evaluate evaluate the thermal margin of the ATRIUM-10ATRIUM~10 and GE14 GE14 fuel. The application of the the SPCB correlation correlation to GE14 fuel follows the indirectindirect process process described Reference 6. Fuel described in Reference pellet-to-cladding gap conductance pellet-to-cladding conductance values values are based on RODEX2 (Reference (Reference 16) calculations calculations for the BF1 Cycle 9 core.

5.1 System Transients System Transients i' ~"

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

Analyses have been performed to determine determine power-dependent power-dependent MCPR MCPR limits thatthat protect

.1 '

operation throughout operation throughout the power/flow domain the powerlflow domain depicted depicted in.in, Figure 1.1.

1.1.

At BF1, BF1, direct scram on turbine stop valve (TSV) position and turbine control valve (TCV) fast I .

closure areare bypassed bypassed at power levels less than 30% of rated (Pbypass). Scram will occur when the (Pbypass). Se:ram the

, I

'( , high pressure pressure or high neutron flux scram setpoint is reached. Reference 17 indicates indicates that MCPR MCPR reached. Reference I

, limits only need to be. be, monitored at power levels greater greater than or equalequal to 25% of rated, which is

'I:

" the lowest power analyzed analyzed for this report.

expo~urefor The limiting exposure for rated power pressurization pressurization transients transients is typically at end offull of full power

. (EOFP) when the control .

rods are fully withdrawn. To provide areflillywithdrawn.

additional margin provide additional margin to the operating operating limits earlier I.imits earlier in the cycle, analyses were also performed performed to establish limits at a near establish operating limits near.

AREVA has submitted Reference 31 to the NRC. Reference 31 addresses Condition Report 2007-AREVA has submitted Reference 3Uo the NRC. Reference 31 addresses Condition Report 2007-regarding the CPR test loop power error. Analyses incorporate 3653 regarding incorporate the revised ATRIUM-10 additive additive constants. Reference constants. Reference 31 31 was was approved approved byby the the NRC NRC inin the final safety evaluation the, final of Reference evaiuation of Reference 42.

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Browns Ferry Unit 1 Cycle 9 I Revision Revision 0

.Reload Safety Analysis for*1 Reload Safety for 105% OLTP 05% OL TP . Page 5-2 Page 5-2 end-of-cycle (NEOC) end-of-cycle (NEOG) core average exposure MWd/MTU. Analyses were performed exposure of 28,285 MWd/MTU. performed at cycle exposures exposures prior to NEOC to ensure ensure that the operating operating limits provide provide the necessary protection. end-of-cycle licensing basis (EOGlB) protection. The end-of-cycle (EOCLB) analysis was performed at EOFP + 15 average exposure EFPD (core average exposure of 31 31,523 MWd/MTU). Analyses were also performed

,523 MWd/MTU). performed to support extended cycle operation with final feedwater extended feedwater temperature temperature reduction reduction (FFTR) and power coastdown. The licensing licensing basis exposures used to develop the neutronics inputs to the transient neutronics inputs analyses analyses are presented iriTable in'Table 5.1.

5.1.

transients assumed that one of the lowest All pressurization transients lowest setpoint main steam relief valves valves (MSRV)

(MSRV) was inoperable.

inoperable. The basis supports operation operation with 1 MSRV out-of-service.

out-of-service.

temperature of less than 10°F from the nominal Reductions in feedwater temperature nominal feedwater feedwater temperature temperature variation of +/-10 and variation +/-1 0 psipsi in dome dome pressure pressure are considered considered base case operation, operation, not an EOOS EOOS .

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

'\ ,

ranges.

,I :-

i FFTR is used to extend extend rated power operationoperation by decreasing decreasing the feedwater feedwater temperature. The The temperature reduction is a function of power with the maximum amount of feedwater temperature decrease maximum decrease 65 0 F (55°F + 1Q°F of 65°F 10°F bias) at ratedrated power. Analyses Analyses were performed performed to support combined

,I FFTR/Coastdown FFTR/Coastdown operation operation to a core average exposureexposure of 32,198 MWd/MTU.

MWd/MTU. The analyses analyses

,r were performed performed with the limiting feedwater and dome pressure allowable pressure conditions in the allowable

, ranges..

ranges pressurization transient results are sensitive to scram System pressurization scram speed assumptions. To take take advantage of average scram advantage scram speeds speeds faster than those associated associated with the Technical Specifications requirements, scram speed-dependent

, . Specifications speed-dependent MCPRPMGPRp limits are provided. The* The nominal

,I ,

scram speed (NSS) insertioninsertion times and the Technical Technical Specifications Specifications scram speed (TSSS)

., insertion insertion times used in the analyses are presented presented in Table 5.2. The NSS MCPR MCPRPp limits can can only

. .I

, I be applied if the scram scram speed test results meet the. the NSS insertion insertion times. System transient transient

. analyses were .

performed performed to establish MCPRp MCPRp limits for both NSS NSS and TSSS insertion insertion times.

. Technical Specifications (Reference 17) allow for operation with up to 13 Specifications (Reference 13 "slow" and i1 stuck control rod. One additional control rod is. assumed to fail .

to scram. Conservative adjustrneQts adjustments to the NSS and TSSS scram speeds were made to the analysis analysis inputs to appropriately account for appropriately account these effects on scram reactivity. ForcasesFor cases below below 30% power, the results are relatively relatively AREVA NP Inc.

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Browns Ferry Unit 1 Cycle 9 Revision 0

.\ Reload Safety Analysis for 105% OLTP 105% OL TP Page 5-3 I""

,; I insensitive to scram speed, and only TSSS analyses performed. At 30% power analyses are performed. power (Pbypass),

(Pbypass), .

analyses analyses were performed, performed, both with andand without bypass bypass of the direct direct scram scram function, resulting in i,

an operating limits step change.

5.1.1 Reiection No Bypass (LRNB)

Load Rejection (LRNB) .

Load rejection causes a fast closure of the turbine control valves. The resulting compression compression wave travels through the steam lines into the vessel and createscreates a rapid pressurization.

pressurization. The The increase in pressure causes a decrease decrease in core voids, which in turn causes a rapid increase increase in power. Fast closure of the turbine turbine control control valves also causes a reactor scram and RPT. TurbineTurbine bypass system operation, which also mitigates mitigates the consequences consequences of the event, is not credited.

credited.

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

LRNB LRNB analyses assume the power load unbalance unbalance (PLU)

(PLU) is inoperable inoperable for power levels levels less than 50% of rated. The LRNB sequence

'. t" sequence of events is different different than the standard event when the the PLU is inoperable. Instead Instead of a fast closure, the TCVs close in servo servo mode and there is no no direct scram on TCV closure. The power and pressurepressure excursion continues until the highhigh pressure pressure scram occurs.

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

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

shown in Figures 5.1-5.3.

5.1.2 Turbine Trip No Bypass (TTNB)

A turbine trip A turbine trip event event can can be initiated as a result of several different different signals. The initiating signal causes the TSV to close in order to prevent damagedamage to the turbine. The TSV closure creates creates a compression wave traveling traveling through the steam lines into the vessel causing causing a rapid pressurization. The increase pressurization. decrease in core voids, which in turn increase in pressure results in a decrease

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

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Browns Ferry Unit 1 Cycle 9 Revision 0 Revision 105% OL Reload Safety Analysis for 105% OLTP TP Page Page 5-45-4 mitigates the consequences consequences of the event,is event, is not credited. The excursion excursion of the core power power duedue to the void collapse is terminated terminated primarily by the reactor scramscram and revoiding revoiding of the core.

In addition to closing the TSV, a signal signal is also sent to close the TCV in fast mode; mode. TheThe closure of the TCV are very similar to those resulting from a TSV closure.

consequences of a fast closure consequences The main difference difference is the time required to close the valves. While the TCV full str~ke stroke closure closure greater than that of the TSV (0.150 sec compared time is greater compared to 0.100 sec), the initial position of the the TCV is dependent dependent on the initial steam flow. 'At At rated power power and lower, the initial position positi9n of thethe TCV is such that the closure time is less than that of the 1SV. TSV. However, the TCV closure closure' characteristics characteristics are nonlinear such that the resulting core core. pressurization and boCPR ACPR may not always bound those of the slower TSV closure.

closure.

Analyses were performed Analyseswere performed demonstrating demonstrating that the TTNB event event is equivalent to or bound by the' the t ;'

~,' , LRNB event; therefore, the thermal limits established LRNBevent; established for the LRNB will also protectprotect against the the

TTNB event.

5.1.3 Feedwater Controller Failure (FWCF)

Feedwater (FWCF)

The increase in feedwater feedwater flow due due to a failure of the feedwater feedwater control control system to maximum maximum

~: I demand demand results in an increase in the water level and a decrease temperature-at decrease in the coolant temperature ,at I,'

j, the core inlet.7The inlet. The increase in core inlet subcooling causes causes an increase in core power. As the the

feedwater flow continues continues at maximum demand, demand, the water level continues continues to rise and eventually eventually i' '

, reaches reaches the high water water level trip setpoint. The initial initial water level is conservatively conservatively assumed to be be

"! I

at the low level normal at normal operating range to delay the hi~h-Ievel high-level trip and maximize maximize the core inlet inlet '

subcooling resulting from the FWCF. The high water level trip causes the turbine stop valves to subcooling close in order to prevent damage damage to the turbine from exces~ive excessive liquid inventory in the steam line.

Valve closure creates a compression wave wave traveling back to the core, causing void col,lapse collapse and subsequent rapid power excursion. The subsequent The clo~ure closure of of the turbine stop valves also initiates initiates a reactor, reactor scram and an RPT. In addition to the turbine stop valve closure, the turbine control control valves also,also ' '

, close in the fast closure closure mode. Because Because of the partially closed initial position of the co'ntrol control

') :

, valves, they will typically typically close faster than than the stop valves and control control the pressurization pressurization portion of the event. However, TCV closure characteristics are nonlinear so closure characteristics so' that that the resulting core

", pressurization and ~CPR pressurization ACPR results may not always always bound those of the the 510we~

slower TSV closure at rated power power (steam flow increases increases above cI05ure)~ The iimitihgofTCV, above rated before fast TCV closure). limiting of TCV, or '

, AREVA AREVA NP Inc.

ANP-2863(NP)

ANP-2863{NP}

Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Reload Safety Analysis Analysis for 105% OLTP for 105% OLTP Page 5":5 5-5 operating conditions, was used in the FWCF analyses, based on TSV closure, for the initial operating analyses. The turbine bypass valves are assumed sensitivity analyses. assumed operable and provide some provide some pressure pressure relief. The core power mitigated in part by pressure relief, but the primary power excursion is mitigate'd termination of the event are reactor scram and revoiding of the core.

mechanisms for termination mechanisms FWCF analyses were performed power/flow conditions to support generation performed for a range of power/flow generation of the thermal limits. Tables 5.5 and 5.6 present the base case limiting FWCF analysis FWCF transient 8:nalysis generate the NEOC and EOClB results used to generate EOCLB operating operating limits for both TSSS and NSS NSS insertion times. Figures 5.4 - 5.6 show the, the responses responses of various reactor reactor and plant parameters*

parameters, during the FWCF FWCF eventevent initiated at 100% power and 105% of rated core flow with TSSS 100% of rated power insertion times.

5.1.4 Loss of Feedwater loss Feedwater Heating Heating t'

'\, . The loss of feedwater feedwater heating heating (LFWH) analysis supports an assumed (lFWH) event analysis 1001F decrease assumed 100°F decrease in h' ;

Ii,

" temperature. The result is an increase feedwater temperature.

the feedwater increase in core inlet subcooling, subcooling, which reduces reduces

'I voids, thereby increasing core power thereby increasing shifting axial power distribution power and ,shifting toward the bottom of .

distribution'toward

.~ !

the core. AsAs a result Of of the axial power increased core power, voids begin power shift and increased begin to build up in

.I I, the bottom region of the core, actingacting as negative feedback to the increased increased subcooling effect.

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

overcome the increase

'i.

I' ! increase in The increase accommodated by the pressure control system via the TCVs or in steam flow is accommodated

j I, ,.

the turbine bypass bypass valves, so no pr~ssurization occurs. A cycle-specific no pressurization cycle-specific analysis performed analysis was performed in accordance Reference 18 methodology accordance with the Reference methodology to determine determine the change change in MCPR MCPR for the the, event. The LFWH presented in Table 5.7.

lFWH results are presented 5.7 ..

5.1.5 5.1,5 Control Control Rod Withdrawal Error Withdrawal Error withdrawal error (CRWE) transient is an inadvertent The control rod withdrawal initiated inadvertent reactor operator initiated withdrawal of a control increases local power and core thermal power, control rod. This withdrawal increases

'I':

lowering the core MCPR. The CRWE transient is typically terminated by control CRWE transient blocks control rod blocks I

initiated initiated by the rod block monitor (RBM). (RBM). The CRWE event event was analyzed assuming no xenon

.~ .' and allowing credible instrumentation out-of-service in the rod instrumentation out-of-service rod block monitor (RBM)

(RBM) system. The, The iI' analysis.

further assumes assumes that the plant could be operating thaUhe' operating

. in either an A or B sequence sequence control .

AREVA AREVA NP Inc.

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Browns Ferry Unit 1. I Cycle 9 , Revision Revision 0 Safety Analysis for 105%

Reload Safety 105% OL OLTPTP Page Page 5-6 5-6 rod red pattern.

pattern. The rated pewer power CRWE results are shown shewn in Table 5.8 for fer the analytical unfiltered unfiltered RBM high pewer setpoint values ef power setpeint of 107%

107% to. to 117%.

117%. At all intermediate intermediate and lewer lower pewer power setpeint setpoint values, the MCPR MCPRPp values for fer ATRIUM-10 ATRIUM-10 and GE14 fuel beund bound er or are equal to to. the CRWECRWE MCPR values. AnalysisAnalysis results indicate indicate standard filtered RBM setpeint setpoint reductions reductiens are '

supported.

supperted. Analyses demenstrate demonstrate that the 1% 1% strain strain and centerline melt criteria are met met ferfor beth both

, ATRIUM-10 ATRIUM-10 and GE14 fuel, fer for the LHGRLHGR limitslimits and their asseciated associated multipliers presented presented in Sections 8.2 and 8.3. Recemmended Recommended operabilityeperability requirements requirements supporting unblocked CRWE supperting unblecked eperatien operation are shownshewn in Table 5.9, based on en the SLMCPR values presented presented in Sectien Section 4.2.

5.2 Slow Flow Flow Runup Analysis Flow-dependent MCPR and LHGR limits are established Flew-dependent established to. to suppert support eperatien operation at eff-rated off-rated cerecore flow conditions. Limits are based flew cenditiens. based en on the CPR and heat heat flux changes experienced experienced by the fuel during slow flewflow excursiens.

excursions. The slew slow flew flow excursien excursion eventevent assumes recirculation flow assumes recirculatien flew control centrel system failure such that cere core flew flow increases increases slewlyslowly toto. the maximum flow flew physically attainable attainable by

, the equipment (107% (107%ef of rated core cere flow).

flew). An uncontrolled uncentrelled increase flow creates the increase in flew potential thepetential for fer a significant significant increase in core cere power pewer and heat heat flux. A censervatively conservatively steep flow flew runup runu'p path was used in the analysis. Analyses were perfermed performed to. to suppert support operation eperatien in all the EOOS EOOS

, scenarios.

scenaries.

MCPRff limits are determined MCPR determined for both ATRIUM-10,and fer beth ATRIUM-10 and GE14 fuel. XCOBRA is used used to to. calculate the change in critical power ratio.

critical pewer ratio during a two-loop twe-Ieep flewflow runup to to. the maximum maximum flow flew rate. The The MCPRff limit is set so.

MCPR so an increase increase in cere core pewer, power, resulting resulting from frem the maximum increase in cere core flow, assures the TLO safety limit MCPR flew, MCPR is net not violated. Calculations were performed vielated. Calculatiens perfermed over ever a range ofef initial flow flew rates to.to determine corresponding MCPR values causing the limiting determine the cerrespending limiting assembly assembly to to. be be atat the safety limit the safety MCPR fer limit MCPR for the highhigh flow flew condition cenditien at the end ef of the flowflow

'j ( excursion.

excursien.

" ' Analysis results are 'presented presented in Table 5.10. MCPRf MCPRf limits providing. required pret~ctien the required previding ,the protection are presented in Table 8.7. MCPR MCPRff limits are applicable applicable for fer all exposures.

expesures.

~ Flow runup analyses were performed Flew perfermed with CASMO-4/MICROBURN-B2 CASMO-4/MICROBURN-B2 to to. determine flow- flew-dependent LHGR dependent multipliers (LHGRFACf)

LHGR multipliers (LHGRFACf ) fer for ATRIUM-10 ATRIUM":10 fuel. The analysis assumes analysis assumes' recirculation flow increases recirculatien ,flew slowly aleng increases slewly along the the limiting rod line tethe to the maximum flew flow physically physically attainable by the equipment. A series

, attainable. series ef of flew flow excursion excursien analyses were were perfermed performed at several

'. AREVA NP Inc.

Inc..

ANP-2863(NP)

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Browns Ferry Unit 1 I Cycle 9 Revision 00 105% OL Reload Safety Analysis for 105% OLTP TP Page 5-7 5-7 exposures throughout the cycle, starting exposures from different startirig from power/~ow conditions.

different initial power/flow conditions. Xenon is assumed to remain constant during assumed during the event. LHGRFACf LHGRFACf multipliers multipliers are established to provide provide centerline melt and overstraining of the cladding during a flow runup.

protection against fuel centerline LHGRFACff multipliers are presented in Table 8.11.

LHGRFAC 8.11. A process process consistent with the GNF thermal-mechanical methodology mechanical methodology was used to determine flow-dependent flow':'dependent LHGR multipliers (LHGRFACf)f )

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

off-rated core flow conditions, are presented The maximum flow during a flow excursionexcursion in single-loop operation operation is much less than the the maximum flow during two-loop operation. Therefore, the flow-dependent flow-dependent MCPR limits and LHGR multipliers multipliers for two-loop operation operation are applicable for SLO., SLO.

5.3 Equipment Out-of-Service Scenarios Equipment Out-of-Service Scenarios The equipment out-of-service (EOOS) equipment out-of-service (EOOS) scenarios scenarios supported for BF1 Cycle 9 operation are are shown in Table 1.1.1.1. The EOOS scenarios supported supported are:

- Turbine bypass valves out-of-service (TBVOOS) valvesout-of-service (TBVOOS)

, ** EOC recirculation recirculation pump trip out-of-service (EOC-RPT-OOS) out-of-service (EOC-RPT-OOS)

I'* ;

, ** Feedwater heaters Feedwater out-of-service (FHOOS) heaters out-of-service

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

~: : ** Combined EOC-RPT-OOS Combined EOC-RPT -005 and TBVOOS TBVOOS r' ** Combined EOC-RPT-OOS Combined EOC-RPT FHOOS

-005 and FHOOS"

" I ** Combined EOC-RPT-OOS Combined EOC-RPT PLUOOS

-005 and PLUOOS

- Combined Combined TBVOOS and FHOOS FHOOS

- Combined Combined TBVOOS and PLUOOS PLUOOS

- Combined Combined FHOOS and PLUOOS PLUOOS

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

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

, t

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

L, .

i: ** Combined Combined TBVOOS, FHOOS, and PLUOOS PLUOOS

. 'I ** Combined EOC-RPT-OOS, Combined EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS PLUOOS

Single-loop operation (SLO) - recirculation Single-loop operation (SLO) - recirculation loop out-of-service out-of-service

'i "

The base case thermal limits support operation operation with 1 MSRV out-of-service, up to MSRV out-of-service, to 2 TIPOOS TIPOOS (or

'1 equivalent n~mber the equivalent number of TIP channels), and up to 50% 50% of the LPRMs out~of-service: .The the, LPRMs out-of-service. The analyses presented in this section also include these EOOS

. analyses protected by.the EOOS conditions protected by the base base case limits. No further discussion discussion for these EOOS conditions conditions is presented presented in this section.

section ..

. AREVA NPlnc.

NP Inc.

..ANP-2863(NP)

" ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 BroWns Revision 0 Reload Safety Safety Analysis for 105%

105% OLTP OLTP Page 5-8 5.3.1 TBVOOS TBVOOS The effect effect of operation with TBVOOS is a reduction in the system pressure pressure relief capacity, which makes the pressurization pressurization events more severe. While the base case LRNB and TTNB

. ' events analyzed assuming the events are analyzed the turbine bypass valves out-of-service, operation operation with TBVOOS TBVOOS has an adverseadverse effect on the FWCF event. Analyses of the FWCF event event with TBVOOS were performed to establish the TBVOOS TBVOOS TBVOOS operating operating limits.

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

(

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

FWCF events assuming EOC-RPT-OOS.

IJ' 5.3.3

5.3.3 FHOOS FHOOS The FHOOS scenario assumes The assumes a feedwatertemperature feedwater temperature reduction of 65°F (55°F + 10°Fbias) 10°F bias) at .

j j 1 :.

rated power and steam flow. The The effect effect of reduced feedwater feedwater temperature temperature is anan increase increase in core core l

f .

> ; inlet subcooling, changing changing axial power shape shape and core void fraction. Additionally, steam flow for

~

a given power level decreases given power decreases because because more power power is required to increase increase coolant enthalpy enthalpy to saturated saturated conditions.

conditions. Generally, LRNBLRNB and TTNB events are less severe with FHOOS FHOOS conditions conditions due to the decrease decrease in steam flow relative to nominal conditions. FWCF events events with with, FHOOS conditions are generally worse due to a larger change in inlet subcooling subcooling and core power prior to the pressurization pressurization phase of the event.

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

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Browns Ferry Unit 1 Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP . Page 5-9 5-9 5.3.4 PLUOOS PLUOOS The PLU device in normal operation is assumed to not function below below 50% power. PLUOOS PLUOOS is assumed to mean mean the PLU device device does not function for any power level, and does not initiateinitiate fast TCV closure. The following PLUOOS scenario assumed for the load reject event.

scenario was assumed

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

EOC-RPT

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

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

Analyses were performed performed for LRNB events assuming assuming PLUOOS.

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

previously discussed

. I 5.3.6 Combined EOC-RPT-OOS and FHOOS Combined EOC-RPT-OOS FHOOS FWCF analyses with both EOC-RPT-OOS FWCFanalyses EOC-RPT-OOS and FHOOS performed. Operating limits for FHOOS were performed.

this combined EOOS scenario scenario were established using these FWCF results and results results

' previously previously discussed. EOC-RPT-OOS and FHOOS discussed. Separate EOC-RPT-OOS FHOOS combined limits are not needed needed for operation beyond the EOCLBEOCLB exposure exposure since a FW temperature temperature reduction is included included to attain the additional cycle extension extension to the FFTR/coastdown FFTRIcoastdown exposure.

5.3.7 Combined EOC-RPT-OOS Combined EOC-RPT-OOS and PLUOOSPLUOOS LRNB analyses with both EOC-RPT-OOS LRNBanalyses EOC-RPT-OOS and PLUOOS were performed. performed. Operating Operating limits forfor this combined EOOS scenario scenario were established using using these LRNB results and results previously discussed.

previously 5.3.8 Combined TBVOOS and FHOOS FHOOS FWCF analyses FWCF analyses with both TBVOOS and FHOOS performed. Operating FHOOS were performed. Operating limits for this this combined combined EOOS scenario were established established using these these FWCF.results and results previously previously AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% TP OLTP 105% OL , Page 5-105-10 discussed. Separate discussed. Separate TBVOOS and FHOOS combined limits are not needed needed for operation operat:ion beyond the EOCLB beyond EOClB exposure since a FWtemperature reduction is included to attain FW temperature reduction attain the the additional cycle cycle extension to the FFTR/coastdown FFTRlcoastdown exposure.

\

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

PlUOOS . No additional analyses are required to construct analyses construct MCPR MCPRpp operating limits for TBVOOS TBVOOS and PlUOOS PLUOOS since TBVOOS TBVOOS and PlUOOS PLUOOS are independent independent EOOS EOOS conditions conditions (TBVOOS only impacts FWCF events; PlUOOS PLUOOS only impacts lRNBLRNB events) events)...

5.3.10 Combined FHOOS and PlUOOSPLUOOS LRNB analyses lRNB analyses with both FHOOS and PlUOOS PLUOOS were performed. Operating limits for this performed. Operating this combined combined EOOS EOOS scenario were established LRNB results and results previously established using these lRNB discussed.

discussed. Separate Separate FHOOS and and PlUOOS PLUOOS combined limits are not neededneeded for operation operation beyond the EOClB EOCLB exposure since a FW temperature temperature reduction reduction is included to attain attain the the "i 1

,I { additional additional cycle cycle extension to the FFTR/coastdown FFTRlcoastdown exposure.

exposure.

.i 5.3.11 EOC-RPT-OOS, Combined EOC-RPT -OOS, TBVOOS, and FHOOS FHOOS analyses with EOC-RPT-OOS, FWCF analyses EOC-RPT-OOS, TBVOOS, and FHOOS were performed. performed. Operating limitslimits

'/

/. for t~is this combined combined EOOS established using these FWCF results and results .

EOOS scenario were established Separate EOC-RPT-OOS, previously discussed. Separate EOC-RPT-OOS, TBVOOS, and FHOOS combined limits are not FHOOS combined needed for operation ,beyond beyond the.EOClB the EOCLB exposure exposure since a FW temperature temperature reduction ,is is .'

j\ ;

included to attain the additional cycle extension to the FFTRlcoastdown FFTR/coastdown exposure.

.., 5.3.12 EOC-RPT-OOS, Combined EOC-RPT TBVOOS, and PlUOOS

-OOS, TBVOOS. PLUOOS i !

were established to support operation Limits were EOC-RPT-OOS, operation with EOC-RPT -OOS; TBVOOS, and PLUOOS. No .

,l additional analyses analyses are required to construct MCPRpp operating limits for EOC-RPT construct MCPR EOC-RPT-OOS,

-OOS; TBVOOS, and PlUOOS PLUOOS since since TBVOOS and PlUOOSPLUOOS are independent independent EOOS conditions .' .

EOOS conditions (TBVOOS (TBVOOS only impacts FWCF FWCF events; PLUOOS PlUOOS only impacts lRNB LRNB events).

5.3.13 Combined Combined EOC-RPT .;06s, FHOOS, and PlUOOS EOC-RPT-OOS, PLUOOS LRNB lRNB analyses with EOC~RPT,OOS, analyses with EOC-RPT-OOS, FHOOS, and PLUOOS were performed.

and PlUOOS performed. Operating limits Operating limits EOOS scenario were established

. for this combined EOOS established using these lRNB result~'

LRNB results and results AREVA AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Unit 11 Cycle 9 Revision 0 Reload Safety Analysis for 105% OLTP OLTP . Page 5-11 5-11 previously discussed.

previously discussed. Separate EOC-RPT-OOS, FHOOS, and PLUOOS Separate EOC-RPT-OOS, PLUOOS combined limits are not needed for operation needed operation beyond beyond the EOCLB exposure since a FW temperature temperature reduction reduction is included to attain the additional included additional cycle extension extension to the FFTR/coastdown FFTRlcoastdown exposure.

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

exposure.

5.3.15 Combined EOC-RPT-OOS, TBVOOS.

Combined EOC-RPT-OOS. TBVOOS, FHOOS.

FHOOS, and PLUOOS PLUOOS Limits were established operation with EOC-RPT established to support operatiqn EOC-RPT-OOS, TBVOOS, FHOOS, and

-OOS, TBVOOS, PLUOOS. No additional analyses analyses are required to construct MCPRp MCPRp operating operating limits for <

EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS EOC-RPT-OOS, PLUOOS since TBVOOS and PLUOOS PLUOOS are*are independent EOOS conditions (TBVOOS only impacts independent impacts FWCF events; events; PLUOOS PLUOOS only impacts impacts LRNB events). Separate EOC-RPT-OOS, TBVOOS, FHOOS, and PLUOOS combined Separate EOC-RPT-OOS, limits combined limits are not needed needed for operation operation beyond the EOCLB exposure exposure since a FW temperature reduction reduction is included to attain the additional cycle extension extension to the FFTRlcoastdown FFTR/coastdown exposure.

5.3.16 Single-Loop Operation Single-Loop In SLO, the two-loop operation ACPRs ilCPRs and LHGRFAC multipliers multipliers remain remain applicable. The onlyonly impacts on the MCPR, LHGR, and MAPLHGRMAPLHGR limits for SLO are an increase increase of 0.02 in the the SLMCPR as discussed discussed in Section 4.2, and the application application of an SLO MAPLHGR MAPLHGR multiplier discussed in Section 8.3. The net result is a 0.02 increase increase in the base case MCPR MCPRpp limits and a decrease in the MAPLHGR decrease MAPLHGR limit. The same situation is true for the EOOS scenarios. Adding Adding 0.02 to the corresponding corresponding two-loop operation EOOS MCPR MCPRpp limits results in SLO MCPR MCPRpp limits limits for the EOOS conditions. The TLO EOOS tHGRFAC LHGRFAC multipliers remain applicable applicable in SLO.

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Browns Ferry Unit 1.

Browns I Cycle 9 Revision Revision 0 Reload Reload Safety Analysis Analysis for 105% OL OLTP TP 5-12 Page 5-12 5.4 Licensing Power Shape Licensing Power Shape The licensing axial power profile used by AREVA analyses bounds the AREVA for the plant transient analyses the projected end of full power projected power axial power profile. The conservative licensing axial power profile conservative licensing profile generated at the EOCLB core average exposure generated exposure of 3131,523

,523 MWd/MTU MWd/MTU is given in TableTable 5.11.

5.11.

Cycle 9 operation is considered to be i~ compliance when:

in compliance

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

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

EOCLB.

Ifthe criteria If criteria cannot be fully met (Le.,

(i.e., not all 7 nodes are at a higher power power than the licensing licensing profile), the licensing licensing basis maynevertheless may nevertheless remain valid but further further assessment win will be be .

required.

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

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

POWERPLEX-Ill*.

the power profile comparison should be done without incorporating Note that the instrument incorporating instrument.

updates to the axial profile because because the updated updated power is not used in the core monitoring monitoring

~ , .

I system to accumulate accumulate assembly assembly burnups.

, , 1

/. ,

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.

countries. .' ". " .

. AREVA AREVA NP Inc.

l.

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I Cycle 9 Browns Ferry Unit 1 . Revision Revision 0 Reload Safety Analysis for 105%

105% OL TP .

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

(MWd/MTU) Comments Comments 14,285 14,285 Beginning of cycle cycle

28,285 Break point for exposure-dependent MCPR dependent MCPRpp limits limits

" ' (NEOC) 31,523 Design basis rod patterns patterns to EOFP + 15 15 EFPD (EOCLB)

(EOCLB) 32,198 Maximum licensing corecore .

~

exposure:"- including FFTR exposure

. ,I , '* /Coastdown

\ 23,458 (16,178)* Cycle 8 EOC (nominal value) 22,925 (15,645)* .

22,925 Cycle 8 EOC (short window) 23,813 (16,533)* Cycle 8 EOC (long window)

~ .

Corresponding Cycle 8 cycle exposure.

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Browns Ferry Unit 1 Cycle Cycle 9 . Revision Revision 0 Reload Reload Safety Analysis for 105%

105% OL OLTPTP 5-14 Page 5-14 Table 5.2 Scram Speed Insertion Times Insertion Times TSSS NSS NSS Control Rod Analytical Analytical Position Time Time Time (notch)

(notch) (sec) (sec)

(full-out) 48 (full-out) 0.00 0.00 48 0.20 0.20 46 0.46 0.421 36 1.09 1.09 0.991 26 1.86 1.62 I .

. 6 3.50 3.04 0o (full-in)

(full-in) 4.0 3.5 3.5

,f*

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ANP-2863{NP)

ANP-2863(NP)

Browns Ferry Unit 1 Cycle Cycle 9 . Revision Revision 0 Reload Safety Analysis for 105%

105% OL OLTP TP Page 5-15 5-15 Table 5.3 NEOC Base Case LRNB Table LRNB Transient Results Power ATRIUM-10 ATRIUM-10 ATRIUM-10 ATRIUM-10 GE14 GE14

(% rated)

(% ACPR

~CPR HFR ACPR

~CPR TSSS Insertion Times TSSS Insertion Times 100 0.35 1.25 1.25 0.34 0.34 90 0.36 1.26 1.26 0.34

\

I 75 0.35 1.24 1.24 0.33 0.33 l' '.50 50 0.76 1.68 1.68 0.75 0.75 40 0.83 1.77 1.77 0.82 0.82 30 . 0.95 1.87 1.87 . 0.94 0.94 25 at > 50%F below Pbypa, Pbypass 1.02 1.94 1.94 1.01

1.01

" 0.89 1.71 0.86 25 at s< 50%F below Pbypass Pbypass 1.71

,, . NSS Insertion Insertion Times Times

\

100 0.33 1.23 1.23 0.31 90 0.34 1.24 1.24 0.32 75 75 0.33 1.23 1.23 0.31 .

50 0.75 1.68 1.68 0.74 0.74 40 0.83 1.76 1.76 0.82 po ._

AREVA Inc.

AREVA NP Inc:,

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 . . Revision 0 Reload Safety Analysis for 105%

105% OL OLTPTP Page 5-16 5-16 Table 5.4 EOCLB Base Case LRNB LRNB

. Transient Transient Results Results Power ATRIUM-10 ATRIUM-10 GE14 Power ATRIUM-10 ATRIUM-10 GE14

(% rated)

(% ACPR ilCPR HFR ACPR ilCPR Insertion Times TSSS Insertion 100 100 0.36 1.30 . 0.35 90 0.37 1.31 0.36

0.36

" i 75 75 0.37 0.37 1.30 1.30 0.36 0.36 50 0.78 1.70 0.76 40 0.84 1.79 0.83 30 30 0.96 1.91 0.95 25 at >> 50%F 50%F below Pbypass below Pbypass 1.02 1.02 1.97 1.01 25 at s< 50%F below PPbypass bypass 0.89 1.73 0.86 Insertion Times NSS Insertion Times 100 0.34 1.28 0.33 90 0.35 1.29 0.34 75 75 0.35

.0.35 1.29 . 0.34

r 50 0.77 1.69 0.76 40 0.83 1.79 0.82 AREVA NP Inc.

!1 ',.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Revision 00 Reload Safety Analysis for 105%

105% OLOLTPTP . Page 5-17 5-17 Table 5.5 NEOC Base Case FWCF FWCF .

Results Transient Results Power ATRIUM-10 ATRIUM-10 ATRIUM-10 ATRIUM-10 GE14 GE14

(% rated) rated) ilCPR ACPR HFR ilCPR ACPR Insertion Times TSSS Insertion 100 0.44 0.44 1.37 1.37 0.43 0.43 90 0.48 0.48 1.42 1.42 0.48 75 75 0.54 1.47 1.47 0.55

, t 65 65 0.59 1.52 1.52 0.62 60 0.62 0.62 1.55 1.55 0.65 50 50 0.71 1.64 1.64 .0.72 40 0.85 1.78 1.78 0.85 30 30 1.07 1.07 1.97 1.97 1.07 1.07 30 at > 50%F below below Pbypass Pbypass 1.47 1.47 2.53 1.56 1.56

1.44

.1.44 2.36 1.56 1.56 30 at at:S< 50%F below PPbypass bypass 50%F below 25 at > 50%F below Pbypass PbypaSS 1.68 1.68 2.71 1.77 1.77 25 at at:S< 50%F below PPbypass bypass 1.63 1.63 2.46 1.74 1.74 Insertion Times NSS Insertion 100 100 0.40 0.40 1.35 1.35 0.40 90 90 0.45 0.45 1.40 1.40 0.45 75 75 0.51 1.45 1.45 0.52 65 65 0.57 0.57 1.51 0.60 60 60 0.60 0.60 1.54 1.54 0.63 50 50 0.69 0.69 1.63 1.63 0.71 40 40 0.83 0.83 1.78 1.78 0.83 30 30 1.06 1.06 1.97 1.97 1.06 1.06 AREVA NP Inc.

AREVA

ANP-2863(NP}

ANP-2863(NP)

Browns Ferry Browns Ferry Unit Unit 1 Cycle 9 . Revision 0 Reload Safety Analysis for 105% OLTP OLTP Page 5-18 Page 5-18 Table 5.6 EOCLB Base Case FWCFFWCF Transient Results Transient Results

ATRIUM-b Power Power ATRIUM-10 ATRIUM-10 ATRIUM-10 ATRIUM-10 GE14 GE14

(% rated) rated) ACPR

~CPR HFR ACPR

~CPR Insertion Times TSSS Insertion 100 100 0.44 0.44 1.37 1.37 0.43 90 90 0.48 0.48 1.46 1.46 0.48 75 75 0.54 1.47 1.47 0.55 65 65 0.59 1.52 1.52 0.62 60 60 0.62 1.55 1.55 0.65 50 50 0.71 1.64 1.64 0.72 40 0.85 1.78 1.78 0.85 30 30 1.07 1.07 1.97 1.97 1.07 1.07 30 at > 50%F below below Pbypass Pbypass 1.47 2.53 2.53 1.56 1.56 30 at s;< 50%F below Pbypass Pbypass 1.44 2.50 2.50 1.56 1.56 I 25 at at>> 50%F below below Pbypass Pbypass 1.68 2.71 1.77 1.77

1 .

.' 25 at s;< 50%F below Pbypass Pbypass 1.63 2.46 1.74 1.74

,J. !

Insertion Times NSS Insertion 100 0.40 1.35 0.40 90 0.45 1.42 0.45 75 0.51 1.45 0.52 65 0.57 1.51 0.60

I 60 0.60 1.54 9.

0.63 63 '

50 0.69 1.63 0.71 40 0.83 1.78 0.83 30 1.06 1.06 1.97 1.06 1.06

. AREVA NP Inc.

ANP-2863(NP)

I Cycle 9 Browns Ferry Unit 1 . Revision 0 Revision Reload Safety Analysis for 105%

105% OLTP OLTP . . Page Page 5-19 5-19 Table. 5.7 Loss Table.S.7 loss of Feedwater Feedwater Heating Heating Transient Analysis Results Analysis Results Power ATRIUM-10/GE14 ATRIUM-10/GE14

(% rated) rated) flCPR ACPR 100 100 0.10 0.10 90 90 0.10 0.10 80 80 0.11 0.11 70 70 0.12 0.12 60 60 0.13

.0.13 50 0.15 0.15 An 40 0.18 0.18

.;1 , 30 30 0.22 25 0.26 0.26 l'

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AREVA NP Inc.

NPlnc.

ANP-2863(NP)

Browns Ferry Unit Unit 1 Cycle 9 . Revision Revision 0 Reload Safety Reload Safety Analysis for 105% OLTP OLTP 5-20

,"~ Page 5,:,20 Table 5.8 Control Rod Withdrawal Error Withdrawal Error ACPR Results L\CPR Results Analytical RBM RBM Setpoint Setpoint (without filter) ACPR*

b.CPR* CRWE CRWE M

(%) MCPRt MCPRt

" . 107 0.28 1.37 1.37

" I I

)

. 111 0.30 1.39 1.39

.' (,

114 0.32 1.41

. f)

Ji 117 0.35 1.44 1.44

. l

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'. ~'. \ *t Results areJor ATRIUM-10 or GE14 fuel in the core:

are for the most limiting of the ATRIUM-10

,t For rated power power and a 1.09 SLMC SLMCPR.PR.

NP Inc.

AREVA NPlnc.

ANP-2863(NP)

Unit 1 Cycle 9 Browns Ferry Unit Revision 0 Revision Reload Safety Safety Analysis for 105% OLTP OLTP Page 5-21 Table 5.9 RBM Operability Requirements Operability Requirements Applicable Applicable Thermal Thermal Power Power . ATRIUM-10/GE14 ATRIUM-10/GE14

(% rated) MCPR MCPR 1.86 1.86 TLO TLO

__27% and << 90%1.6TL

~ 27% and 90% 1.90 SLO

J i I' 1.90 SLO

~. 1

~90%

>90% 1.47 TLO TLO

, ~ . (

AREVA Inc.

AREVA NP Inc:

.. ANP-2863(NP}

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Browns Ferry Unit 1I Cycle 9 Browns FerrY Revision 0 Revision Reload Reload Safety Analysis for 105% OL OLTP TP Page 5-22 Table 5.10 Flow-Dependent Flow-Dependent MCPR Results Results Core ATRIUM-10 GE14 Flow Limiting Limiting

(% rated) MCPR MCPR 30 1.58 1.57 40 1.48 1.45 50 1.43 1.40 60 1.39 1.35 70 1.32 1.32 80 1.27 1.26 90 1.23 1.22 100 1.19 1.17 107 1.09 1.09 i' '

I, \

t:

. AREVA AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% OL TP OLTP Page 5-23 Table 5.11 Licensing Table 5.11 Licensing Basis Core Average Average Axial Power Profile Profile State Conditions for State Conditions for Power Shape Shape Evaluation Evaluation Power, MWt 3458.0 Core pressure, psia psi a 1050.1 Inlet subcooling, Btu/Ibm 24.2 Flow, Mlb/hr MIb/hr 107.6 107.6 Control state ARO ARO average exposure Core average 31,523 31,523 (EOCLB),

(EOClB), MWd/MTU Licensing Axial Power Profile Profile (Normalized)

(Normalized)

Node Node Power Power Top 25 0.189 0.189 24 0.590 0.590 j,

23 0.770 0.770 22 0.874 0.874 21 0.935 0.935 20 0.979 0.979 19 1.023 1.023 18 1.076 1.076 I j I 17 17 1;138 1.138 16 1.206 1.206 15 1.264 14 14 1.392 13 1.416 1.416 12 1.407 11 1.370 10 1.315 1.315 9 1.247 1.247 8 1.165 1.165 7 1.077 1.077 6 0.999 5 0.943 4 0.909 3 0.851 2 '0.671 0.671

, Bottom Bottom 1 0.194 0.194 AREVA AREVA NP Inc.

ANP-2863(NP)

ANP-2863(NP}

Browns Ferry Unit 1. 1*Cycle Cycle 9 Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP Page Page 5-24 5-24 500.0,---------------------------------,

Relative Core Power Relative Heat Flux Flux

--- Relative Total Core Flow 400.0 -

Relative Steam Flow Relative Feed Flow 300.0 300.0 -

"tJ Q) c

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(seconds)

Figure 5.1 EOCLB LRNB at 1OOPI105F 100P/105F -- TSSS Key Parameters Parameters AREVA NPNP Inc.

ANP-2863(NP)

Browns Ferry Unit Unit 1I Cycle 9 .. Revision Revision 0 Reload Reload Safety Safety Analysis for 105% OL TP OLTP 5-25 Page 5-25 34.0

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Figure 5.2 EOCLB LRNB at 1IOOP/105F OOP/1 05F --TSSS TSSS Sensed Water Level AREVA NP Inc; Inc.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 , Revision 0 Safety Analysis for 105%

Reload Safety 105% OL OLTP TP Page Page 5-26 5-26 1 300.0..,----------------------------------.

1300o1.o 1250.0 -

1250.0 I' " ---- .... ....

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.0,

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

Figure S.3 5.3 EOCLB LRNB at 10OP/I105F 100P/10SF - TSSS TSSS Vessel Pressures Pressures AREVA NP Inc.

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ANP-2863(NP)

Browns Ferry Unit 1 Cycle Browns Cycle 9 Revision 0 Reload Reload Safety Analysis for 105% 105% OL OLTP TP. 5-27 Page 5-27 500.0.---------------------------------,

Relative Core Power Power Relative Heat Flux Relative Relative Total Core Flow 400.0 -

Relative SteamFlow Steam Flow Relative Feed Flow

,300.0 -

300.0 i, 'U

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.0 5.0 10.0 15.0 20.0 25.0 25.0 30.0 (seconds)

Time (seconds)

Figure 5.4 EOCLB EOCLB. FWCFat FWCF at 1OOPI105F 1OOP/1 05F - TSSS Key Parameters Parameters AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Revision 0 Revision 105% OL Reload Safety Analysis for 105% OLTP TP Page Page 5-28 70.0 c-c:

...o 4)

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Figure 5.5 EOCLB FWCF 1001PI105F - TSSS FWCF at 100P/105F TSSS Sensed Water Level Sensed ,Water

.AREVA AREVA NP Inc.

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Browns Browns Ferry Unit 1 Cycle Cycle 9 . Revision 0 Reload Reload Safety Analysis for 105% OL OLTP TP : Page 5-29 5-29 1 300.0,----------------------------------,

UU.U.ý Vessel Lower Plenum Dome Steam Dome 1250.0 1250.0 -

I. ~

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1200.0-1200.0

,.... J 00

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- -- - - -- -- - - - - - - - - - I N

N N

N 1000.0+-----~-----_r_----__,.-----_r_----_._------l wvv.v 1

.0 5.0 5.0 10.0 10.0 15.0 20.0 25.0 25.0 30.0 Time (seconds)

Time (seconds)

Figure 5.6 EOCLB FWCF at 10OPI1O5F 1OOP/1 05F - TSSS TSSS Vessel Pressures Pressures AREVA NP Inc.

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Revision 0 Revision Reload Safety Analysis for 105%105% OLTP OLTP Page 6-1 6.0 Postulated Postulated Accidents Accidents 6.1 Loss-of-Coolant-Accident (LOCA)

Loss-of-Coolant-Accident (LOCA)

As discussed in Section Section 2, the LOCA models, evaluation, and and results are the same for all threethree units for a full core of ATRIUM-10 ATRIUM-10 fuel. The The limiting ATRIUM-10 ATRIUM-10 LOCA results are for EPU operation and bound 105% 105% OL OLTP TP operation.

operation. The basis for applicability of PCT results from full ATRIUM-10 fuel (based on AREVA cores of ATRIUM-10 AREVA methods) and GE14 fuel (based on GNFmethods)'GNF methods) for a mixed (transition) core is provided in ReferenceReference 39 Appendix A. Thermal-hydraulic Thermal-hydraulic '

characteristics of the GE14 characteristics GEl4 and ATRIUM-10 fuel designs are similar as presented presented in Reference Reference

3. Therefore, the core response during a LOCA will not be significantly significantly different different for a full 'core core of GE14 fuel or a mixed core of GE14 and ATRIUM-10 ATRIUM-10 fuel. In addition, since about 95% of the the reactor system volume is outside the core region, slight changes in core 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, the current GE14 LOCA analysis and resulting licensing PCT currentGE14 I: " and MAPLHGR MAPLHGR limits remain applicable.

1 '

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

forATRIUM.;.10 Limitin~

Limiting Break: ft22 split 0.5 ft Recirculation Pump Discharge Line Recirculation Line Battery (DC)

(DC) power Based on the PCT results in Reference Reference 20 and subsequent subsequent evaluations evaluations to provide provide 10 CFR 50.46 reporting reporting estimates estimates (Reference 40, equally applicable for Unit 1), the current current licensing PCT is provided below. The The MCPR value used in the LOCAanalyses LOCAanalyses is less than the the rated power MCPR limits.

(OF)

Initial PCT (OF) 2007 (Reference 20)

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

(Reference 40)

(Reference CurrentLicensing Current Licensing PCT (OF)(OF) 2002 AREVA AREVA NP Inc.

\ '

ANP-2863(NP)

ANP-2863(NP) ,

Browns Ferry Unit 1 Cycle 9 " Revision Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP Page 6-2 6-2' The peak peak local metal-water reaction for the limiting PCTlattice iocal metal-water PCT lattice design is 1.711.71%. maximum '

%. The maximum core wide metal-water generation) for a full ATRIUM-10 metal-water reaction (for hydrogen generation) ATRIUM-10 core is <1.0%.

<1.0%.

The cycle specific ATRIUM-10 ATRIUM-10 reload fuel PCT was calculated to be 1979°F 1979 0 F (1984°F (1984°F - SOF);

5°F); ,

therefore, in terms of PCT, the limiting neutronic neutronic design design used in Reference Reference 20 remains remains bounding.

bounding.' The peak local metal-water metal-water reaction and total core wide metal-water metal-water reaction were calculated to be 1.72%

calculated 1.72% and < 1.0%,

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

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

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

Note:'

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

ii' Ij The GE14 LOCA analysis results are are presented in References References 21 and 26. No No system, system r' modifications modifications have beenbeen made at BF1 that would invalidate, invalidate the reactor reactor system response response J* assumed in assumed in the GE14 LOCA analysis of record.

6.2 Control ControlRod Drop Drop Accident (CRDA) a Plant startup utilizes a bank position withdrawal withdrawal sequence sequence (BPWS) including including rod worth worth, minimization minimization strategies. CRDA evaluation was performed performed for both A Aand Bsequence B sequence startups startups i

, ,~ ! consistent with the withdrawal withdrawal sequences sequences specified specified by TVA. Approved ApprovedAREVAAREVA genericCRDA generic CRDA i , methodology methodology is described Reference 22. Subsequent calculations' described in Reference calculations havehave shown thethe I

methodology methodology is applicable applicable to fuel modeled with the CASMO4/MICROBURN-B2 CASM04/MICROBURN-B2 code system.

Analysis Analysis results demonstrate demonstrate thethe maximum maximum deposited fuel rod enthalpy deposited fuel enthalpy is less than 280 cal/g;

r, estimated number the estimated number of fuel rods that exceed exceed the fuel damage threshold threshold of 170 170 cal/g is iess less than the number of failed failed rods assumed in FSAR (8S0 (850 rods).

" I I: I Maximum dropped control rod worth, mk Maximum mk , '10.98 10.98 1)- .

Core average Doppler coefficient, Ak/k/°F

~klkloF -10.58

-10.S'8x x 10~6 1076

t Effective delayed Effective delayed neutron neutron fraction ' 0.0052 0.00S2 Four-bundle local Four-bundle local peaking factor 1.391 Maximum deposited deposited fuel rod enthalpy, cal/g 189.5 189.5.

number of rods exceeding Maximum number, 170 cal/g exceeding 170 276 AREVA NP Inc.

l ANP-2863(NP)

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Browns Browns Ferry Ferry Unit Cycle 9 Unit 1 Cycle *. Revision Revision 0 Reload Safety Reload Safety Analysis 105% OLTP Analysis for 105% OLTP Page Page 6-3 6-3

. 6.3 Fuel and Equipment Fuel Equipment Handling Handling Accident Accident The fuel handling handling accident implementing the alternate radiological analysis implementing accident radiological alternate source term (AST) source term as approved approved in Reference 27 in Reference 27 was performed consideration of ATRIUM-10 performed with consideration ATRIUM-10 corecore source source terms. Fuel assembly assembly and inventories used as isotopic inventories and reactor core isotopic as input input to design basis design basis radiological accident radiological accident analyses applicable to all three units analyses are applicable (Reference 27).The number units (Reference number of failed fuel rods for ATRIUM-10 fuel as the ATRIUM-10 forthe as previously provided to TVA previously provided Reference 28 for use in TVA in Reference in unchanged. No other aspect the AST analysis is unchanged. aspectof ATRIUM-10 fuel affects of utilizing the ATRIUM-10 affects the the' current analysis; therefore, current analysis; bounding for Cycle 9.

remains bounding therefore, the AST analysis remains 6.4 Fuel Loading Error Fuel Loading (InfrequentEvent)

Error (Infrequent Event)

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

6.4.1 Mislocated Bundle Mislocated Fuel Bundle performed a bounding fuel mislocation error analysis

, AREVA has performed analysis and has demonstrated continued applicability of the bounding continued bounding -results. considered the impact of a' results. The analysis considered a mislocated assembly against potential mechanisms due to increased potential fuel rod failure mechanisms increased LHGR and offsite dosecriteria (a small fraction of 10 CFR r~duced CPR. Based on the analyses, the offsitedose,criteria reduced 50.67) is conservatively consequence evaluation is not necessary since no rod satisfied. A dose consequence conservatively satisfied.'

approaches the fuel centerline melt or 11%

approaches % strain limits, and less than 0.1 0.1%

% of the fuel rods are experience boiling transition.

expected to experience expected 6.4.2 Misoriented Bundle Misoriented Fuel Bundle performed a bounding fuel assembly misorientation analysis. The analysis was, AREVA has performed was performed assuming that the limiting assembly was loaded in performed in the worst orientation (rotated 1800), while simultaneously producing sufficient power to be on the MCPR operating,li.mitas 180°), operating limit as ifif itit

. were oriented correctly. The analysis demonstrates the small fraction 50.67 offsite :

fraction of 10 CFR 50.670ffsite consequence evaluation is conservatively satisfied. A dose consequence dose criteria is conservatively is not necessary necessary since Inc.

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Browns Ferry Unit 1 Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP Page 6-4 no rod approaches centerline melt or 1 approaches fuel centerline 1%

% strain limits, and less than 0.1%

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

transition.

't:

, I

l'. .

'I AREVA NP Inc:

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Browns Ferry Unit 1 Cycle 9 Revision 0 Revision Reload Safety Analysis Analysis for 105% OL OLTP TP Page Page 7-1 7.0 Special Analyses Special Analyses 7.1 ASME Overpressurization ASME OverpressurizationAnalysis This section describes the maximum overpressurization analyses maximum overpressurization performed to demonstrate analyses performed demonstrate compliance with the ASME Boiler and Pressure Vessel Code. The analysis compliance analysis shows that the the safety/relief valves have sufficient safety/relief performance to prevent sufficient capacity and performance prevent the reactor vessel pressure pressure from reaching the safety limit of 110% 110% of the design pressure.

MSIV MSIV closure, TSV closure, and TCV closure (without bypass) analyses were performed with the AREVA plant simulator simulator code COTRANSA2 COTRANSA2 (Reference (Reference 12)12) for 102% power and both 81% 81%

and 105%

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

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

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

- To support To support operation with 11 MSRVOOS, operation with MSRVOOS, the the plant plant configuration configuration analyzed analyzed assumed that assumed that one of the lowestsetpoint lowest setpoint MSRVsMSRVs was inoperable.

- TSSS insertion times were used.

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

(1055 psig)

.. ; ** A fast MSIV MSIV closure time of 3.0 seconds was used.

- ATWS-RPT setpoint and function were assumed.

The analytical limit ATWS-RPTsetpoint Results Results of the MSIV MSIV closure, TCV closure, and TSV closure overpressurization analyses are overpressurization analyses presented presented in Table 7.1.

7.1. Various reactor plant parameters parameters during the limiting MSIV'closure MSIVclosure event presented in Figures 7.1-7.4.

are presented 7.1'-:"'7.4. The maximum pressure of 1328 psig occurs in the lower pressure 011328 lower plenum. The maximum maximum dome pressure for the same event is 1291 demonstrate 1291 psig. Results demonstrate the maximum vessel pressure pressure limit of 1375 1375 psig and dome dome pressure pressure limit of 1325 1325 psig are not exceeded for any analyses.

exceeded Pressure Pressure results include a 7-psi7-psi increase to bound a bias in the void-quality void-quality correlations.

correlations. The The void-quality bias is further discussed discussed in Reference Reference 32.

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Browns Ferry Unit Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105%

105% OLOLTP TP Page 7-2 7.2 A TWS TWS Event Evaluation Evaluation 7.2.1 ATWS Overpressurization Analysis Overpressurization Analysis This section describes demonstrate that the peak vessel pressure for the performed to demonstrate describes analyses performed the limiting ATWS event is less than the ASME Service Service Level C limit of 120%

120% of the design design pressure pressure (1500 psig). Overpressurization Overpressurization analyses analyses were performed 100% power at both 81%

performed at 100% 81% and 105% flow over the cycle exposure range for both the MSIV closure event and the pressure pressure regulator failure open (PRFO) events. The PRFO event event assumes assumes a step decrease decrease in pressure pressure demand such that the pressure control control system system opens the turbine control and turbine bypass bypass .

valves. Steam flow demand is assumed assumed to increase increase to 125%

125% demand demand (equivalent 152.46% of (equivalent to 152.46%

rated steam flow) allowing a maximum maximum TCV flow of 122.0%

122.0% and a maximum maximum bypass system "flow flow of 25.2%. The system pressure pressure decreases decreases until the low pressure setpoint is reached resulting in the closure of the MSIVs. subsequent pressurization MSIVs. The subsequent pressurization wave wave collapses core voids, thereby increasing core power.

increasing The following assumptions assumptions were made in the analyses.

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

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

inoperable.

- All scram functions were disabled.

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

'1'

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

events:

Analyses presented in Table 7.2. The response of various reactor plant parameters Analyses results are presented parameters during the limiting PRFO eventevent are shown shown in Figures 7.5-7.8. The maximum lower plenum plenum 1403 psig and the maximum pressure is 1403 maximum dome pressure is 1384 1384 psig. The results demonstrate demonstrate that the ATWS maximum vessel pressure limit of 1500 1500 psig is not exceeded.

exceeded.

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

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

AREVA NP Inc.

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Browns Unit 1 Cycle 9 Browns Ferry Unit Revision 0 Reload Reload Safety Analysis for 105% OLOLTP TP Page 7-3 7-3 I

,\

I]

The suppression suppression pool temperature temperature and containment containment pressure pressure limits and the corresponding corresponding licensing values of record (Reference 36) are presented record (Reference presented in the following table. The results are for EPU operation and bound 105% 105% OLTP operation. ,

AREVA NP Inc.

Inc ..

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Browns Ferry Unit 1 Cycle 9 9. ,', Revision Revision 0 Reload Safety Analysis for 105%

105% OLTP OLTP Page 7-4 ATWS A TWS Criteria Limit Licensing Value Value Suppression Suppression pool temperature temperature (OF)

(OF) 281 187.3 187.3 Drywell pressure (psig) 56 48.5 48.5 pressure (psig)

Wetwell pressure 56 30.5 Relative to the 10 Relative 10 CFR 50.46 acceptance acceptance criteria (i.e., PCT and cladding oxidation), the the consequences of an ATWS consequences A TWS event are bound by those of the limiting LOCA event.

7.3 Standby Liquid Control ControlSystem In the event that the control rod scram function becomes incapable of rendering the core in a becomes incapable a shutdown shutdown state, the standby liquid liquid control (SLC) system system is required required to be capable of bringing the the reactor from full power power to a cold shutdown shutdown condition condition at any time in the core life. The Browns Browns

. , , Ferry Unit 1 SLC system is required required to be able to inject 720 ppm naturalnatural boron equivalent at

, 70°F into the reactor coolant. AREVAAREVA has performed performed an analysis,demo':lstrating analysis.demonstrating the SLC system meets the required shutdown capability for the cycle. The analysis was performed performed at a coolant temperature 3660 F, with a boron concentration temperature of 366°F, concentration equivalent equivalent to 720. ppm at 68 720.ppni 0 68°F*. The F*. The temperature 3660 F corresponds temperature of 366°F corresponds to the low pressure permissive low'pressure permissive for the RHR shutdown cooling suction valves, and represents the maximum reactivity condition with soluble boron in reactivity conditionwith'soluble the coolant.

The analysis shows the core to be subcritical subcritical throughout throughout the cycle by at least 2.83%

Ak/k based on the Cycle 8 EOC short window, which is the most limiting exposure i1k1k exposure bound by the the short and long Cycle 8 exposure exposure window.

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

in Reference The spent fuel pool criticality analysis for ATRIUM-10 ATRIUM-10 fuel is presented in Reference.25.

Reference 25. The.

ATRIUM-10 fuel assemblies identified ATRIUM-10 identified for the cycle meet both the new new and spent fuel storage fuel storage requirements.

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

plant.'.

NP Inc.

AREVA NPlnc.

. ANP-2863(NP)

ANP-2863(NP)

Cycle 9 Browns Ferry Unit 1 Cycie 0 Revision O' Revision Reload Safety Analysis for 105%

105% OL OLTPTP Page 7~5 7-5 Table 7.1 ASME Overpressurization ASME Overpressurization Analysis Results*

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

(% (%

(% rated) (psig) (psig)

MSIV closure MSIV 295 125 1328 1291 295 125 1328 1291 (102P/1 05F)

(102P/105F)

MSIV closure 317 317 126 126 1315 1315 1284 1284 (102P/81 F)

TSV closure closure without bypass 553 133 133 1327 1289 1289 (102P/105F)

(1 02P/1 Q5F)

TSV closure closure

.' , without bypass 393 130 130 1310 1280 1280 (102P/81 F)F)

TCV closure without bypass 555 133 133 1327 1289 1289 (1

(1 02P/1 05F)

TCV closure without bypass bypass' 391 130 130 1311 1280 1280 (102P/81F)

(102P/81 F)

Pressure Limit --- --- 1375 1325 1325

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

AREVA Inc..

AREVA NP Inc.*

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Browns Ferry Unit 1 Cycle Cycle 9 Revision Revision 0 Reload Safety Analysis for 105% OLTP 105% OL TP Page Page 7-6 7-6 Table 7.2 ATWS Overpressurization Overpressurization Analysis Results*

Analysis Results*

Maximum Maximum Peak Peak Vessel Maximum Maximum Neutron Neutron Heat Pressure Dome.

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

(% (% rated)

(% rated) (psig) (psig)

MSIV closure, MSIV closure 279 279 140 140 1382 1382 1360 1360 (1OOP/1 05F)

(100P/105F)

MSIV MSIV closure closure 296 296 136 136 1394 1394 1374 1374 (100P/81 (100P/81 F)

PRFO 277 277 152 152 1390 1390 1368 1368 (10OP/105F)

(100P/105F)

PRFO 297 297 145 145 1403 1403 1384 1384 (100 P/81 F)

(100P/81

1 "

Pressure Limit 1500 1500 Limit 1500

Limit

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

(Reference 32}. '

AREVA NP Inc; Inc.

ANP-2863(NP)

, ANP-2863(NP)

Browns Ferry Unit 1I Cycle Cycle 9 Revision 0 Reload Safety Analysis for 105%

105% OL OLTP TP Page 7-7 Page Table 7.3 [

]

I.,

I

~: i I

I t

I AREVA NP NP Inc.

ANP-2863(NP)

Browns Browns Ferry Ferry Unit Unit I1 Cycle Cycle 9 Revision Revision 0 Reload Safety AnalysisAnalysis for 105% 105% OL OLTP TP Page 7-8 Page 7-8 300.0,----,-----------------------------,

Relative Core Power Relative Heat Flux Relative Total Core Flow Relative Steam Flow Relative Feed Flow 200.0 i '

a

....o0 100.0 -F--=--=--=--=--:':;;--=='--=-=--=--=--;O;--~;':'"

Cc Q) 0o

'p Q)

, )

u.

0~

.0 J'

-100.0 - / - - - - - . . , . - - ' - - - - - - r - - - - - - r - ' - - - - - - - - r - - - - - - - r - - - - - - l

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

Figure 7.1 MSIV Closure Overpressurization Overpressurization Event at at 102P1105F 102P/1 OSF - Key Parameters Parameters AREVA NP Inc.

ANP-2863(N P)

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Browns Ferry Unit 1 Cycle 9 Revision Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP Page 7-9 35.0 c-Cc 0

...o Q)

N

..., 30.0 Cc G)

Q)

E

[ ...,...

J L

en

£C

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...,0 25.0

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Q)

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.(12 12)

Q)

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

, . Figure 7.2 MSIV MSIV Closure Overpressurization Overpressurization Event at 102P/105F 102P/1 05F - Sensed Water Level AREVA AREVA NP Inc.

I .

ANP-2863(NP)

Browns Ferry Unit 1 Cycle 9 Revision 0 Revision Reload Safety Analysis Reload Analysis for 105%

105% OL OLTP TP . Page 7-10 7-10

(~ . '\

1350.0.,--------------'-----------------------,

Vessel Lower. Plenum Steam Dome 1300.0 ,,/..., ..........

I - .....

I .... ,

I "

I ,

I "

I ,

1250.0 I '

I

.-... I I "

0

'00 (I,

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1150.0 I I

I I

I 1100.0 I I

I I

1050.0 +--------,-----.,--------.------.--------,---------l

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

Figure 7.3 MSIV Closure Closure Overpressurization Overpressurization Event at 102P/105F 1 02P/1 05F - Vessel Vessel Pressures Pressuresr AREVA AREVA NP Inc.

NPlnc.

ANP-2863(NP)

ANP-2863{NP)

Browns Ferry Unit 1 Cycle Cycle 9 _Revision 0 Reload Reload Safety Analysis for 105% 105% OL TP OLTP 7-11 Page 7-11 1500.0~-------------------------------,

Low Setpt (3) f' . . .'. . . . . . ---.. --.. . . _-.. . . --..-------

......... 1250.0 U

i:

U IV rn -----1

.a E

E

.;:::.. ,"'1/" .... ___ - - - - _______ :

Hioo.o

.0~ ----:,..."',

0 G: I I

IV I o>

I

- 750.0 I I

.~ I Qj a:::: I I

I

~ 500.0 I IV I

-+'

Ul I I

I I

' : 250.0 I I

'. i I

I I

I

~+-----,-----,--~-~.-----.-_ _ _~.-_I_ _~~

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

Figure 7.4 MSIV MSIV Closure Overpressurization Overpressurization Event at 1102P1105F 02P/1 05F - Safety/Relief Safety/Relief Valve Flow Rates Rates AREVA NPlnc~

NP.Inc.

ANP-2863(NP)

ANP-2863(NP}

Browns Browns Ferry Unit Unit 1 Cycle 9 Revision Revision 0 Reload Reload Safety Analysis for 105% OL OLTP TP 7-12 Page 7-12 300.0...----------------------------------,

Relative Core Power Relative Heat Flux Relative Total Core Flow Relative Steam Flow Relative Feed Flow 200.0 "1J

.i**

, ....0 Q) 0::

0 0

....c:C 100.0 Q) 0 CL Q) a..

.0

-100.0-+-_ _ _ _ _- ._ _ _ _ _- ._ _ _ _ _ _. -_ _ _ _ _-.-_ _ _ _ _---1

.0 10.0 20.0 30.0 30,0 40.0 50.0 Time (seconds) 7.5 PRFO ATWS Figure 7.5 ATWS Overpressurization Overpressurization Event at 1OOPI81F - Key Parameters 100P/81F Parameters AREVA NP Inc. Inc~

.ANP-2863(NP)

ANP-2863(NP}

Browns Ferry Unit 1 Cycle 9 .Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP Page Page 7-13 7-13 80.0 c:

c-o 0

II)

N N

....t: 60.0 II)

E

J

....'-rn

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....c II)

.0 "C

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-20.0

.0 10.0 20.0 30.0 40.0 50.0 Time (seconds)

(seconds)

Figure 7.6 PRFO A TWS Overpressurization ATWS Overpressurization Event at IOOPI81F 100P/81F - Sensed Water Level AREVA AREVA NP Inc.

ANP-2863(NP)

ANP-2863{NP}

Browns Ferry Unit 1 Cycle 9 .

BroiNns Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP Page Page 7-14 7-14 1600.0'T"'"----------------------------------,

Vessel Lower Plenum Steam Dome 1400.0 0 1200.0

'iii 0-C,,

en U1)

Q)

L-

J en en ....

IL Q)

L- 1000.0 " I a.. , I

, I

\ I

" \ II

\ I

\ J

) ( 800.0 .... ~

'I I j.

"'.. 600.0 +-------.-------r----------,.-------'---~------_l

.0 10.0* 20.0 30.0 40.0 50.0 Time ((seconds) seconds)

Figure 7.7 7.7 PRFO ATWS Overpressurization Event at Overpressurization Event'at 10PI81F 100P/81F - Vessel Pressures Pressures AREVA AREVA NP Inc.

t~ , ANP-2863(NP)

Browns Ferry Unit Browns Unit 1.

1.Cycle Cycle 9 Revision Revision 00

,. Reload Safety Reload Safety Analysis for 105% OL OLTP TP . Page*7-15 Page 7-15

I

1 '

1IDuu.o 5 I0 0 . 0 . , . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,

Low Setpt (3) (3)

Med Setpt J41)

---Hf.h_.Seqtp.L-O ----

1250.0 -

E v 1000.0-

\

i 0 LL_

4) a I' > 750.0-

. I~

I 0)

E .500.0-2) 250.0 -

.o+-_

-A _ _ _ _.-_ _~_ _._-----._---~-~-~-~-~

.0 10.0 20.0 20.0 30.0 30.0 40.0 50.0 50.0 (seconds)

Time (seconds)

\' ,j

~ i

. 'I Figure 7.8 PRFOPRFO ATWS Overpressurization Event at A TWS Overpressurization at 100PI81F Safety/Relief Valve 1OOP/81 F - Safety/Relief Valve Flow Rates Flow Rates

. AREVA AREVA NP NP Inc.

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Browns Ferry Unit Unit 1 Cycle 9 . Revision 0 Reload Safety Analysis for 105% OLTP OLTP Page 8-1 8.0 Operating Limits and COLR Input Input 8.1 MCPR MCPR Limits Determination of MCPR limits are based on analyses of the limiting abnormal operational .

Determination transients transients (AOTs). The MCPR operating limits are established MCPR operating established so that less than 0.1% bfthe 0.1% of the fuel rods in the core are expected expected to experience experience boiling transition transition during an AOT initiated from rated or off-rated conditions and are based on the Technical Specifications two-loop operation*

Technical Specifications operation SLMCPR of 1.09 1.09 and a single-loop operation SLMCPR of 1.11. 1.11. Exposure-dependent Exposure-dependent MCPR MCPR limits were established to support operation from BOC to near end-of-cycle (NEOC), NEOC to end-of-cycle (NEOC).

end-of-cycle licensing basis (EOCLB) end-of-cycle (EOCLB) and combined FFTR/Coastdown.

FFTR/Coastdown. MCPR limits are established to support base established base case operation scenarios presented operation and the EOOS scenarios presented in Table 1.1.1.1.

Two-loop operation MCPR MCPRpp limits for ATRIUM-10 and GE14fuei GEl4 fuel are presented presented in Tables 8. 1-TablesB,1-8.6 for base case operation and the EOOS conditions. Limits ar~ are presented presented for nominal nominal scram speed (NSS) and Technical Specification Specification scram speed (TSSS) insertion times for the exposure exposure ranges considered.

considered. Tables 8.1 and 8.2 present the MCPR MCPRpp limits for the BOC BOC to NEOC exposure exposure range. Tables 8.3 and 8.4 present present the MCPR MCPRPp limits applicable for the BOG BOC to EOCLB exposure exposure range. Tables 8.5 and 8.6 present present the MCPRp MCPRp limits for FFTRICoastdown FFTR/Coastdown operation.

MCPRp limits for single-loop operation are MCPRp are 0.02 higher for all cases. Comparisons Comparisons of the limiting limiting AOT analysis results and the MCPRplimitsfor MCPRp limits for ATRIUM-10 ATRIUM';10 and GE14 f~el fuel are presented presented in Appendix A.

MCPRff limits protect against MCPR against fuel flJel failures during a postulated postulated slow flow excurs,ion.

excursion. ATRIUM-10 ATRIUM-10 and GEI4 GE14 fuel limits are presented in Table 8.7 and are applicable for all cycle exposures exposures and identified in Table 1.1.

EOOS conditions identified 1.1.

8.2 LHGR Limits The LHGR LHGR limits for ATRIUM-10 presented in Table 8.8.

ATRIUM-10 are presented 8.8. The LHGR limits-for limitsJor GE14 fuel are presented presented in Reference Reference 29. Power- and flow-dependent flow-dependent multipliers (LHGRFACp (LHGRFAC p and LHGRFACf)

LHGRFACf ) are applied applied directly directly to the LHGR limits to protect against fuel melting and fuell11elting overstraining of the cladding during overstraining during an AOT.

LHGRFACpp multipliers for ATRIUM-10 LHGRFAC ATRIUM-10 fuel are determined determined using using the heatflux heat flux ratio results from from,

. the transient analyses. TheLHGRFAC The LHGRFACpp and LHGRFAC LHGRFACff multipliers were de'veloped developed inma in*a manner manner consistent with the GNF GNF thermal-mechanical thermal-mechanical methodology methodology for GE14 fuel.

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Unit11 Cycle 9 Browns Ferry Unit Revision 0 Reload Safety Safety Analysis for 105%

105% OLOLTP TP Page 8-2 8-2 LHGRFACp LHGRFACp multipliers multipliers were established established to support operation at all cycle exposures for both NSS and TSSS TSSS insertion times and for the EOOS conditions conditions identified in Table 1.1 1.1 with and without TBVOOS. LHGRFACpp limits are presented TBVOOS. LHGRFAC presented in Tables 8.9 and 8.10 for ATRIUM-10 ATRIUM-10 and GE14 fuel, respectively. Comparisons of the limiting results and the LHGRFACp LHGRFAC p limits are are presented in Appendix Appendix A.

LHGRFACf multipliers are established LHGRFACfmultipliers established to provide provide protection against against fuel centerline melt and overstraining of the cladding during a postulated overstraining postulated slow flow excursion.

excursion. LHGRFAC LHGRFACff limits are presented in Table 8.11 and 8.12 for ATRIUM-10 presented ATRIUM-10 and GE14 fuel, respectively. LHGRFAC LHGRFACff applicable for all cycle exposures multipliers are applicable exposures and EOOS EOOS conditions conditions identified in Table 1.1.

1.1.

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

presented in References 8.3 MAPLHGR Limits

.MAPLHGR ATRIUM-10 MAPLHGR limits are discussed ATRIUM-10 MAPLHGR discussed in Reference Reference 20. The TLO operation limits are presented inin Table 8.13. For operation operation in SLO, a multiplier of 0.85 must be applied to the TLOTLO

, , MAPLHGR limits. Power MAPLHGR Power and flow dependent dependent MAPFAC setdowns are not required; therefore, I,

MAPFAC=1.0.

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

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Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% OLTP 105% OL TP Page 8-3 Table 8.1 8.1 MCPR MCPRpp Limits for NSS Insertion NSS Insertion Times Times BOC to NEOC*

BOCto NEOC*

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

(% Fuel Fuel 100.0 1.49 1.49 1.49 90.0

90.0 1.55 1.55 1.55 50.0 1.78 1.80 1.80 50.0 1.84 1.83 1.83 Base case 40.0 1.92 1.92 1.92 operation operation 30.0 2.15 2.15 2.15 30.0 at > 50%F . 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at <s 50%F 2.53 2.65 .

25.0 at 50%F 3.01 3.03 25.0 at >> 50%F 3.35 3.35 3.35 30.0 at <s 50%F 2.71 2.83 25.0 at ~~50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86~~

2.86 30.0 at <s 50%F 2.53 2.65 25.0 at > 50%F 2.67 2.76 25.0 at 25.0 at >> 50%F 50%F 2.90 3.00 3.00 30.0 at s< 50%F 2.62 2.75 25.0 at s< 50%F 25;0 50%F 2.84 2.96
~~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 of TIP channels), and up to 50% of the LPRMs out:-of-service.~~
out-of-service. For single-loop operation, operation, MCPRPp limits will be 0.02 MCPR 0.02 higher. .
AREVA NP Inc.
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Browns Ferry Unit 1 Cycle 9 Revision 0 Revision Reload Safety Safety Analysis for 105% OLTP OLTP Page 8-4 8-4 Table 8.1 MCPRMCPRpp Limits for NSS Insertion Times NSS Insertion Times BOC to NEOC BOCto NEOC (Continued)
(Continued)
MCPRp '
MCPRp Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel 100.0 100.0 1.49 1.49 1.49 90.0 1.55 1.55 1.55 50.0 --
50.0 1.89 1.87 1.87 40.0 1.92 1.92 1.92 PLUOOS 30.0 2.15 2.15 2.15 30.0 at > 50%F 2.56 2.65 2.65 25.0 at > 50%F 2.77 2.86 30.0 at s< 50%F 2.53 2.65 2.65 25.0 at s< 50%F 2.72 2.83 100.0 100.0 1.52 1.52 1.52 90.0 1.58 1.58 1.58 50.0 ---
50.0 1.84. 1.83 1.83 EOC-RPT-OOS EOC-RPT -005 40.0 1.96 1.96 1.96 and TBVOOS 30.0 2.19 2.19 2.19 30.0 at > 50%F 3.01 3.03 3.03 25.0 at > 50%F 3.35 3.35 3.35 30.0 at 5s 50%F 2.71 2.83 25.0 at 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 3.00 30.0 at <s 50%F 2.62 2.75 25.0 at ~~50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 30.0 at <s 50%F 50%F 2.53 2.65 25.0 at s< 50%F 50%F 2.72 . 2.83 AREVA NP NP Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
~~Browns Ferry Unit 1I Cycle 9 Revision Revision 0 Reload Safety Analysis Reload Analysis for 105%~~
~~105% OL OLTP TP Page Page 8-5 8-5 Table 8.1 MCPR MCPRpp Limits for NSS Insertion NSS Insertion Times Times BOC to BOCto NEOC NEOC (Continued)~~
~~(Continued)~~
~~MCPRpp MCPR Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%of rated)~~
~~(% Fuel Fuel 100.0 100~0 1.55 1.55 1.54 90.0 1.61 1.61 1.61 1;61 50.0 ...~~
~~50.0 --- ---~~
50.0 1.87 1.87 1.90 TBVOOS 40.0 2.03 2.04 and FHOOS 30.0 2.27 2.27 30.0 at> 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 30.0 at <S 50%F 2.82 2.95 25.0 at 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 3.35 30.0 at <s 50%F 2.71 2.83 25.0 at5 at <50%F s 50%F ' 3.04 3.17 3.17 100.0 100.0 1.52 1.51 90.0 1.59 1.58 1.58 50.0 --
~~50.0 50~0 1.89 1.87 1'.87 FHOOS 40.0 2.00 2.01 and PLUOOS 30.0 30.0, 2.24 2:24 2.24 '~~
~~30.0 at > 50%F 2.67 2.76 at > 50%F 25.0 at> 2.90 3.00 30.0 at <s 50%F 2.62~~
~~'2.62 2.75 25.0 at ~~50%F 3.13 3.17 3.17~~~~
, 25.0 at >>50%F 50%F 3.47 3.47 30.0 at <S 50%F 2.82 2.95 25.0 at ~~50%F 30.0 3.01 3.03 25.0 25.0 at > 50%F 50%F 3.35 3.35~~
~~< 50%F 30.0 at !5: 2.71 2.83 2.83 25.0 at !5:~~
~~25.0 50%F~~
~~<50%F 3.04 3.17 3.17 100.0 100.0 1.52 1..52 1.51 90.0 1.59 1.58 1.58 50.0 --.. ---~~
50.0 1.89 1.87 1.87 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 40.0 2.00 2.00 2.01 2.01 FHOOS, 30.0 2.24 30.0 2.24 2.24 and PLUOOS 30.0 at > 50%F 2.67 i ' 30.0 at > 50%F 2.67 2.76 2.76
~~, 25.0 at > 50%F 2.90 3.00 3.00~~
~~< 50%F 30.0 at !5: 2.62 2.62' 2.75 2:75~~
,, 25.0 < 50%F 25.0 at !5: 2.84 2.96 2.96 100.0 100.0 1.55 1.54 1.54 90.0 1.61 1.61 50.0 --
50.0 1.89 1.90 1.90 TBVOOS, 40.0 2.03 2.04 40.0 2.03 2.04 FHOOS, 30.0 2.27 30.0 2.27 2.27 and PLUOOS 30.0 at > 50%F 3.13 30.0 at > 50%F 3.13 3.17 3.17 25.0 at > 50%F , 3.47 3.47 3.47 30.0 < 50%F 30.0 at !5: 2.82 2.95 2.95 I '
~~25.0 at !5:~~
~~< 50%F 3.20 3.35 "~~
~~3.35 100.0 100.0 1.55 1.54 1.54~~
~~, 90.0 1.61 1.61 0 .0 550.0 ---~~
~~EOC-RPT-OOS, EOC-RPT~OOS, 50.0 1.89 1.90 1.90 TBVOOS, 40.0 2.03 2.04 '~~
2.04 FHOOS, 30.0 2.27 2.27 and and PLUOOS PLUOOS 30.0 at > 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 3.47
~~" : 30.0 at s5 50%F ' 2.82 2.95 2.95~~
~~\ 25.0 at !5:< 50%F 3.20 3.35 3.35 AREVA NP NP Inc.~~
~~\ '~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Ferry Ferry Unit Unit 1 Cycle 9 Revision 0 Reload Safety Safety Analysis for 105% OLTP OLTP Page 8-7 8-7 Table 8.2 MCPRp MCPRp Limits for for Insertion Times TSSS Insertion Times BOC toto NEOC*
NEOC*
~~MCPRp MCPRp Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 .~~
~~Condition (%of rated)~~
~~(% Fuel Fuel Fuel~~
\
100.0 100.0 1.53 1.52 1.52 90.0 1.58 1.58 1.58 50.0 ' 1.80 1.81 50.0 1.85 1.84 1.84 Base case 40.0 1.94 1.94 1.94 operation 30.0 2.16 2.16 .
~~2.16 30.0 at> 50%F at >50%F 2.56 2.65 2.65~~
~~. 25.0 at > 50%F 2.77 . 2.86 2.86 30.0 at s< 50%F 2.53 2.65 2.65 25.0 at s< 50%F 2.72 2.83 100.0~~
~~. 100.0 1.56 1.55 1.55 90.0 1.62 1.61 50.0 50.0 --- ---~~
50.0 1.85 1.85 1.85 40.0 1.98 1.97 1.97 TBVOOS 30.0 2.21 2.20 2.20 30.0 at > 50%F 3.01 3.03 3.03 25.0 at :>> 50%F 3.35 3.35, 3.35'
'I: 30.0 at S< 50%F 2.71 2.83 25.0 at s< 50%F 3.04 3.17 3.17 100.0 100.0 1.53 1.53 1.52 1.52 90.0 1.58 1.58 .
~~1.58~~
~~, I 50.0 1.80 1.81~~
(' I -50.0 50.0 1.85 1.85 1.84 1.84 EOC-RPT-OOS 40.0 1.94 1.94 1.94 EOC-RPT-OOS 30.0 2.16 2.16 2.16 t,
30.0 at > 50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86 2.86 30.0 at <s 50%F 2.53 .2.65
~~2.65 25.0 at ~~50%F 2.67 . 2.76~~~~
,i.
25.0 at->
at> 50%F '2.90
'2.90 3.00 3.00 30.0 at < s 50%F 2.62 2.75 25.0 at < s 50%F 2.84 2.96
Limits support operation operation with any combination combination of 1 MSRVOOS; MSRVOOS,ý up to 22'TIPOOS TIPOOS (or the equivalent equivalent number of TIP channels), and up to 50% of the LPRMs LPRMs out-of-service.
out~of-service. For single-loop single-loop operation, operation, MCPRpp limits will be 0.02 higher. "
MCPR . '
AREVA NPlnc.
AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Revision
.Reload Safety Safety Analysis for 105% OLTP for*105% OLTP 8-8 Page 8-8 Table 8.2 MCPRMCPRpp Limits for TSSS Insertion TSSS Insertion TimesTimes BOC to BOCto NEOCNEOC (Continued)
(Continued)
MCPRp MCPRp Operating Operating Power ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel Fuel 100.0 100.0 1.53 1.52 1.52 90.0 -
1.58 1.58 1.58 50.0 --
50.0 1.89 1.87 1.87 40.0 1.94 1.94 1.94 PLUOOS 30.0 2.16
~.16 2.16 2.16 30.0 at > 50%F 2.56 2.65 2.65 25.0 at > 50%F 2.77 2.86 2.86 30.0 at s< 50%F 2.53 2.65 2.65 25.0 at s< 50%F 2.72 2.83 2.83 100.0 100;0 1.56 1.55 1.55 90.0 1.62 1.61 50.0 ---
50.0 1.85 1.85 1.85 1.85 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.98 1.97 1.97 and TBVOOS 30.0 2.21 2.20 2.20 30.0 at > 50%F 3.01 3.01 3.03 25.0 at >> 50%F 3.35 3.35 30.0 at S< 50%F 2.71 2.83 2.83 25.0 at S< 50%F 3.04 3.17 3.17 100.0 100.0 1.56 1.54 1.54 90.0 1.61 1.61 1.60 1.60 50.0 --
50.0 1.86 1.89 1.89 EOC-RPT-OOS EOC-RPT -OOS 40.0 2.01 2.02 2.02 and FHOOS FHOOS 30.0 2.25 2.25 2.25 30.0 at > 50%F 2.67 2.76 2.76 25.0 at >> 50%F 2.90 3.00 3.00 30.0 at s< 50%F 2.62 . 2.75 2.75 25.0 at s< 50%F 2.84 2.96 2.96 100.0 100.0 1.53 1.52 1.52 90.0 1.58 1.58 1.58 50.0 --
50.0 1.89 1.87 1.87 EOC-RPT-OOS EOC-RPT -OOS 40.0 1.94 1.94 1.94 and PLUOOS PLUOOS 30.0 2.16 2.16 2.16 30.0 at >> 50%F . 2.56 2.65 2.65 25.0 at.>
at> 50%F 2.77 2.86 30.0 at s< 50%F 2.53 2.65 2.65 25.0 at s< 50%F 2.72 2.83 2.83 AREVA NP Inc.
NP Inc.,
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105%
105% OLTP OLTP Page 8-9 Table 8.2 MCPRpMCPRp Limits forfor Times Insertion Times TSSS Insertion BOC to NEOC BOCtoNEOC (Continued)
(Continued)
MCPRPp MCPR Operating Operating Power ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel 100.0 100.0 1.59 1.57 1.57 90.0 1.64 1.63 1.63 50.0 --
. 1.89 50.0 1.89 1.92 1.92 TBVOOS 40.0 2.05 2.05 and FHOOS FHOOS 30.0 2.29 2.29 30.0 at > 50%F 3.13 3.17 3.17 25.0 at > 50%F 50%F 3.47 3.47 at,< 50%F 30.0 at.S 2.82 2.95 25.0 < 50%F 25.0 at S 3.20 3.35 100.0 100.0 1.56 1.56 1.55 1.55 90.0 1.62 1.62 1.61 50.0 --
50.0 1.89 1.89 1.87 1.87 TBVOOS 40.0 1.98 1.98 1.97 1.97 and PLUOOS 30.0 2.21 2.20 30.0 at > 50%F 50%F 3.01 3.03 25.0 at > 50%F 50%F 3.35 3.35 5 50%F 30.0 at S 2.71 2.83 at:S 25.0 at <50%F 50%F 3.04 3.17 3.17 100.0 100.0 1.56 1.56 1.54 1.54 90.0 1.61 1.61 1.60 1.60 50.0 --
50.0 1.89 1.89 1.89 1.89 FHOOS 40.0 2.01 2.02 and PLUOOS 30.0 2.25 2.25 30.0 at > 50%F 50%F 2.67 2.76 25.0 at > 50%F 50%F 2.90 3.00
< 50%F 30.0 at S 50%F 2.62 2.75
< 50%F 25.0 at S 2.84 2.96 100.0 100.0 1.59 1.59 1.57 1.57 90.0 90.0 1.64 1.64 1.63 1.63 50.0 --
50.0 1.89 1.89 1.92 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 2.05 2.05 40.0 2.05 2.05 TBVOOS, FHOOS 30.0 30.0 2.29 2.29 and FHOOS
> 50%F 30.0 at :> 50%F 3.13 3.17 3.17 25.0 at > 50%F 50%F 3.47 3.47
< 50%F 30.0 at S 50%F 2.82 2.95 25.0 at S
< 50%F 3.20 3.35 AREVA Inc.
AREVA NP Inc:
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Browns Ferry Unit Cycle 9 Unit 11 Cycle Revision Revision 0 I, ;. Reload Safety Reload Safety Analysis Analysis for for 105%
105% OLTP OLTP . ; Page Page 8-10 8-10
~~I, "~~
~r : 8.2 MCPRp Table 8.2 Table MCPRp Limits Limits for for Ii, \I I; .. TSSS Insertion Times TSSS .Insertion Times I',I, BOC to NEOC BOCtoNEOC
':, f
.(Continued)
(Continued)
MCPRp MCPRp Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition Condition (%
(% of rated) Fuel Fuel 100:0 100:0 1.56 1.56 1.55 1.55 90.0 1.62 1.62 1.61 1.61 50.0 50.0 , --- ---
50.0 1.89 1.89 1.87 1.87 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.98 1.98*
1.97 40.0 1.97 j: TBVOOS, 30.0 2.21 30.0 2.21 2.20 l' . and PLUOOS 30.0 at > 50%F 3.01 I', 30.0 at > 50%F 3.01 3.03
.. , 25.0 at >> 50%F 3.35 3.35 3.35*
i, 30.0 at <s 50%F 2.71 2.83
L
~~'I,: .1 25.0 at ~~50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00~~~~
3.00 30.0 at <s 50%F 2.62 2.75 25.0 at 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 30.0 at s< 50%F 2.82 2.82' 2.95 25.0 at s< 50%F 3.20 3.35 100.0 1.59 1.59 1.57 1.57*
90.0 90.0. 1.64 1.64 1.63 50.0 ---
EOC-RPT-OOS, 50.0 1.89 1.89 . 1.92 1.92
.TBVOOS,
~~TBVOOS, 40.0 2.05 2.05~~
.1 :
FHOOS, FHOOS, 30.0 30.0 2.29 2.29 2.29 2.29
/ . and PLUOOS 30.0 at 30.0 at >> 50%F 50%F 3.13 3.13 3.17 3.17 25.0 at >> 50%F 3.47 3.47 30.0 at s< 50%F 2.82 2.95 25.0 at S< 50%F 3.20 3.35
~~3.35 AREVA NP Inc.~~
. AREVA
ANP-2863(NP)
ANP-2863(NP)
Unit 1 Cycle 9 Browns Ferry Unit
Revision 0 Safety Analysis for 105% OLTP Reload Safety OLTP . Page Page 8-11 8~11 Table 8.3 MCPRp MCPRp Limits for for .
NSS Times NSS Insertion Times BOC to EOCLB*
MCPRp MCPRp Operating Operating Power ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel Fuel Fuel 100.0 100.0 1.49 1.49 1.49 90.0 1.55 1.55 1.55 1.55 50.0 1.78 1.78 1.80 1.80 50.0 1.86 1.86 1.85 1.85 Base case 40.0 1.92 1.92 1.92 1.92 operation ' 30.0 2.15 2.15 2.15 30.0 at > 50%F 2.56 2.65 ,.
25.0 at > 50%F 2.77 . 2.86 30.0 at s< 50%F 2.53 2.65 25.0 at s< 50%F 2.72 2.83 100.0 100.0 1.52 1.52 1.52 1.52 90.0 1.58 1.58 1.58 1.58 50 .0 50.0 ---
50.0 1.86 1.86 1.85 1.85 40.0 1.96 1.96 -r1.96 1.96 TBVOOS 30.0 2.19 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at s< 50%F 2.71, 2.71* 2.83 25.0 at s< 50%F 3.04 3.17 3.17 100.0 1.49 1.49 1.49 1.49 90.0 1.55 1.55 1.55 1.55 50.0 1.78 1.78 1.80 1.80 50.0 1.86 1.86 1.85 1.85 40.0 1.92 1.92 1.92 1.92 EOC-RPT-OOS EOC-RPT-OOS 30.0' 2.15.
2.15, 2.15 30.0, 2.15 30.0 at > 50%F 2.56 2.65 .
25.0 at > 50%F 2.77 2.77. 2.86 30.0 at - 50%F ats 2.53.
2.53, 2.65 25.0 at 50%F 2.67 2.67_ 2.76 at.> 50%F 25.0 at> 2.90 3.00 at<5 50%F 30.0 ats 2.62 2.75 25.0 at 50%F 2.56 2.65 2.65 25.0 at > 50%F 5Q%F 2.77 2.86 2.86 30.0 at s< 50%F 2.53 2.65 2.65 25.0 at s< 50%F 2.72 2.83 2.83 100.0 100.0 1.52 1.52 1.52 90.0 1.58, '
~~1.58 1.58 1.58 50.0 ---~~
50.0 1.86 1.85 1.85 EOC-RPT-OOS EOC-RPT-OOS 40.0 1.96 1.96 1.96 and TBVOOS 30.0 2.19 2.19 2.19 30.0 at > 50%F 3.01 3.03 25.0 at > 50%F 3.35 3.35 30.0 at s< 50%F 2.71 ' 2.83.
~~2.83 25.0 at S< 50%F 3.04 3.17 3.17 100.0 100.0 1.52 1.51 90.0 1.59 1.58 1.58 50.0 --~~
~~50.0 1.86 1.87 1.87 EOC-RPT-OOS EOC-RPT-OOS .40.0~~
.40.0 2.00 2.01 and FHOOS FHOOS 30.0 2.24 2.24 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 3.00 30.0 at S< 50%F 2.62 2.75 25.0 at S< 50%F 2.84 2.96 .
~~100.0 100.0 1.49 1.49 1.49 90.0 1.55 1.55 1.55 50.0 --~~
50.0 1.91 1.91 EOC-RPT-OOS EOC-RPT -OOS 40.r0 40:0 1.92 1.92 1.92 and PLUOOS 30.0 2.15 2.15 2.15 30.0 at >> 50%F 2.56 2.65 25.0 at >> 50%F 2.77 2.86 30.0 at <S 50%F 2.53 2.65 25.0 at 50%F 50%F 3.13 3.17 3.17 25.0 25.0 at > 50%F 50%F 3.47 3.47 30.0 at S< 50%F 2.82 2.95 25.0 at S< 50%F 50%F 3.20 3.35 100.0 100.0 1.52 1.52 1.52 1.52 90.0 1.58 1.58 1.58 1.58 50 .0 50.0 ---
50.0 1.91 1.91 TBVOOS 40.0 . 1.96 1.96 1.96 1.96 and PLUOOS 30.0 2.19 2.19
~~. 2,19~~
~~> 50%F 30.0 at >50%F 3.01 3.03~~
~~3.03 25.0 25.0 at > 50%F 50%F 3.35~~
,3.35 3.35 3.35 30.0 at S< 50%F 2.71 2.83
'2.83 25.0 25.0 at S< 50%F 3.04 3.17 3.17 100.0 100.0 1.52
~~1.52 1.51 90.0 1.59 1.58, 1.58 50.0 50.0 --- ---~~
50.0 1.91 1.91 1.91 FHOOS FHOOS 40.0 2.00 2.01 and PLUOOS PLUOOS 30.0 2.24 2.24, 2.24 2.24
. 30.0 at > 50%F 2.67 2.67. 2.76 2.76 25.0 at > 50%F 2.90 3.00 30.0 at S< 50%F 2.62 2.75 2.75 25.0 25.0 at S< 50%F 2.84 2.96 2.96 I. 100.0 100.0 1.55 ' 1.54 1.54 90.0 ..
1.61 1.61 1.61 50.0 --
50.0 1.87 1.90 1.90 .
EOC-RPT-OOS, EOC-RPT-OOS, 40.0 2.03 2.04 40.0 2.03 2~04 TBVOOS, TBVOOS, 30.0 -.2.27 2.27 30.0 3 '2.27 2.27 and FHOOS FHOOS .
30.0 at > 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 3.47 30.0 at S< 50%F 2.82 2.95
~~2.95 25.0 at S< 50%F 3.20 3'.20 3.35~~
.3.35 AREVA NP Inc.
NPlnc.
ANP-2863(NP)
ANP-2863(NP)
Browns Unit 1 Cycle 9 Ferry Unit Browns Ferry Revision Revision 0
.. Reload Reload Safety Analysis Analysis for 105%
105% OL OLTP TP Page 8-14 Page 8-14 Table 8.3 MCPRMCPRpp Limits for NSS NSS Insertion Insertion Times Times BOC to EOCLB BOCto EOCLB (Continued)
(Continued)
MCPRp MCPRp Operating Operating Power ATRIUM-10 GE14 GE14 Condition (%of rated)
(% Fuel Fuel Fuel 100.0 1.52 1.52 1.52 1.52 90.0 1.58 1.58 1.58 1.58 50.0 --
50.0 1.91 1.91 1.91 EOC-RPT-OOS, EOC-RPT-OOS, 40.0. 1.96 1.96 40.0. 1.96 1.96 TBVOOS, 30.0 2.19 2.19 and PLUOOS 30.0 2.19 2.19 30.0 at > 50%F 50%F 3.01 3.03 25.0 at > 50%F 50%F 3.35 3.35 30.0 at s< 50%F 50%F 2.71 2.83 at*s 50%F 25.0 at 50%F 3.04 3.17 3.17 100.0 1.52 1.51 90.0 1.59 1.58 1.58 50.0 50.0 --- ---
50.0 1.91 1.91 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 2.00 2.01 40.0 2.00 2.01 FHOOS, 30.0 2.24 2.24 30.0 2.24 2.24 and PLUOOS PLUOOS 30.0 at > 50%F 50%F 2.67 2.76 2.76 25.0 at > 50%F 2.90 3.00 30.0 at s< 50%F 2.62 2.75 2.75 25.0 at s< 50%F 2.84 2.96 2.96 100.0 100.0 1.55 1.54 1.54 90.0 1.61 1.61 50.0 --
50.0 1.91 1.91 TBVOOS, TBVOOS, 40.0 2.03 2.04 40.0 2.03 2.04 FHOOS, 30.0 2.27 2.27 and PLUOOS 30.0
~~3. 2.27~~
.722 2.27 and PLUOOS 30.0 at >> 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 30.0 at s< 50%F 2.82 2.95 2.95.
25.0 at s< 50%F 3.20 3.35 3.35 100.0
.100.0 1.55 1.54 1.54 90.0 1.61 . 1.61 50.0 --
EOC-RPT-OOS, EOC-RPT-OOS, 50.0 1.91 1.91 TBVOOS, 40.0 2.03 2.04 FHOOS, 30.0 2.27 2.27 2.27 and PLUOOS PLUOOS 30.0 30.0 at at >> 50%F 50%F 3.13 3.13 3.17 3.17 25.0 at >> 50%F 3.47 3.47 3.47 30.0 at S< 50%F 2.82 2.95 2.95 25.0 at S< 50%F 3.20 3.35 3.35 AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1I Cycle 9 ;"Revision Revision 0 Reload Safety Analysis for 105%
105% OL OLTPTP Page 8-15 Page 8-15 Table 8.4 MCPR MCPRpp Limits for for TSSS Times TSSS Insertion Times BOC to BOC EOCLB*
to EOCLB*
MCPRpp MCPR Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (% of rated)
(% rated) Fuel Fuel 100.0 100.0 1.53 1.52 1.52 90.0 1.58 1.58 1.58 50.0 1.80 1.81 50.0 1.87 1.85 1.85 Base case 40.0 . 1.94 1.94 1.94 operation operation 30.0 2.16 2.16 2.16 30.0 at > 50%F 2.56 2.65 2.65 25.0 at > 50%F 2.77 2.86 2.86*
30.0 at <S 50%F 2.53 2.65 2.65 25,0 at s< 50%F 25.0 2.72 2.83 2.83 100.0 100.0 1.56 1.55 1.55 90.0 1.62 1.61 5 0 .0 50.0 ---
J. , 50.0 1.87 1.85 1.85 40.0 1.98 1.97 1.97 TBVOOS 30.0 2.21 2.20 2.20 30.0,at 30.0 ,at>> 50%F 3.01 3.03 3.03 25.0 at > 50%F 3.35 3.35 3.35 30.0 at <s 50%F 2.71 2.83 2.83 25.0 at ~~50%F 2.56 2.65 25~0 25.0 at > 50%F 2.77 2.86 30.0 at at <~~
s 50%F 2.53 2;53 2.65 25:0 25.0 at 50%F 30.0 at> 2.67 2.76 25.0 at > 50%F 50%F' 2.90 3.00 30.0 at s< 50%F 50%F 2.62 2.75 25.0 at s< 50%F 50%F 2.84 2.96 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 of TIP channels), and up to 50% of the the LPRMs out-of-service.~~
out~of-service. For single-loop operation, operation, MCPRpp limits will be 0.02 MCPR 0.02 h igher.**
higher. . ,
AREVA NP Inc:
ANP-2863(NP)
ANP-2863(NP}
Browns Ferry Unit 1 Cycle 9 Revision 0 105% OL
. Reload Safety Analysis for 105% OLTP TP 8-16 Page 8-16 Table 8.4 MCPRMCPRpp Limits for for TSSS Times TSSS Insertion Times BOC to EOCLB BOCto (Continued)
(Continued)
MCPRpp MCPR Operating Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (% of rated)
(% Fuel Fuel 100.0 100.0 1.53 1.52 1.52 90.0 1.58 1.58 1.58 50.0 --
50.0 1.91 1.91 40.0 1.94 1.94 1.94 PLUOOS 30.0 2.16 2.16 2.16 30.0 at >> 50%F 2.56 2.65 25.0 at >> 50%F 2.77 2.86 30.0 at <s 50%F 2.53 2.65 25.0 at ~~> 50%F 3.01 3.03 25.0 at >> 50%F 3.35 3.35 3.35 30.0 at <s 50%F 2.71 2.83 25.0 at ~~> 50%F 2.67 2.76 .~~~~
~~25.0 at >> 50%F 2.90 3.00 30.0 at <s 50%F 2.62 2.75 25.0 at ~~50%F 2.56 2.65 25.0 at > 50%F 2.77 2.86~~~~
~~2.86 30.0 at <~~
S 50%F 2.53 2.65 25.0 at <
S 50%F 2.72 2.83 AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision Revision 0 OLTP 105% OL Reload Safety Analysis for 10S% TP . Page 8-17 8-17 Table 8.4 MCPR Table MCPRpp Limits for for TSSS TSSS Insertion Insertion Times Times BOCto BOC EOCLB to EOCLB (Continued)
(Continued)
MCPRpp MCPR Operating Power ATRIUM-10 ATRIUM-10 GE4 GE14 Condition Condition (% of rated)
(% Fuel Fuel 100.0 1.59 1.S9 1.57 1.S7 90.0 1.64 1.63 1.63 50.0 SO.O --- ---
50.0 SO.O 1.89 1.92 1.92 TBVOOS 40.0 2.05 2.0S 2.05 2.0S and FHOOS FHOOS 30.0 2.29 2.29 30.0 at > SO%F 50%F 3.13 3.17 3.17 25.0 at > SO%F 2S.0 50%F 3.47 3.47 30.0 at <S SO%F 50%F 2.82 2.95 2.9S 25.0 at SO%F 3.01 3.03 25.0 at > SO%F 2S.0 50%F 3.35 3.3S 3.35 3.3S 30.0 at <S SO%F 50%F 2.71 2.83 25.0 at SO%F 2.67 2.76 2S.0 50%F 25.0 at > SO%F 2.90 3.00 at5<50%F 30.0 at S SO%F 2.62 2.75 2.7S 25.0 at S< 50%F 2S.0 SO%F 2.84 2.96 100.0 1.59 1.S9 1.57 1.S7 90.0 1.64 1.64 1.63 1.63 50.0 SO.O --
~~.. SO.O~~
... 50.0 1.89 1.89 1.92 1.92 EOC-RPT-OOS, EOC-RPT -OOS, 40.0 2.05 2.05 40.0 2.0S 2.0S TBVOOS, 30.0 2.29 2.29 30.0 2.29 2.29 FHOOS and FHOOS
>50%F 30.0 at >SO%F 3.13 3.17 3.17 25.0 at >SO%F 2S.0 >'50%F 3.47 3.47 30.0 at S < 50%F SO%F 2.82 2.95 2.9S 25.0 at 2S.0 at S< 50%F SO%F . 3.20 3.20 3.35 3.3S AREVA AREVA NP Inc.
~~ANP-2863(NP)~~
ANP-2863(NP) 1 Cycle 9 Browns Ferry Unit 1. Revision Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP Page 8-18 8-18 Table 8.4 MCPRMCPRpp Limits for
~~. TSSS Times TSSS Insertion Times BOC BOCto to EOCLB (Continued)~~
~~(Continued)~~
~~MCPRpp MCPR Operating Operating Power Power* ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (%~~
~~(% of rated) Fuel Fuel 100.0 100.0 1.56 1.55 1.55 90.0 1.62 1.61 50.0 --~~
~~50.0 1.91 1.91 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 1.98~~
'1.98 1.97 40.0 1.97 TBVOOS, 30.0 andTPLUOOS and PLUOOS 30.0 . 2.21 2.21 2.20 30.0 at > 50%F 3.01 3.03 3.03 25.0 at > 50%F 3.35 3.35 3.35 30.0 at s< 50%F 2.71 2.83 25.0 at s< 50%F 3.04 3.17 3.17 100.0 100.0 1.56 1.54 1.54 90.0 1.61 1.60 1.60 50.0 --
50.0 1.91 1.91 EOC-RPT-OOS, EOC-RPT-OOS, 40.0 2.01 2.02 40.0 2.01 2.02 FHOOS, 30.0 30.0 2.25 2.25 2.25 and PLUQOS PLUOOS 30.0 at > 50%F 2.67 2.76 25.0 at > 50%F 2.90 3.00 30.0 at S< 50%F 2.62 2.75 25.0 at s< 50%F 2.84 2.96 100.0 1.59 1.57 1.57 90.0 1.64 1.63 50.0 --
50.0 1.91 1.92 TBVOOS, TBVOOS, 40.0 2.05 2.05 40.0 2.05 2.05 FHOOS, 30.0 2.29 2.29 and PLUOOS 30.0
~~3. 2.29~~
.922 2.29 and PLUOOS 30.0 at > 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 30.0 at <s 50%F 2.82 2.95 25.0 at ~~50%F 3.13 3.13 3.17 3.17 25.0 at > 50%F~~
>50%F 3.47 3.47 30.0 at <s 50%F 2.82 2.95 25.0 at SO%F 50%F 2.67 2.76 2.76 25.0 2S.0 at > SO%F 50%F 2.90 3.00 3.00 30.0 at S< SO%F 50%F 2.62 2.75 2.7S 25.0 2S.0 at S< SO%F 50%F 2.84 2.96 2.96 100.0 100.0 1.55 1.SS 1.54 1.S4 90.0 1.61 1.61 50.0 SO.O --
~~50.0 SO.O 1.87 1.90 1.90 40.0 2.03 2.04 TBVOOS TBVOOS 30.0 2.27 2.27 2.27 30.0 at >SO%F~~
>50%F 3.13 3.17 3.17 25.0 at >>'50%F 2S.0 SO%F 3.47 3.47 30.0 at S< SO%F 50%F 2.82 2.95 2.9S 25.0 2S.0 at S< SO%F 50%F 3.20 3.35 3.3S 100.0 100.0 1.52 1.S2 1.51 .
~~1.S1 90.0 1.59 1.S9 . 1.58 1.S8 50.0 SO.O. --~~
~~50.0 SO.O 1.86 1.86 .1.87 1.87 40.0 2.00 2.01 EOC-RPT-OOS EOC-RPT-OOS 30.0 2.24 2.24~~
~~'2.24 30.0 at > SO%F 50%F 2.67 " 2.76 25.0 at>~~
2S.0 50%F at > SO%F 2.90, 2.90 3.00 3.00 30.0 at S< SO%F 50%F 2.62 2~62 2.75 2.7S 25.0 2S.0 at < 50%F S SO%F 2.84 2.84 2.96 2.96
~~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 of TIP channels), and up to 50% LPRMs out-of-service.~~
SO% of the LPRMs out-of-service. Limits Limits, also support support operation operation with FFTRlFHOOS FFTR/FHOOS which boundsbounds operation with feedwater feedwater heaters in-service. For single-loop
. operation, MCPRp MCPRp limits will be 0.02 higher.
higher. .
AREVA NP Inc...
AREVA NP"lnc
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit Unit 1 Cycle 9 Revision 0 Revision Reload Safety Safety Analysis for for*1105% TP OLTP 05% OL Page Page 8-20 8-20 MCPRpp Limits for Table 8.5 MCPR NSS Insertion NSS Times Insertion Times FFTR/Coastdown BOC to FFTRICoastdown (Continued)
(Continued)
MCPRp MCPRp Operating Operating Power ATRIUM-10 GE14 GE14 Condition (% of rated) Fuel Fuel 100.0 100.0 1.52 1.51 90.0 1.59 1.58 1.58 50.0 --
50.0 1.92 1.91 PLUOOS 40.0 40.0 2.00 2.01 PLUOOS 30.0 2.24 2.24 2.24 30.0 at > 50%F 50%F 2.67 2.76 2.76 25.0 at > 50%F 25.0 50%F 2.90 3.00 3.00 30.0 at s< 50%F 2.62 2.75 2.75 25.0 at s< 50%F 25.0 2.84 2.96 2.96 100.0 100.0 1.55 1.54 1.54 90.0 1.61 1.61 50.0 ---
1.90 50.0 1.87 1.90 .
EOC-RPT-OOS EOC-RPT-OOS 40.0 2.03 2.04 and TBVOOS 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 3.47 30.0 at s< 50%F 2.82 2.95 2.95 25.0 at s< 50%F 25.0 3.20 3.35 3.35 100.0 100.0 1.52 1.51 90.0 1.59 1.58 1.58 50.0 .. -- ---
! 50.0 1.92 1.91 EOC-RPT-OOS EOC-RPT -OOS 40.0 2.00 2.01 and PLUOOS PLUOOS 30.0 30.0 2.24 2.24 2.24*
30.0 at > 50%F 2.67 2.76 2.76 25.0 at > 50%F 2.90 3.00 3.00 30.0 at s< 50%F 2.62 2.75
.2.75 25.0 at s< 50%F 2.84 2.96 2.96 AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP. Page 8-21 Table 8.5 MCPR Table for MCPRpp Limits for NSS NSS Insertion Times Insertion Times BOC to FFTR/Coastdown FFTRICoastdown (Continued)
(Continued)
MCPRPp MCPR Operating Power ATRIUM-10 ATRIUM-10 GE14 GE14 Condition (% of rated)
(% Fuel Fuel 100.0
~~100.0 1.55 1.54 1.54 90.0 1.61 1.61 50.0 --~~
50.0 1.92 1.91 TBVOOS 40.0 2.03 2.04 and PLUOOS PLUOOS 30.0 2.27 2.27 30.0 at > 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 3.47 30.0 at s 50%F 2.82 2.95 2.95 25.0 at 50%F 3.13 3.17 3.17 25.0 at > 50%F 3.47 3.47 30.0 at <s 50%F 2.82 2.95 25.0 at SO%F 50%F 2.67 2.76 25.0 at > SO%F 2S.0 50%F 2.90 3.00 30.0 at S< SO%F 50%F 2.62 2.75 2.7S 25.0 at<* SO%F 2S.0 ats 50%F 2.84 2.96 100.0 1.59 1.S9 1.57 1.S7 90.0 90.0 1.64 1.64 1.63 1.63 50.0 SO.O --.. ---
50.0 SO.O 1.89 1.92 1.92 40.0 2.05 2.0S 2.05 2.0S TBVOOS 30.0 2.29 2.29 30.0 at >> SO%F 50%F 3.13 3.17 3.17 25.0 at > SO%F 2S.0 50%F 3.47 3.47 30.0 at s< SO%F 50%F 2.82 2.95 2.9S 25.0 2S.0 at S< SO%F 50%F 3.20 3.35 3.3S 100.0 1.56 1.S6 1.54 1.S4 90.0 1.61 1.60 1.60 50.0 SO.O* --
50.0 SO.O 1.87 1.89 1.89 40.0 2.01 2.02 EOC-RPT-OOS 30.0 2.25 2.2S 2.25 2.2S 30.0 at > SO%F 50%F 2.67 2.76 25.0 at > SO%F 2S.0 50%F 2.90 3.00 30.0 at <S SO%F 50%F 2.62 2.75 2.7S 25.0 at 50%F 50%F 2.67 2.76 25.0 at > 50%F 50%F 2.90 3.00 30.0 at S< 50%F 50%F 2.62 2.75 25.0 at S< 50%F 50%F 2.84 2.96 100.0 1.59 1.59 1.57 90.0 1.,64 1.,64 1.63 50.0 --- ---
50.0 1.89 1.89 1.92 EOC-RPT-OOS EOC-RPT-OOS 40.0 2.05 2.05 TBVOOS and TBVOOS 30.0 2.29 2.29 30.0 at > 50%F 50%F 3.13 3.17 3.17 25.0 at > 50%F 50%F 3.47 3.47 30.0 at S< 50%F 50%F 2.82 2.95 25.0 at S< 50%F 50%F 3.20 3.35 100.0 100,0 1.56 1.56 1.54 90.0 1.61 1.61 1.60 50.0 --
, 50.0 1.92 1.92 1.91 EOC-RPT-OOS EOC-RPT-OOS 40.0 2.01 2.02 and PLUOOS 30.0 2.25 2.25 30.0 at > 50%F 50%F 2.67 2.76 25.0 at > 50%F 50%F 2.90 3.00 30.0 at S< 50%F 50%F 2.62 2.75 25.0 at Ss 50%F 50%F 2.84 2.96 AREVA NP Inc.,
~~Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP}~~
. Browns Ferry Unit 1 Cycle 9 '. .* Revision Revision 0 105% OL Reload Safety Analysis for 10S% OLTP TP 8-24 Page 8-24 Table 8.6 MCPRpp Limits for 8.6 MCPR for TSSS Insertion TSSSlnsertion Times Times BOC to FFTRICoastdown FFTR/Coastdown (Continued)
~~(Continued)~~
~~MCPRPp MCPR Operating Power ATRIUM-10 ATRIUM-10 GE14~~
~~. GE14~~
~~. Condition (% of rated)~~
~~(% Fuel Fuel 100.0 1.59" 1.S9* 1.57 1.S7 90.0 1.64 1.63 1.63 50.0 SO.O --,~~
50.0 SO.O 1.92 1.92 f92 TBVOOS 40.0 2.05 2.0S 2.05 2.0S and PLUOOS 30.0 2.29 2.29 30.0 at > SO%F 50%F 3.13 3.17 3.17 25.0 2S.0 at > SO%F 50%F 3.47 3.47 3.47 30.0 at <S SO%F 50%F 2.82 2.95 2.9S 25.0 2S.0 at 50%F SO%F 3.13 3.17 3.17 25.0 2S.0 at > 50%F SO%F 3.47 3.47 30.0 < 50%F at S SO%F 2.82 2.95 2.9S 25.0 2S.0 < 50%F at S SO%F 3.20 3.35 3.3S
~~AREVA NP Inc.~~
ANP-2863(NP)
ANP':2863(NP)
Browns Ferry Unit 1I Cycle 9 , Revision Revision 0 Reload Safety Analysis Reload Analysis for 105% OL OLTP TP Page 8-25 '
Table 8.
8.7 Flow~Dependent MCPR Limits 7 Flow-Dependent Limits ATRIUM-10 and GE14 Fuel ATRIUM-10 Core Flow Core Flow
(% of rated)
(% MCPRf MCPRf
,30.0 30.0 1.61 78.0 1.28 '
1.28 107.0 1.28 1.28
\
AREVA NP Inc.
NPlnc.,
ANP-2863(NP)
ANP-2863(NP)
Browns Unit 1I Cycle 9 Browns Ferry Unit . Revision 0 Revision Reload Reload Safety Analysis Analysis for 105% OL OLTP TP 8-26 '
. Page 8~26 Table 8.8 ATRI,UM-10 ATRIUM-10 Steady-State LHGR Limits Limits Peak Exposure Pellet Exposure LHGR LHGR (GWd/MTU)
(GWd/MTU) (kW/ft) 0.0 13.4 13.4 18.9 18.9 13.4 13.4 74.4 7.1
, AREVA NP NP hic:
Inc. .'
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 I Cycle Cycle 9 Revision Revision 0 Reload Safety Analysis for 105%
105% OLOLTP TP . Page 8-27 Table 8.9 ATRIUM-10 Table ATRIUM*10 LHGRFAC LHGRFACpp Multipliers for NSS/TSSS Insertion NSSITSSS Insertion. Times Times All Cycle 99 Exposures*
EOOS Power ATRIUM-10 ATRIUM-10 Condition (%rated)
(% LHGRFACpp LHGRFAC 100.0 1.00 1.00 Base 30.0 30.0 0.64 0.64 case at > 50%F 30.0 at> 50%F 0.47 0:47 operation operation 25.0 at >> 50%F 25.0 at 50%F 0.47 0.47 (TBVIS)t 30.0 at < 50%F 0.47 30.0 at s 50%F 0.47 25.0 at s< 50%F 0.47 0.47 100.0 0.90 0.90 90.0 0.83 0.83 30.0 0.62 0.62 TBVOOSý TBVOOSt 30.0 at > 50%F 50%F 0.43 0.43 25.0 at > 50%F 50%F 0.39 0.39 30.0 at S< 50%F 0.47 0.47 25.0 at S<50%F 50%F 0.46 0.46 Limits support operation with any combination of I 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 of TIP channels).~~
channels), and up to 50% of the LPRMs out-of-service. Base case supports single-loop operation.
operation. .
t Limits are applicable for all the EOOS scenarios presented in Table 1.1 except those that Limits are applicable for all the EOOS scenarios presented in Table 1.1 except those that include include TBVOOS.
Limits are applicable for all the EOOS scenarios presented in Table 1.1 including Limits are applicable for all the EOOS scenarios presented in Table 1.1 including those those with with TBVOOS.
TBVOOS. . -
AREVA NP Inc~
Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 , Revision Revision 0 Reload Safety Analysis for 10S%105% OL OLTP TP . Page 8-288-28, Table 8.10 GE14 LHGRFACLHGRFACpp Multipliers Multipliers for NSSITSSS Insertion NSSITSSS Times Insertion Times All Cycle 9 Exposures*
All EOOS Power GE14 EOOS Power GE14 Condition (%rated)
(% LHGRFACpp LHGRFAC 100.0 1.00 1.00 75.0 7S.0 0.78 0.78 Base 30.0 30.0 0.60
. 0.60 case case operation operation 30.0 at 30.0 SO%F at>> 50%F 0.44 (TBVIS)t 25.0 at > 50%F 2S.0 at> SO%F 0.42 0.42 30.0 at S< 50%F SO%F 0.44 0.44 25.0 at S< 50%F 2S.0 SO%F . 0.44 0.44 100.0 100.0 0.99 0.99 75.0 7S.0 0.77 30.0 0.58 0.S8 TBVOOSt TBVOOSt 30.0 at > 50%F SO%F 0.37 25.0 2S.0 at > 50%F SO%F 0.31 30'.0 at S< SO%F 30:0 50%F 0.44 2S.0 at S< SO%F 25.0 50%F 0.43 Limits support operation with any combination of 1. MSRVOOS, up to 2 TIPOOS (or the equivalent
~~Limits support operation with any combinati()n of 1 MSRVOOS: up to 2 TIPOOS (or the equivale~t number of TIP channels);'~~
channels); and up to SO% out-of-service. Base case supports 50% of the LPRMs out-af-service. supports single-single,.
loop operation.
operation. . . .
t Limits are applicable for all the EOOS scenarios presented in Table 1.1 t* Limitsare applicable for all the EOOS scenarios presented in T~ble. 1.1 except those that include exceptthosethatinclude" TBVOOS. . . ,
.t 'Limits are applicable for all the EOOS scenarios presented in Table 1.1 including those Limits are applicable for all the EOOS scenarios presented in Table 1.1 including those with '., with TBVOOS, TBVOOS. . . '
AREVA NP IncInc.... "I'
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 for 1105%
Reload Safety Analysis for TP OLTP 05% OL . Page 8-29 8-29 Table 8.11 ATRIUM-10 Table 8.11 LHGRFACff Multipliers ATRIUM*10 LHGRFAC Multipliers All All Cycle 9 Exposures Exposures Core Flow Core Flow
(% of rated)
(% LHGRFACff LHGRFAC 0.0 0.86 30.0 0.86 56.4 1.00 1.00 107.0 107.0 1.00 1.00 AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1.
Browns I Cycle 9 Revision 0 Revision Reload Reload Safety Analysis for 105% OL OLTPTP Page 8-30 Table Table 8.12 GE14 LHGRFAC LHGRFACff Multipliers Multipliers All Cycle 9 Exposures Exposures Core Flow GE14 Core Flow GE14
(% rated) LHGRFACf LHGRFACf 0.0 0.54 30.0 0.54 81.8 1.00 1.00 107.0 1.00 1.00 AREVA AREVA NP Inc.
ANP-2863(NP} .
ANP-2863(NP)
I Cycle 9 Browns Ferry Unit 1 Revision 0 Revision 0.
Reload Safety Analysis for 105%
105% OL TP OLTP Page 8-31 ...
Page Table 8.13 ATRIUM-10 ATRIUM-10 MAPLHGR MAPLHGR Limits' Limits Average Planar Average Planar, Exposure MAPLHGR MAPLHGR (GWd/MTU)
'(GWd/MTU) (kW/ft)
(kW/ft) 0.0 12.5 12.5 15.0 12.5 12.5 67.0 7.3 7.3
! f
, I AREVA NP NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9.
9 . . Revision 0 Reload Safety Analysis for 105%
105% OLOLTP TP Page 9-1 Page 9.0 References References
~~1. ANP-2859(P)~~
ANP-2859(P) Revision 1, Browns Ferry Ferry Unit 1I Cycle 9 Fuel Design (105%
Fuel Cycle Design (105% OLTP),
OLTP),
AREVA AREVA NP, October 2009. .
2. ANP-2877(P) MechanicalDesign ANP-2877(P) Revision 0, Mechanical Report for Browns Ferry Design Report FerryUnit Unit 1I Reload BFE1-9 ATRIUM-10 BFE1-9 ATRIUM-IC Fuel FuelAssemblies Assemblies (105% OL OLTP),
~~TP), AREVA AREVA NP, November November 2009.~~
~~3. ANP-2821 (P) Revision 0, Browns Ferry Unit 1I Thermal-Hydraulic Ferry Unit Thermal-HydraulicDesign Design Report for A TRIUM TM-10 Fuel ATRIUM'-10 Fuel Assemblies (105% OLTP),~~
~~OLTP), AREVA NP, June 2009 2009...~~
4. ANF-524(P)(A) Revision 2 and Supplements Supplements 1 and 2, ANF CriticalCriticalPower PowerMethodology Boiling Water for Boiling Water Reactors, Reactors,Advanced Advanced Nuclear Fuels Corporation, Corporation, November November 1990.
~~1990:~~
~~5. Revision 2, SPCB Critical EMF-2209(P)(A) Revision CriticalPower Correlation,FramatomeANP, Power Correlation, Framatome ANP, September 2003.~~
~~September~~
~~6. EMF-2245(P)(A) Revision 0, Application EMF-2245(P)(A) Revision Application of Siemens Power Corporation'sCritical Power Corporation's CriticalPower~~
'- Correlationsto Co-Resident Co-Resident Fuel, Fuel, Siemens Power Corporation, August 2000.
\
Correlations
7. NEDO-32465-A, NEDO-32465.,.A, Licensing Topical Report, Reactor Reactor Stability Stability Detect Detect and Suppr~ss and Suppress Solutions Solutions Licensing Basis Methodology Licensing Basis Methodology and Reload Reload Applications, Applications, GE Nuclear Nuclear Energy,
~~,r . August 1996.~~
~~8. OG04-0153-260, Plant-Specific OG04-0153-260, Plant-Specific Regional Regional Mode Mode DIVOM Procedure Procedure Guideline, 15, 2004.~~
~~June 15,2004.~~
9. BWROG-03047, BWROG-03047, Resolution of Reportable Condition for Stability Reload Licen~ing Licensing Calculations Using Generic Calculations Generic Regional Regional Mode DIVOM DIVOM Curve, September September 30, 2003.
~~2003.~~
10. OG02-0119-260, Backup Stability OG02-:0119-260, Protection (BSP) for Inoperable Stability Protection Inoperable Option III Solution, GE Nuclear Nuclear Energy, July 17,2002.
17, 2002.
11.
11. EMF-CC-074(P)(A) Volume 4 Revision 0, BWR Stability EMF-CC-074(P)(A) StabilityAnalysis - Assessment of STAIF ofSTAIF with Input Input from MICROBURN-B2, MICROBURN~B2, Siemens Power Power Corporation, August August 2000.
I'
~~12. ANF-913(P)(A)~~
ANF-913(P)(A) Volume 1 Revision 1 and Volume 1 Supplements Supplements 2, 3 and 4, 4, COTRANSA2: A Computer Programfor Boiling Computer Program Boiling Water Water Reactor Reactor Transient TransientAnalyses, Analyses, Advanced Advanced Nuclear Corporation, August 1990 NuClear Fuels Corporation, 1990..
. 13. XN-NF-84-105(P)(A) Volume XN-NF-84-105(P)(A) Volume 1 and Volume 1 Supplements Supplements 1 and 2, XCOBRA-T:
XCOBRA:T: A Computer Code Computer Code for for BWR Transient Transient Thermal-Hydraulic Thermal-HydraulicCore Core Analysis, Exxon Nuclear Nuclear Company, February 1987. . .
~~14. . XN-N F-80-19(P)(A)~~
F-80-19(P)(A) Volume Volume' 3 Revision Revision 2, Exxon Nuclear NuclearMethodology Methodology for Boiling Boiling Water Reactors, Reactors, THERMEX: Thermal Thermal Limits Methodology SummaryDescription, Exxon Methodology Summary Description, Nuclear Company, January.
NuclearCompany, January, 1987 1987...
AREVA NP Inc.*
Inc. ..
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105%
105% OL TP .
OLTP Page 9-2
15. EMF-2158(P)(A) Revision 0, Siemens Power EMF-2158(P)(A) PowerCorporation Boiling Water Corporation Methodology for Boiling Reactors: Evaluation
. Reactors: Evaluation and Validation Validation of CASMO-4/MICROBURN-B2, CASMO-4IMICROBURN-B2, Siemens Power Power Corporation, October 1999.
Corporation, October 16.
~~16. XN-NF-81-58(P)(A)~~
XN-NF-81-58(P)(A) Revision 2 and Supplements Supplements 1 and 2, RODEX2 Fuel Fuel Rod Therrnal-Thermal-MechanicalResponse Mechanical Response Evaluation Evaluation Model, Nuclear Company, March 1984.
Model, Exxon Nuclear
~~17. Technical Specification Technical Specification Requirements Requirements for for Browns Ferry FerryNuclear NuclearPlant Plant Unit 1, Tennessee Tennessee Valley Authority, as amended.~~
Valley 18.
18.* ANF-1 358(P)(A) Revision 3, The Loss of Feedwater ANF-1358(P)(A) FeedwaterHeating Heating Transient Transient in Boiling Water Reactors, Framatome Framatome ANP, September 2005.
19. EMF-2950(P) Revision EMF-2950(P) Revision 2, Browns Ferry Ferry Units Units 1, 2, and and 3 Extended Power Power Uprate LOCA Uprate LOCA Break Spectrum Analysis, Break Analysis, AREVA AREVA NP, August 2009.
20. EMF-3145(P) Revision 1, Browns Ferry EMF-3145(P) Ferry Units Units 1, 2, and and 3 Extended Power Power Uprate Uprate LOCA-ECCS Analysis MAPLHGR Limit for forATRIUM TM-1O Fuel, ECCS ATRIUMTM-10 Fuel, AREVA NP, August 2009.
~~21.~~
21. 0000-0044-1520-SRLR Revision 0, Supplemental 0000-0044-1520-SRLR Supplemental ReloadLicensing Reload Licensing Report Report for for Browns Ferry 1 Reload Ferry Reload 6 Cycle 7, Global Global Nuclear Nuclear Fuel, Fuel, January January 2007.
22. XN-NF-80-19(P)(A) Volume 1 and Supplements XN-NF-80-19(P)(A) Supplements 1 and 2, Exxon Nuclear Nuclear Methodology for Boiling Water ReaCtors for Reactors - Neutronic NeutronicMethods for Design and Analysis, Exxon Nuclear Design and Nuclear Company, March 1983. .
~~23. XN-NF-80-19(P)(A)~~
XN-NF-80-19(P)(A) Volume 4 Revision 1, Exxon Nuclear Nuclear Methodology for Boiling Boiling Water Reactors:Application Reactors: Application of the ENC Methodology to BWRReloads, BWR Reloads, Exxon Nuclear Exxon Nuclear Company, JuneJune 1986.
24. EMF-2978(P) Revision 0, Browns Ferry EMF-2978(P) FerryNuclear PlantNew Fuel Nuclear Plant Fuel Storage Storage VaultCriticality Vault Criticality Safety Analysis for for A TRIUM TM-IO Fuel, Framatome ATRIUMTM-10 Fuel, Framatome ANP, July July 2005.
~~25. EMF-2939(P) Revision 0, Browns Ferry Nuclear Plant Ferry Nuclear Plant Spent Fuel Fuel Storage Storage Pool Criticality Pool Criticality forATRIUM'm-IO~~
~~.Safety Analysis for Fuel, Framatome ATRIUMTM-10 Fuel, Framatome ANP, August 2003.~~
~~26. 0000-0077-8380-SRLR Revision 0000-0077-8380-SRLR Supplemental Reload Licensing Revision 0, Supplemental Licensing Report Report for for Browns~~
. Ferry Ferry 1 I Reload 7 Cycle 8, Global Nuclear Nuclear Fuel, August 2008...
August,2008
27. Letter, EA Brown (NRC) to KW Singer (TVA), "Browns Ferry Nuclear Nuclear Plant, Units 1,2, 1, 2, and 3 - Issuance of Amendments Regarding Regarding Full-Scope Implementation Alternative Implementation of Alternative Source Source Term (TAC Nos. MB5733, MB5734, MC0156, MCOt57 MB5734, MB5735, MC0156, MC0157 and MC0158) 27, 2004.
~~(TS-405)," September 27,2004.~~
28. Letter, TA Galioto (FANP) to JF Lemons (TVA), "Fuel Handling Accident Assumptions JFLemons Assumptions for Browns Browns Ferry," TAG:02:012, January January 23, 2002.
23,2002. .
29.
'29. . MJ Mneimneh Mneimneh (GNF) to D McNelley McNelley (TVA), "Revised LHGR Limits for BF1 Transition,"
MJM-TVA-ER1-09-39, MJM-TVA-ER1-09-39, April 2, 2009.
I
30. BAW-1 0255PA Revision BAW-10255PA Revision 2; DIVOM Methodology 2, Cycle-Specific DIVOM Methodology Using the RAMONA5-RAMONA5-FA Code, AREVA NP, May May 2008. .
. AREVA AREVA NP Inc.
Inc:
ANP-2863(NP)
ANP-2863(NP}
Browns Ferry Unit 1I Cycle 9 Revision 0 Reload Safety Analysis for 105% OLOLTP TP 9-3 Page 9-3 31.
~~31. EMF-2209(P) Revision EMF-2209(P) Revision 2 Addendum 1 Revision 0, SPCB SPCB Additive Constants Constants for ATRIUM-10 ATRIUM-10 Fuel,Fuel, AREVA AREVA NP, April 2008.~~
32. ANP-2860(P) Revision 2, Browns ANP-2860(P) Ferry Unit I1 - Summary of Responses to Request Browns Ferry Request for Additional Additional Information, Information, AREVA NP, October 2009.
~~33. Letter, TE Abney (TVA) to U. U. S. NRC, "Browns Ferry Nuclear Plant (BFN) (BFN) - Unit 11--~~
Technical Specifications Proposed Technical Specifications (TS) Change TS - 431 -Request
- Request for License License Amendment Amendment- - Extended Power Uprate Uprate (EPU) Operation,"
Operation," TVA-BFN-TS-431, TVA-BFN-TS-431, June June 28, 2004.
34. EMF-2982(P) Revision EMF-2982(P) Revision 0, Browns Ferry Units 2 and 3 Safety Analysis Report for Ferry Units Extended Power Extended Uprate ATRIUMm-1O Power Uprate ATR/uMTM-10 Fuel Fuel Supplement, Supplement, Framatome ANP, June June 2004.
35. NEDC-33047P Revision 2, Browns Ferry NEDC-33047P Ferry Units 2 and 3 Safety Analysis Report Report for Extended Power Extended Uprate, GE Nuclear Energy, June 2004.
~~Power Uprate,~~
36. NEDO-33101, NEDO-331 01, Browns Ferry FerryUnit Unit 1 Safety Analysis Report Report For ForExtended Power Power Uprate, Uprate, GE Nuclear Nuclear Energy, JuneJune 2004. . .
37. Browns Ferry Browns FerryNuclear Nuclear Plant Units 1, 2, Plant Units 2, and 3 Fire Fire Protection ProtectionReport Volume 1 Section 3 Shutdown Analysis, Revision 4, Tennessee Safe ShutdownAnalysis, Tennessee Valley Valley Authority, March March 25, 2009.
~~38.~~
~~38. EMF-2361 (P)(A),~~
EMF-2361 (P)(A), Revision Revision 0, 0, EXEM EXEM BWR-2000 BWR-2000 ECCS Evaluation Model, ECCS Evaluation Framatome Model, Framatome ANP, May 2001.
2001.
39. ANP-2638(P), Revision 2, Applicability Applicability of AREVA AREVA NP NP BWR BWR Methods to Exteoded Extended Power Uprate Conditions, Uprate Conditions, AREVA AREVA NP Inc., October October 2009.
~~40. Letter, TA Galioto (AREVA) to GC Storey (TVA), "10 CFR 50.46 PCT Reporting for BFN Units 2 and 3," TAG:05:056, June June 30, 2005.~~
30,2005.
41.
41. Letter, S Richards Richards (NRC) to JF Mallay Mallay (SPC), "Siemens Power Power Corporation Corporation Re: Request Request for Concurrence Concurrence on Safety Evaluation Clarifications (TAC No. MA6160),"
~~Evaluation Report Clarifications MA6160)," May May 31, 31, 2000.~~
~~42. Letter, TB Blount (NRC)~~
(NRC) to RL Gardner (AREVA), "Final Safety Evaluation Evaluation for AREVA NP, Inc. (AREVA) Topical Reports (TR) EMF-2209(P),
EMF-2209(P), Revision Addendum 1, 'SPCB Revision 2, Addendum ATRIUM-10 Fuel' Additive Constants for ATRIUM-10 Supplement 1, Fuel' and ANP-10249(P), Revision 0, Supplement
'ACE Additive Constants for ATRIUM-10 ATRIUM-10 Fuel'Fuel' (TAC Nos. MD8754 MD8754 and ME0162),"
ME01 62),"
September 23, 2009.
September AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Ferry Unit 1t Cycle 9 . Revision 0 Revision Reload Safety Analysis for 105% OLTP Page AA-1
.. 1 Appendix A Appendix Operating Operating. Limits and Results Comparisons Comparisons The figures and tables presented presented in this appendix appendix show comparisons of the BF1 Cycle 9 operating operating limits and the transient Comparisons are presented for the transient analysis results. Comparisons the ATRIUM-10 ATRIUM-10 and GE14 MCPR MCPRpp limitsand limits and LHGRFAC LHGRFACpp multipliers.
I' AREVA AREVANPNP Inc.
1.
ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry Ferry Unit Unit 1 Cycle 9 Revision 0 Revision Reload Safety Safety Analysis for 105% OLTP OLTP PageA-2 Page A-2 3.0 , - - - - - - - r - - - , - - - - , - - - - - - - r - - - , - - - - , - - - - - - . - - - , - - - , - - - - - - - r - - - ,
o3 o F'VC FWCF V/CF o0 LFR*NB LRNB t:.
RWE CRWE 2.5 I-
+-'
'E
°E
-j 0
~~=i 0~~
'Q.o 2.0 0 a:::
a_
0L 0....
u02
~ 0A 1.5 k 00 I I1 I I II I 1.0 '--_--'-_ _--'-_ _L - - _ - - L_ _- - ' -_ _L - - _ - - L_ _--1-_ _.L.-_----1._ _---l 1.0 0,
~~0. 10 20 30 40 50 60 70 80 ,90 90 100 110 110 Power (% (% Rated)~~
Power MCPRpp MCPR
(% of rated) rated) Limit Limit 100 100 .1.49
1.49 90 1.55 1.55 50 1.78 1.78 50 1.84 1.84 40 1.92 30 2.15 2.15 30 at >> 50%F 2.56 25 at >> 50%F 2.77 30 at <s 50%F 2.53 25 at5 s 50%F at <50%F 2.72 Figure A.9.1 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for MCPR ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Insertion Times Times Base Case Case AREVA AREVA NP Inc.
. ANP-2863(NP),
ANP-2863(NP)
Browns Ferry Unit 1I Cycle 9 Revision Revision 0 105% OLTP Reload Safety Analysis for 105% Page A-3 A-3 3.0 .---'-------r----.----,------r----.----T-----r--'-r----r----.:....---r~-_,
oO] FWCF FWCF o LRNB LRNB A*
b.. CRWE CRWE 2.5 1-4-t
'EE
i
-j 00 Cl. 2.0 F-0:: 00 a..
0~
012
~
A0 1.5 I-1.5 oA
,.. 0o b.
0 0 3, 0
" ,I. i i ii , i, 1.0 1.0 0 10 20 30 40 50 60 70 80 90.
90 100.
100 110 110 J
1 Power (% (% Rated)
Power . MCPR MCPRpp
'I; (% of rated) Limit Limit
., I ,. 100 1.49 1'.49 90 1.55 1.55 50 1.80 1.80 50 1.83 1.83 40 1.92 1.92
, i 30 2.15 2.15 30 at > 50%F
. *30 2.65 25 at > 50%F 2.86 at* 50%F 30 ats 50%F 2.65 25 ats
~~25 at < 50%F 50%F 2.83 2.83.~~
Figure A.9~2 A.9.2 BOC BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for
\ " GE14 Fuel N.SS Insertion Times NSS Insertion Times Base Case Base Case.
AREVA AREVA NP Inc.
,ANP-2863(NP)
ANP-2863(NP)
, Browns Ferry Unit 1 Cycle Cycle 9 .' Revision Revision 0 Reload Safety Analysis for 105%
105% OLOLTP TP PageA-4 Page A-4 3.0 II IFII 0o FWCF FWCF 0o LRNB '
A t:. CRWE CRWE 2.5 [-.
+-'
'EE 0
~~.=i~~
~~a. 2.0 0_ 2.0 0 rY 0:::~~
0...
0~
C-_
()
~
0 6 1.5 1-o0I
,1.0 1.0 L--_----'-_ _--'--_ _-'--_---'-_-'----'--_ _-'-----'----'-_ _--'-_ _.l...-._---L'--_---'
o0 10 20 30 40 50 50 60 70 80 . 90 100 100 ,110
~~110 .~~
Power (%(% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 1.49 1.49 90 1.55 1.55 50 1.78 1.78 I'
50 1.86
, 1.86 40 1.92 1.92
.I I.
30 2.15 2.15 30 at > 50%F 2.56 at>> 50%F '
25 at 2.77 at5s<50%F 30 at 50%F' 2.53 2.53 .
25 at s< 50%F 2.72 2.72 Figure A.9.3 A.9.3 BOC to EOCLB '
Power-Dependent Power-Dependent MCPR Limits for, for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Times Base Case AREVA NP NP Inc.
ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for for, 105%
105% OL OLTP TP PageA-5 Page A-5 3.0 o
o] FWCF FWCF oa LRNB LRNB AI:J. CRWE CRWE 2.5 F
EE
_j
--l a 0
0_ 2.0 0...
ry a::: a0 a..
0L 0D
()
o
~
1.5 F 0 0 6 a0 1.0 l...-_----L._ _....1...-_ _.L.--_---L_ _---'----_ _.L.--_---L_ _---'----_ _.L.--_----1._ _-1 o0 10 20 30 40 50 60 60 70 80 90 100 110ci 11 Power (% Rated)
Rated)
Power MCPRpp MCPR
(%
(% of rated) Limit Limit 100 1.49 1.49 90 1.55 1.55 50 1.80 1.80 50 1.85 1.85 40 1.92 1.92 30 2.15 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 2.86 30 at <s 50%F 2.65 2.65 25 at 50%F 2.67 25 at > 50%F 2.90 30 at5 at <50%F s 50%F 2.62 25 at5 at <50%F S 50%F' 2.84 Figure A.9.5 BOC to FFTRlCoastdown FigureA.9.5 FFTR/Coastdown Power-Dependent MCPR Power-Oepen'dent MCPR Limits for for, ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Insertion Times Base CaseCase AREVA NP Inc.
~~ANP-2863(NP)~~
~~Unit 1 Cycle 9 Browns Ferry Unit Revision Revision 0 Reload Safety Analysis Analysis for 105%~~
105% OL OLTPTP '~ Page PageA-7A-7 3.5 o FWCF FWCF 0o LRNB LRNB 3.0 A CRWE CRWE
+J
~~'EEE 2.5 2.5~~
~~--.J o_~~
~~02 0..~~
~~0:::~~
~~a-a.. 0 0 0~~
2
~ 2.0 2.0 0
1.5 "I I I I I I I I I I 1.0 o0 10 20 30 30 40 50 60 60 70 80 90 100 100 110 110
, Power (% Rated)
Rated)
Power MCPRpp MCPR
(%of rated)
(% Limit Limit 100 100 . 1.51 90 1.58 1.58 50 ---
50 1.87 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 3.00 30 at s< 50%F . 2.75 25 at s< 50%F 2.96 Figure A.9.6 A.9.6 BOC to FFTRICoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion NSS Insertion Times Times Base Case Case AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1*Cycle
1. Cycle 9 .: Revision 0 Reload Safety Analysis for 105%105% OL OLTP TP Page A-8 PageA-8 3.0 ,.-------,--.,...---,-------,--.,...---,------,----,---,------,.,...,----,
~~I.II-II -I I r~~
~~[o FWCF FWCF o LRNB LRNB CRWE Az~~
~~6. CRWE 2.5 E 0~~
---l
_j 0 0
0_
Q. 2.0 0
~
Of a..
n~
()
2:
A A
1.5 1.5 1-o o o
I .I I I I I I I I
. 1.0 1.0 ~_~_ _~_ _L-_~_ _~_ _L-_~_~~~-~-~-~~
o 10 10 20 30 .40 40 50 50 60 60 70 80 90 100 100 110 110 Power (% Rated)
Power(%
Power Power MCPRpp MCPR
(% of rated)
(% rated) Limit Limit 100 100 1.53 1.53 90 1.58 1.58 50 1.80 1.80 50 1.85 1.85 40 1.94 1.94 30 2.16 2.16 30 at >> 50%F
.30 2.56 25 at >> 50%F 2.77 30 at < 50%F ats50%F 2.53 25 at ~~50%F 30 at>50%F 2.65 25 at at> > 50%F 50%F 2.86~~
<50%F 30 at S50%F 2.65 25 at S< 50%F 2.83 Figure A.9.8 A.9.S BOC toNEOC to NEOC Power-Dependent Power-Dependent MCPR Limits for GEI4 GE14 Fuel TSSS TSSS Insertion Times Times Base CaseCase..
~~. AREVA NP Inc.,~~
~~Inc. "~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Ferry Unit 1 I Cycle 9 Revision Revision 0 Reload Reload Safety Analysis for 105% OLTP OLTP Page A-10 Page A-10 3.0 , . . . . - - - - - - r - - - - r - - - , . . . . - - - - , - - - - - r - - - , . . . . - - - - , - - - - - r - - - - r - - - - - - - r - - - ,
~~o FWCF FWCF o LRNB A~~
~~l>. CRWE CRWE 2.5 1-~~
~~'"""E:t 0~~
~~.::::i 0~~
E~ 2.0 p 0 0.. 0 0:::
C-)
Q..
U
~~2E 0A 1.5 k 1.5 I l>.~~
A 0 0 g 0o 1.0 o
0 10 20 30 40 50 60 70 80 90 90 100 100 110 110 Power (% (% Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 100 1.53 1.53 90 1.58 1.58 50 1.80 1.80 50 1.87 1.87 40 1.94 1.94 30 2.16 2.16 30 at >> 50%F 2.56 25 at >> 50%F 2.77 30 at at:S< 50%F 2.53 25 at ats < 50%F 2.72 Figure A.9.9 A.9.9 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 Fuel ATRIUM-10 TSSS Insertion TSSS Insertion Times Times Base Case AREVA AREVA NP Inc.
~~I""~~
.ANP,.2863(NP)
ANP-2863(NP)
Browns Browns FerryFerry Unit I Cycle 9 Unit 1 Revision Revision 0 Reload Safety Analysis for 105% OL OLTPTP Page A-11 A,.11 3.0 .---------r---,---..---------r---.---,-----.----.----,--,-------r-~__,
O o FWCF FWCF o LRNB A
1:;.. CRWE CRWE 2.5 2.5
'EE
~~t 03~~
~~i 0 0~~
Q. .2.0
.2.0 0::: 0 0.2.
a..
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;.
I:;.
A I:;.
1.5 A 0
a0 I:;.
e 0 II
~~I I I I I I I "I 1.0 o0 10 20 30 40 50 60 70 80 90.~~
~~90. 100 100 110 110 Power (% Rated)~~
Rated)
Power Power MCPRpp MCPR
(% of rated) rated) Limit Limit.
100 1.52 1.52 90 1.58 1.58 50 1.81 1.81 50 1.85 1.85 40 1.94 1.94 30 2.16 2.16 30 at> 50%F 2.65 2.65 25 at > 50%1=
50%F 2.86 2.86 30 at s< 50%F 2.65 2.65 25 at*
at s 50%F 2.83 2.83 Figure A.9.10 A.9.10 BOC to EOCLB Power-Dependent MCPR Power-Dependent MCPR Limits for for
. GE14 Fuel TSSS Insertion.
TSSS Insertion Til11es Times Base Case
, :. ,I' AREVA NP Inc.
'\ :,"
f \'
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 . Revision 0 105%
Reload Safety Analysis for 105%OL OLTPTP . Page A-12 A-12 3.5 II I II I , I o]o FWCF FWCF o LRNB LRNB 3.0 A CRWE CRWE
..... 2.5 E
~
---l Q_
a.
cr_
0:::
CL 00 002 0
~:2 2.0 2.0 0 0 0 1.5 I-1.5 1.0 1.0
~
0o 110
\
10 20 30 40 50 60 70 80 90 100 110 Power (%
Power (% Rated)
Power MCPRPp MCPR
(% of rated) Limit Limit 100 1.56
'.1.56 '.
90 90 1.61 50 50 ---
50 1.87 1.87
, : 40 2.01 30 2.25 2.25 30 at > 50%F 50%F 2.67
.2.67 at > 50%F 25 at> 50%F 2.90 2.90 I'
30 at s5 50%F 2.62 2.62 25 atat*s 50%F 50%F 2.84 2.84 Figure A.9.11 BOC to FFTR/Coastdown Figure A.9.11 FFTRICoastdown Power-Dependent MCPR Limits for Power-Dependent for
, ATRIUM-10 ATRIUM-10 Fuel Insertion Times' TSSS Insertion Times Case Base Case, AREVA NP Inc.
AREVA
ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Ferry Unit Unit 1 I Cycle 9 Revision Revision 0 Reload Safety Reload Safety Analysis for 105% OLTP OLTP Page Page A A-13*
3.5 . - - - - - - - r - - - y - - - . . - - - - - - - - r - - - y II.- - - . . - - - - - - - , - -I - - - r - - - - r - - - -I - - , - . . , .' ; - - - - ,
on FWCF FWCF o LRNB 3.0 A CRWE
'fE2.5 2.5
°_j
~~.:::::i Q.~~
a...
a:::
0... 0 0 U 0
~ 2.0 0
O AO A l!.
I:.
1.5 [- l!. A l!.
0 6 0 III I I I I I I - I
, 1.0 ~_~_ _~_~~-~-~~--~-~--~--~-~--~
o 0 10 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRPp MCPR
(% of rated)
(% Limit 100 '1.54 1.54 90 1.60 1.60 50 ---
S50
,50 1.89 1.89 40 2.02 2.02 30 2.25 2.25 30 at > 50%F 2.76 2.76 25 at > 50%F 3.00 3.00 30 at 50%F 3.01 25 at > 50%F 3.35 30 at s< 50%F 2.71 2.71 25 at s< 50%F 3.04 Figure A.9.13 A.9.13 BOC to. to NEOC Power-Dependent Power-Dependent MCPR Limits forMCPR ATRIU/M-10 Fuel ATRIUM-10 NSS Insertion Times NSS Insertion Times TBVOOS
~~.TBVOOS AREVA NP NP Inc.~~
~~ANP-2863(NP)~~
Browns Ferry Unit 11 Cycle Browns Cycle 9 Revision Revision 00 Reload Safety Analysis for 105% OL Reload OLTP TP . Page A-15 PageA:-15 3.5 ,....----,---,--...,----,....----,---...,----.-----,----,---,.----,----,
- III -I I I I I oO FWCF o LRNB 3.0 3.0 A CRWE
~~E- 2.5~~
---l Q_
-rQ.
(:t:
a_
0 0... 00 0
2
~ 2.0 00 1.5 F 1.5 0 A I.'*. I I I I I 1.0 I L--_.....J....:........;_....l...-_ _L-_.....J.._ _....l...-_ _L-_.....J.._ _....1-_ _.l....-_---L_ _-J 0o 10 10 20 30 . 40 50 60 60 70 80 90 100 100 110 110 Power (%
Power (% Rated)
Rated).
Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.52 1.52 90 1.58 1.58 50 ---
50 .1.83 1.83 40 1.96 1.96 30 2.19 2.19 at > 50%F 30 at 50%F 3.03 25 at at > 50%F 50%F 3.35 30 at ats< 50%F 2.83 .
2.83 25 at5 ats<50%F 50%F 3.17
.3.17 Figure Figure A.9.14 A.9.14 BOC BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for for GE14 Fuel GE14 NSS Insertion NSS Insertion Times Times TBVOOS*
TBVOOS.
AREVA AREVA NP NP Inc.
Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 . Revision 0 105% OLTP.
Reload Safety Analysis for 105% OLTP Page A-16 A-16 3.5 3.5 o FWCF FWCF o
O LRNB
. LRNB 3.0 3.0 [*
A CRWE CRWE 4'-'
2.5
'EE 2.5 0
-_jl Q.
0::::
a..
n 2 0 0 2.0
~ 2.0 0 oA 06 A 0 1.5 F IIII I I I I II 1.0 o0 10 20 30 40 50 50 60 70 80 90 100 110 110 Power (% Rated)
Rated)
Power Power MCPRp MCPRp .
(%
(% of rated) Limit Limit 100 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.86 1.86 40 1.96 1.96 30 2.19 2.19 30 at > 50%F 3.01 3.01 25 at > 50%F 3.35 30 at s< 50%F 2.71 2.71 25 at s< 50%F 3.04 Figure A.9.1S A.9.15 BOC to EOCLBEOCLB Power-Dependent MCPR Limits for Power-Dependent MCPR for ATRIUM-10Fuel ATRIUM-10Fuel NSS Insertion Times NSS Insertion Times TBVOOS TBVOOS
. AREVA NP NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% 105% OLTP OLTP . . Page Page A-17 A-17 3.5 . - - - - - - - r - - . . , - - - . - - - - - - - r - - - - , - - - , - - - - - , - - . . . , - - - . - - - - - - , - - - - ,
3.5 o]o FWCF FWCF*
o LRNB LRNB 3.0 3.0 A CRWE CRWE
..... 2.5
'E
-J
~
Q_
Q.
a:::
a.. 0
()
~ 2.0 00 A "0' S03 1.5 1-1.5 0 A o o II
II I I I I I I 1.0 o0 10 20 30 40 50 50 60 60 70 80 90 100 100 110 110 Power (% Rated) Rated)
Power Power MCPRpp MCPR
(%
(% of rated) Limit Limit 100 100 1.52 1.52 90 1.58 1.58 50 . ---
50 1.85 1.85 40 1.96 1.96 30 2.19 2.19 30 at > 50%F 3.03 25 at > 50%F 3.35 3.35 30 at s< 50%F 2.83 2.83 25 at5 at s<50%F 50%F 3.17 3.17 Figure A.9.16 A.9.16 BOC to EOCLB EOCLBI .
Power-Dependent MCPR Power-Dependent MCPR Limits for GE14 Fuel .
NSS Insertion NSS Insertion TimesTimes TBVOOS TBVOOS AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry UnitUnit 1 Cycle 9 Revision Revision 0 Reload Safety Safety Analysis for 105%
105% OLTP OLTP . Page A-18*
A-18 4.0 , - - - , . - - - , - - - , - - - , . - - - , - - - , - - - , - - - , - - - , - - - - - , - - - ,
oO FWCF FWCF o LRNB LRNB 3.5 a
6 CRWE CRWE 3.0
~E
--.J Q. 2.5 a-0:::
ry (L
U
~
00 0 0" 2.0 0 0 A 6 1.5 1.5 o A 0 o 6 o III I I I I I I I 1.0 o0 10 20 30 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Power MCPRpp MCPR
(% of rated) Limit 100 100 1.55 1.55 90 90 1.61 50 ---
50 1.87 40 2.03 30 2.27 30 at > 50%F 50%F 3.13 3.13 25 at > 50%F 3.47 30 at s< 50%F 2.82 25 at s< 50%F 3.20 Figure A.9.17 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for MCPR for
. ATRIUM-10 ATRIUM-10 Fuel Insertion Times NSS Insertion Times TBVOOS TBVOOS_
AREVA NP Inc.
AREVA
ANP-2863{NP) .
ANP-2863(NP)
Browns Ferry Unit 1. 1 Cycle 9 Revision Revision 0 Reload Safety Analysis for 105% 105% OL OLTPTP . Page Page A-19 A-19 4.0 , - - - - - - - , - - . . . , - - - , - - - - - - - , - - - , - - - , - - - - - - . - - - , - - - . - - - - - - - , . - - - - ,
o]o FWCF FWCF 3.5 o LRNB LRNB A
~~b. CRWE CRWE 3.0 3.0~~
~~+-'~~
~
E
--1 Cl. 2.5 Of 0:::
0...
a-U
~
0 2.0 0
00 1.5 1.5 o 6 o 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) Rated)
Power Power MCPRpp MCPR
(%
(% of rated) Limit Limit
,~ .
100 100 1.54 1.54 90 1.61 50 ---
50 1.90 1.90 40 2.04 2.04 30 2.27 2.27 30 at > 50%F 3.17 3.17 25 at > 50%F 3.47 3.47 30 at s< 50%F 2.95 2.95 25 atats< 50%F 3.35 3.35 Fig*ure Figure A.9.18 A.9.18 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent MCPR Power-Dependent MCPR Limits for for GE14 Fuel NSS Insertion NSS Insertion Times Times TBVOOS TBVOOS AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Ferry Unit Unit 1 Cycle 9 **Revision Revision 0 Safety Analysis for 105% OLTP Reload Safety OLTP PageA-20 Page A-20 3.5 . - - - - - - , - - - . , - - - , - - - . , . - - . , - - - , - - - . , . - - - - r - - - . .I - - - - - - , .I - - - - ,
IIIIII o]
o FWCF FWCF o LRNB
. LRNB 3.0 3.0 A* CRWE CRWE
...... 2.5
'E
~
a.
n::
a-0.. 00 0 00
~ 2.0 0 A
AA 1.5 l-1.5 o A 00 o t:. o I .I I I I I I i I.
1.0 o
0 10 20 30 40 50 60 70 80 90,
~~90. 100 100 110~~
~~.110 Power (% Rated) Rated)~~
Power MCPRpp
.MCPR
(% of rated)
(% Limit Limit 100 100 1.56 1.56 .
90 1.62 50 --
50 1.85 1.85 40*
40 1.98 1.98 30 2.21 30 at > 50%F 3.01 .
3.01 25 at > 50%F 3.35 30 at s< 50%F 2.71 25 at s< 50%F 3.04 Figure A.9.19.
A.9.19, BOC to NEOC Power-Dependent Power-Dependent MCPR Limits for for*
ATRIUM-10 Fuel ATRIUM-10 fuel TSSS Insertion TSSS Insertion Times Times TBVOOS TBVOOS AREVA NP NPlnc:
Inc.
ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 .* Revision Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP Page A-21 3.5 ...-------r-----r---.---------r-----.---.--------,-----r---.-------r----,
I I
~~I 0o FWCF FWCF o LRNB LRNB~~
. 3.0 3.0 A CRWE CRWE 4.
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Ir-n::::
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() 0
~ 2.0 0 0 1.5 1.5 A A 0 0 0 1.0 o0 10 20 30 40 5050 60 70 80 90 .100 110 110 Power. (% Rated)
Power Rated)
Power Power MCPRPp MCPR
(%
(% of rated) Limit Limit 100 100 1.55 1.55 90 1.61 50 ---
50 1.85 1.85 40 1.97 1.97 30 2.20 2.20 30 at > 50%F 3.03 3.03 25 at > 50%F 3.35 3.35 30 at s< 50%F 2.83 2.83 25 at*
ats 50%F 3.17
.3.17 A.9.20 BOC to NEOC Figure A.9.20 NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for for GE14 Fuel TSSS Insertion TSSS Insertion Times Times TBVOOS.
TBVOOS.
AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 'Revision Revision 0 Safety Analysis for 105%
Reload Safety 105% OLOLTPTP. PageA-22 Page A-22 3.5 .--------r----,---.---------r----,---T------r---'T---..--------r----,
3.5 I II , I II o
o] FWCF FWCF oo LRNB LRNB 3.0 3.0 t.
A* CRWE CRWE
+J 2.5
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--l
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() 00
~ 2.0 00 AA 1.5 1 o A o III I I I I I II 1.0 o0 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Rated)
Power (% Rated)
Power MCPRpp MCPR
(%
(% of rated) Limit 100 100 1.56 1.56 90 1.62 1.62 50 ---
50 1.87 1.87 40 1.98 1.98 30 2.21 30 at
~~30 > 50%F at > 50%F 3.01 25 at > 50%F 50%F 3.35 at < 50%F 30 at:S 2.71 at~~
50%F 25 at:S 50%F 3.04 Figure A.9.21 A.9.21 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times TBVOOS TBVOOS AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
. Browns Ferry Unit 1I Cycle 9 Revision 0 .
Reload Reload Safety Analysis Analysis for 105%
105% OLOLTP TP . PageA-23 Page A-23 3.5 o FWCF FWCF o LRNB LRNB 3.0 A CRWE CRWE
+-'
2.5 2.5
'EE
~~i 2_.~~
0..
Q3_"
0:::
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~ 2.0 00 0 A0 A0 1.5 1- o 6 a III I I I I I I I 1.0 o0 10 20 30 40 50 0 6 0 5 60 70 80 90 100 100 110 110 Power Power (% Rated) Rated)
Power Power MCPRpp MCPR
(% of rated)
(% rated) Limit Limit 100 100 1.55 1.55 90 1.61 50 ---
50 1.85 1.85 40 1.97 1.97 30 2.20 ,
30 at >> 50%F 3.03 25 at >> 50%F 3.35 3.35 30 at <s 50%F 2.83 25 at5<50%F ats 50%F 3.17
~~3.17 Figure A.9.22 A.9.22 BOCto BOC to EOClBEOCLB~~
. Power-Dependent Power-Dependent MCPR MCPR Lirriitsfor Limits for GE14 Fuel, Fuel .
TSSS Insertion TSSS Insertion Times Times TBVOOS TBVOOS AREVA NP Inc Inc...
ANP-2863(NP)
ANP-2863(NP}
Browns Ferry Unit 1 Cycle 9 , Revision 0 10S% OLTP Reload Safety Analysis for 105% OLTP . . Page A-24 A-24 4.0 ,-------,----,----,.------,----,----,.----,----,----r------,----,---;
o FWCF FWCF o LRNB LRNB 3.5 6 CRWE CRWE 3.0
'E
t
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Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 100 1.59 1.S9 90 1.64 1.64 50 SO ---
50 SO 1.89 1.89 40 2.05 2.0S 30 2.29 30at 30 50%F at > SO%F 3.13 3.13 125 2S at 50%F at > SO%F 3.47 at5 30 at <50%F S SO%F . 2.82 25 2S at S< SO%F 50%F 3.20 Figure A.9.23 A.9.23 BeC BOC to FFTRlCoastdown*
FFTR/Coastdown.
Power-,Dependent Power-Dependent MCPR Limits for MCPR for ATRIUM-10 ATRIUM-10 Fuel TSSS Insertion TSSS Insertion Times Times TBVeOS.
TBVOOS-AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP PageA-25 Page A-25 4.0 , . . . . - - - - - - , - - - , - - - , . - - - -IIIII 4.0 - - - , - - - , - - - . . - - - - , - - - , - - -.I, - - - ,I - - - - ,
oo FWCF FWCF o LRNB LRNB 3.5 3.5 A6 CRWE CRWE 3.0 3.0
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a-,
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~~30. 40 50 60 70 80 90 100 110 110 Power (% (% Rated)~~
Power MCPR MCPRpp '
(% of rated)
(% Limit Limit 100 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 2.05
- 30 2.29 2.29 30 at > 50%F 3.17 3.17 25 at > 50%F 3.47 30 at s< 50%F 2.95 2.95 25 at ats< 50%F 3.35 3:35
. Figure A.9.24 BOC to FFTRICoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for MCPR GE14 Fuel TSSS TSSS Insertion Insertion Times Times TBVOOS TBVOOS
. AREVA AREVA NP Inc.
ANP-2863(NP) .
ANP-2863(NP)
Browns Ferry UnitUnit 1 Cycle 9 . Revision Revision 0 Reload Safety Safety Analysis for 105%
105% OLTP OLTP PageA-26 Page A-26 3.0 ,.-------r----,---.--------r----,--,---.------,-----,---,------,-,-----,
3.0 oO FWCF FWCF o LRNB A
t:. CRWE 2.5 I-
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0o 10 10 20 !30 40 50 60 60 70 100 . 110 80 90 110 Power (%
Power (% Rated)
.Power
'Power MCPRpp MCPR
(% of rated)
(% Limit Limit*
100 1.49 1.49 90 90 1.55 1.55 50 1.78 50 1.84 1.84 40 1.92 1.92 30 2.15 2.15 30at 30 at > 50%F 2.56 2.!56 25 at > 50%F 2.77 30 at s< 50%F50%F 2.53 25 at s< 50%F50%F 2.72 Figure A.9.25 A.9.25 BOC to NEOC Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion Times NSS Times EOC-RPT-OOS EOC-RPT~OOS Inc.
AREVA NP Inc:
ANP~2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 BroWns FerryUnit . Revision Revision 0
.Reload Reload Safety Safety Analysis for 105% OLTP OLTP A~27 Page A-27 3.0 ,....------r-----r---T"""'""':"---'----,-----r----r------,-----r------'--r---:--~--__,
o FWCF FWCF o LRNB LRNB
/:;.'
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00 Aoo o 1.5 I-oo o
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f. 1.0 '--_---'-_ _ --'-_ _.L...-_----'-_ _....1-_ _.L...-_----'-_ _....1-_ _-'----,-:-----1._-----"-,-I 0o 10 10 20 30 . 40 50 50 60 70 80 9 900 1 0 0
.100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit
i
" 100 1.49 1.49 90 1.55 1.55*
50
~~50. 1.80 .~~
1.80 50 1.83 1.83 40 1.92
'1.92 30 2.15 2.15 30 at > 50%F 50%F 2.65 at> 50%F 25 at'> 50%F 2.86 30 at s< 50%F 2.65 .
25 atsat < 50%F 50%F 2.83 Figure A.9.26 A.9.26 BOC to NEOC JJower~Dependent MCPR Limits for Power-Dependent GE14 Fuel .
GE14 NSS Insertion
. NSS Insertion TimesTimes EOC .. RPT-OOS EOC-RPT-OOS AREVA NP Inc., Inc..
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0
'Revision Reload Safety Analysis for 105%105% OL TP OLTP Page A-28
, PageA-28 3.0 ~---r---r---.-------r----r---"------r---r---"-----.----'
III I o
O FWCF FWCF o ' LRNB LRNB A
ll. CRWE CRWE 2.5 l-
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o IIIII I I I , - I I 1.0 o
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10 20 30 , 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit 100 1.49 1.49 90 1.55 1.55 50 1.78 50 1.86 1.86 40 1.92 1.92 30 2.15 2.15
> 50%F 30 at >50%F 2.56 25 at > 50%F 50%F 2.77 at < 50%F 30 ats 2.53 25 at s< 50%F 2.72 I'
Figure A.9.27 A.9.27 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 Fuel ATRIUM-10 NSS Insertion NSS Insertion Times Times EOC-RPT-OOS EOC-RPT -005 AREVA NP Inc: Inc.
ANP ..2863(NP)
ANP-2863(NP)
Browns Browns Ferry Unit Unit 1 Cycle 9 Revision 0 Revision Reload Safety Reload Safety Analysis for 105% OL TP OLTP Page A-29 A-29 3.0 , - - - - - - r - - . , - -I
-,.-----r--.. IIII
,---,----r--..,- --,-----,-----,
I- .
o]
o FWCF FWCF o LRNB LRNB A
A OCRWE
'CRWE 2.5 1-
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o
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0 0 A A A 1.5 1-o II
II I I I I I I 1.0 ' - - _ - - L_ _--'-~_-'--_'___---'-_ _---'-_ _- ' - - _ , _ _ - - - ' - - - - - - - ' - - - - ' - - - - ' - - ' . - - - - '
0o 10 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit 100 1.49 1.49 90 1.55 .
1.55 50 1.80 1.80 50 1.85 1.85 40 1.92 1.92 30 ,,2.15 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 at < 50%F 30 ats 50%F 2.65
.2.65 25 ats50%F at < 50%F 2.83
'2.83, Figure A.9.28 A.9.28 BOCto BOCto EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for
. GE14 GE14 Fuel NSS Insertion Times NSS Times EOC-RPJ:
EOC-RPT-OOS -005 '
AREVA NP Inc.
, ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 .' Revision Revision 0 Reload Safety Analysis Analysis for 105%
105% OL OLTP TP .. Page A-30 A-30 3.5 ,------,----,---,------,----,---.,-----,----,----.------,.,.:.-.,----,
IIIII . I I -
oO FWCF FWCF o LRNB 3.0 1- a CRWE -
-+J 2.5 -
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6 0
,j, II I I I I I I 1.0 0 10 20 30 40 50 60 60 70.
70 80 90 100 110 110 Power (% Rated)
Rated)
" Power Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.52
~~1.52 90 1.59 1.59 50 ---~~
50
.50 1.86 1.86 40 2.00 2.00 30 2.24 2.24 30 at > 50%F 2.67 2.67 at > 50%F 25 at> 2.90 2.90 30 at <s 50%F 50%F 2.62 2.62 25 ats at < 50%F50%F 2.84 Figure Figure A.9.29 A.9.29 BOC BOC to FFTR/Coastdown FFTRICoastdown Power-Dependent Power.Dependent ,MCPR Limits for MCPR
. ATRIUM*tO ATRIUM-10 Fuel NSS Insertion Times NSS Times EOC-RPT-OOS EOC-RPT *OOS AREVA NP Inc: Inc.
. ANP-2863(NP)
ANP-2863(NP}
1 Cycle 9 Browns Ferry Unit 1. Revision Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP Page Page A-31 3.5 3.5 I III I .- -I
[]o FWCF FWCF o0 LRNB LRNB 3.0 I-3.0 A CRWE CRWE
--i-J 2.5 F 4i E
~~=i a.~~
0:::
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<.) 0 2.0 1- 0
2
~~~ 0 1.5 F 1.5 I~~
~~I- I I I I I I I " I 1.0 0o 10 20 30 40 50 60 60* 70 80 90 100 100 110 110 Power (%~~
Power (% Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit I;
100 1.51 90 1.58 1.58 50 50 ---
50 1.87 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F 30ats 2.75 25 ats at < 50%F 2.96 Figure A.9.30 A.9.30 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel .
NSS Insertion NSS Insertion Times Times EOC-RPT-OOS EOC-RPT -005
. AREVA AREVA NP Inc.
, ANP-2863(NP}*
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Browns .'. Revision Revision 0
. Reload Reload Safety Analysis Analysis for 105% OL OLTP TP A-32*
Page A-32
.3.0
.3.0 o FWCF FWCF o LRNB
~A CRWE CRWE 2.5 I-
'EE
-j 0
~~=i 0~ 0 0.._ 2.0 00 0:::~~
CL
~~2 0~~
U
~~E AA 1.5 I-o ~ 0 o o~~
II- I I I I I I I I 1.0 L - _ - - - L ._ _-'-'-C--_'--_----'-_ _-'-'-_.,....-'--_----'-_ _-'-'-_---.-.l...-_---1_ _--J 0o 10 20 30
.30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.53 1.53 90 1.58 1.58 50 1.80 1.80 50 1.85 1.85 40 1.94 1.94.
30 2.16 2.16
> 50%F 30 at > .2.~6 2.56 at > 50%F 25 at> 2.77 2.77 30 at<5 ats 50%F 50%F 2.53 25,at ~~. CRWE CRWE 2.5 [-~~
o
+'
~~'EE~~
~~i 0 0~~
0.._ 2.0 2.0 0::: 0 r0 CL 0...
0
~
A A -...
1.5 1.5 1 oo 0 0o o
I III I I I II 1.0 '--_--'-_ _-'---_ _. l - _ - - - - L_ _-'---_ _.1....-_----L_ _-'---_ _.1....-_----L_ _- I o
0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.52 1.52 90 1.58 1.58 50 1.81 50 1.84 1.84 40 .1.94 30 *2.16 2.16 30 at at> > 50%F 2.65 2.65 25 at > 50%F 2.86 2.86 30 at5 ats<50%F 50%F 2.65 .
2.65 25 at5 ats<50%F 50%F 2.83 2.83 Figure A.9.32 A.9.32 BOC to NEOC Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel TSSS Insertion Times TSSS Insertion Times EOC*RpT EOC-RPT-OOS -OOS AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 Revision Reload Safety Analysis for 105%
105% OL OLTPTP . . Page A-34 A-34 3.0 o FWCF FWCF o . LRNB LRNB *.
A t:. CRWE 2.5 F
+-'
'E
°-E 00
=:i 0 c_ 2.0 2.0 0
~~0. 0 et::~~
CL a-)
()
~ 0A 1.5 k t:. 0 Q o0 1.0 '--_----'-_ _-'-_ _.1....-_--'-_ _- ' -_ _.1....-_--'-_ _----'-_ _"'--_---1._ _--'
o0 10 20 30 40 50 50 60 70 80 90 100 100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRnp MCPR
(% of rated) Limit Limit 100 1.53 1.53 90 1.58 1.58 50 1.80 1.80 50 1.87 1.87 40 1.94 1.94 30 2.16 2.16 30 at > 50%F 2.56 50%F 25 at > 50%F 2.77 30 at ~~50%F 2.65 25 at > 50%F 2.86 30 at <s 50%F50%F 2.65 25 at s< 50%F50%F 2.83 Figure A.9.34 BOC to EOClB EOCLB .~~
~~Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel GE14 Insertion Times TSSS Insertion Times EOC-RPT-OOS EOC-RPT -OOS AREVA NP Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Ferry Unit 1I Cycle 9 Browns Revision Revision 0 Reload Reload Safety Analysis for 105% OL OLTPTP Page A-36
~~'Page A-36 3.5 3.5 o FWCF FWCF o LRNB LRNB 3.0 3.0 A* CRWE CRWE~~
~~...... 2.5~~
~~'E 2.5~~
~~--l a..~~
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~~2 2.0 2.0 0.~~
~ 0 1.5 t- 0 .A 0
,b, 0 c I~~~ ~ 0 1.0 L - _ - - ' -_ _- ' -_ _' - - _ - - ' -_ _- ' -_ _' - - _ - - ' -_ _- ' -_ _-'--_----L_ _--'
o0 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power (% Rated)
Rated)
Power MCPRp MCPRp
(%
(% of rated) Limit Limit 100 . 1.56 1.56 90 1.61 50 --
50 1.87 1.87 40 2.01 30 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 30 at*
at S 50%F . 2.62 25 at ats< 50%F 2.84 A.9.35 BOC to FFTRlCoastdown' Figure A.9.35 FFTR/Coastdown Power~Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM*10 TSSS Insertion Times TSSS Insertion Times EOC-RPT-OOS EOC*RPT *OOS ,
AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 Reload Safety Analysis for 105% 105% OL OLTPTP PageA-37 Page A-37 3.5 I II I I II Oo FWCF FWCF 0o LRNB LRNB 3.0 aI:> CRWE CRWE
'EE2.52.5
~~i CL Q.~~
0:::
a.. 0
() 0 0 0
~ 2.0 0 0
1.5 [-
o 6 I'
I II I I I I I I 1.0 ' - - _ - - L_ _ .:....l-_ _"--_----L._ _--L..._ _"--_----L._ _---'-_ _-'--_---1_-'----.J
,0
.0 10 20 30 40 50 60 60 70 80 90 100 110 110 Power (% Rated) Rated)
Power Power MCPRpp MCPR
(% of rated) Limit Limit 100 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.89 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at <s 50%F 50%F 2.75 25 at <
,25 s 50%F50%F 2.96 Figure Figure A.9.36 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for for GE14 GEI4 Fuel Insertion Times TSSS Insertion Times EOC~RPT EOC-RPT-OOS -OOS AREVA NP NP Inc.
i' i'
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 ; Revision 0 Reload Safety Analysis for 1 05% OLTP 105% OLTP. . Page A-38 PageA-38 3.5 ,...-----,--..,---,-----,----,----,-'-----,---:---,----,------.--:----,
3.5 IIIIIIII I
[]o FWCF FWCF oo .. LRNB LRNB 3.0 6. CRWE CRWE
...... 2.5
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0:::,
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(;)
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0o 10 20 30 40 50 60 70 80 90 .. 100" 100 110 110 Power (%
. Power (% Rated)
Power MCPRp MCPR"
(%of rated)
(% Limit Limit 100 1.52 1.52 90 1.59 1.59 50 50 ---
50 1.84 1.84 40 2.00 30 2.24 30at 30 at>> 50%F 2.67 25 at > 50%F 2.90 2.90 30 at*
at S 50%F 50%F 2.62 2.62 25 at 5S 50%F 50%F 2.84 '.
2.84 A.9.37 BOC to NEOC Figure A.9.37 Power-Dependent MCPR Limits for Power-Dependent for ATRIUM-10 ATRIUM-10 Fuel "
NSS Insertion Times' NSSlnsertion Times.
FHOOS FHOOS AREVA NP NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9
'Browns : Revision Revision 0 Reload Reload Safety Analysis for 105% OL OLTP TP , PageA-39 Page A-39 3.5 r----,-----,-:---,-----,-----,---,------,-----,---,....------r----,
oo] FWCF FWCF o
0, LRNB LRNB 3.0 a CRWE
+J 2.5
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~~.::::i 0.~~
a:::
0...
0~ 00 0
C-)
2: 2.0 0 1.5 I " II I I I I I I I 1.0 L-_----'-_ _--1-_ _.L.-_----'-_ _--1-_ _.L.-_----'----,---,----'-_ _-'----_----L_----':.....J 0o 10 10 20 30 40 50 60 70 80 90 . 100 110 110 Power (% (%' Rated)
Rated)
Power MCPRPp MCPR I I
(% of rated)
(% Limit Limit 100 1.51 90 1.58 1,58 50 ---
50 1.87 1.87 40 2.01 30 2.24 t; , 30 at >50%F
> 50%F 2.76
!, 25 at > 50%F 50%F 3.00 30 at s< 50%F 2.75 25 ats at < 50%F 2.96 Figure A.9~38 A.9.38 BOC to to,NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel GE14 NSS Insertion NSS Insertion Times Times FHOOS FHOOS
,AREVA AREVA NP Inc. Inc.
, .~ - ..'
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 . Revision 0 Reload Safety Analysis for 10S% 105% OL OLTP.
TP . Page A-40 Page A-40 3.5 , - - - - - . - - - - , - - - , - - - - - . - - - - , - - - , - - - - - , - - - - . - - - , - - - - - - , - - - - ,
o FWCF FWCF o LRNB 6A CRWE 3.0
+'
2.5 2.5
'E 41
~~.=i Q.~~
0:::
0... 00 0.
~ 2.0 I00 1.5 I I I II 6*6I0 o 1.0 '--_----L._ _--'--_ _"---_----L_ _--'--_ _"---_----L_ _--'--_ _. . L . - _ - - - I ._ _- '
0o 10 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Power MCPRP Power MCPRp
(% of rated)
(% Limit Limit 100 100 1.52 1.S2 90 1.59 1.S9 50 SO --
50 SO 1.86 1.86 40 2.00 2.00 30 2.24 2.24 30 at > SO%F 30.at> 50%F 2.67 2.67 25 at > 50%F 2.90 2.90 30 at ~~50%F 2.76 25 at > 50%F 50%F 3.00 3.00 30 ats~~
'30 at < 50%F 50%F 2.75 25 ats at5<50%F 50%F 2.96 2.96' Figure A.9.40 BOC to EOClB EOCLB Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel GE14 .
NSS Insertion*
~~NSS Insertion Times' Times FHOOS FHOOS AREVA NP Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Ferry Unit Unit 1 Cycle 9 . Revision Revision 0 Reload Safety Safety Analysis for 105% OLTPOLTP . Page A-42 A-42 3.5 3.5 ,-------r--__r_--r__-----r~-__r_--r__-__r--__.__--,__-__,_--__,
~~I II I I I o[] FWCF FWCF o LRNB LRNB 3.0 A CRWE CRWE~~
~~-+J~~
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()
2.0 2.0 000
~ 0 1 ,
~: . 1.5 1 A 6 ¢ 0 IIIII I I I 1.0 00 10 10 2020 30 30 40 50 60 70 80 90 100 110 110 Power (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated) .
(% Limit Limit 100 1.56 1.56 90 1.61 50 ---
50 1.86 1.86 40 2.01 30 2.25 2.25 30 at > 50%F 30at> .2.67 2.67 25 at > 50%F 25 2.90 2.90 30 at <s50%F 50%F 2.62 2.62 25 at: <50%F at s 50%F 2.84 2.84 Figure A.9.41 BOC to NEOC Power~Dependent MCPR Limits for Power-Dependent for
.. ATRIUM*10 ATRIUM-10 Fuel Insertion Times TSSS Insertion Times FHOOS FHOOS
1*
AREVA NP Inc...
NP Inc
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit Unit I1 Cycle 9 Revision Revision 0 Safety Analysis for 105% OLTP Reload Safety OLTP Page A-43 A-43 3.5 ....----'----r---,---..----..,.---,---...----..,.---.----...-----.----,
oEl FWCF o0 LRNB 3.0 3.0 A CRWE E2.5 2.5 E
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0... 00 0 0 0 0
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o0 o0 o0 1.0 II I I I I I l...-_---L._ _- ' -_ _.l...-_---L_ _- ' -_ _.l...-_---L_ _--L-_ _.l.--_-...I._ _- l I
o
~~0. 10 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)~~
Rated)
Power MCPRpp MCPR
(% of rated)
(% rated) Limit 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.89 1.89 40 2.02 30 2.25 30 at > 50%F 50%F 2.76 25 at > 50%F 3.00 3.00 30 at <s 50%F 50%F 2.75 25 at < 50%F 25 ats 50%F 2.96
. Figure A.9.42BOC A.9.42 BOC to NEOC Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel GE14 Insertion Times TSSS Insertion Times FHOOS FHOOS AREVA NP NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 . Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP PageA-44 Page A-44 3.5 I i I I I II o
O FWCF FWCF o LRNB LRNB 3.0 CRWE CRWE
+-'
2.5
'E
~~.::J ry0.~~
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0... 00 0~
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III I I I I I I I 1.0 L - _ - - - - L_ _- ' - - - - - ' _ . L . . . - _ - - - - L_ _- - ' -_ _.L...-_----'-_ _-'--'-_._-'-----I.c..,..,.....----'
o.
0 10 10 20 30 . 40 50 60 70 80 80 90 100.
100 110 110 Power* (%
Power (% Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.56 1.56 90 1.61 50 --
50 1.87 1.87 40 2.01 30 2.25 30 at > 50%F 50%F 2.67 2.67 25 at > 50%F 50%F . 2.90 30 at s< 50%F 2.62 2.62 25 at
~~25 at5 s<50%F 50%F 2.84 Figure A.9.43 BOC to EOClB Figure EOCLB Power-Dependent MCPR Limits for .~~
Power-Dependent ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times .
FHOOS FHOOS AREVA AREVA NP Inc.
NPlnc:
i*
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision Revision 0 Safety Analysis for 105%
Reload Safety 105% OLOLTPTP Page A-45 3.5 I "I I*II o
O FWCF FWCF o LRNB LRNB 3.0 A CRWE CRWE
'EE 2.5 2.5
~~..::J~~
,-j 0..
~
0... 0 0 0 0
~ 2.0 2.0 0
1.5 1.0 o 10 10 20 30 40 50 60 60 70 80 90 100 100 ,110 10
. , Power (% Rated)
Rated)
., ,, Power Power MCPRnp MCPR
(%
(% of rated) ,Limit Limit
,r.
100 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.89 40 2.02 30 2.25 30 at >> 50%F 2.76 2,.76 25 at > 50%F at> 3.00 3.00 30 at < 50%F, ats 50%F 2.75 '
25at*
25 ats 50%F 2.96 Figure A.9.44 BOC to EOCLB EOCLB Power-Dependent
. Power-Oependent,MCPR MCPR Limits for for GEI4 Fuel GE14 TSSS Insertion
. TSSS Insertion Times Times FHOOS FHOOS AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
. Browns Ferry Unit 1 Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP .. PageA-46 Page A-46 3.0 ,-------,---,---,----,-----,---,---,-------,---,---..--------r.,..-----,
3.0 I III o3 o FWCF FWCF o LRNB LRNB A
I:>. CRWE CRWE 2.5 I-
+'
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~~.::i 0~~
_j 0.. 2.0 0 0a-0::
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0
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Rated)
Power Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.49 1.49 90 1.55 1.55 50 --
50 1.89 1.89 40 1.92 1.92 30 2.15 2.15 30 at>
at > 50%F 2.56 2.56 25 at > 50%F 25at> 50%F 2.77 2.77 30 at s< 50%F 50%F 2.53 25 at s< 50%F 50%F 2.72 Figure A~9.45 A.9.45 BOC to NEOC NEOC Power-Dependent Power.Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM*10 NSS Insertion NSS Insertion Times Times PLUOOS PLUOOS AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision Revision 0 Safety Analysis for 105%
Reload Safety OLTP 105% OLTP PageA-47
, Page A-47 3.0 r - - - . , - - - - , - - - , - - - . , - - - - , - - - , - - - - , - - - - , - - - , . - - - - , - - - - ,
o0 FWCF FWCF o LRNB A
~~b. CRWE CRWE 2.5 F~~
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1.5 0 A III I I I I I II 1.0 o0 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power. (% Rated)
Rated)
Power Power MCPRpp MCPR
. (%
(% of rated) rated) Limit Limit 100 100 1.49 1.49 90 1.55 1.55 50 ---
50 1.87 1.87 40 1.92 1.92 30 2.15 2.15 30 at > 50%F 2.65 25 at > 50%F 2.86 30 at < 50%F ats 2.65 25 at > 50%F 2.56 25 atat> > 50%F 2.77 30 at < 50%F 30ats50%F, 2.53 25 at s< 50%F 2.72 Figure A.9.47 BOC to EOCLB FigureA.9.47 Power-Dependent MCPR Power-Dependent MCPR Limits for ATRIUM-10 ATRIUM-10 Fuel ,
~~NSS Insertion Times NSS Insertion Times PLUOOS PLUOOS AREVA NP Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
~~Browns Ferry Unit 1 1.*Cycle Cycle 9 Revision 0 Reload Safety Analysis for 105%~~
~~.Reload 105% OLTP OLTP Page A-49A-49 3.0 , . - - - - - - - , - - - - , -~~
I
~~- - , - - - - - - - , - - -iIIII oo FWCF FWCF o LRNB LRNB 6A CRWE CRWE 2.5 1-~~
~~'E_J~~
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~~a. 0 0::: 0 0_~~
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0 U 0
~ 0 I 0 0 6
A 1.5 1.5 I-0 I~~0 0 1.0 0o 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Power MCPRP MCPRp
(%of rated)
(% Limit Limit 100 1.49 1.49 90 1.55 1.55 50 50 ---
50 1.91 40 1.92 1.92
- 30 2.15 2.15 30 at > 50%F 2.65 2.65 25 at > 50%F 2.86 2.86 30 atsat s 50%F 2.65 2.65 25 at S< 50%F 50%F 2.83
.Figure A A.9.48
..9.48 BOC to EOCLB .
Power-Dependent Power.Depen~ent MCPR Limits for GE14 Fuel NSS Insertion NSS Insertion Times Times PLUOOS PLUOOS*
AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry Unit 1 Cycle Cycle 9 . Revision 0 Reload Reload Safety Analysis for 10S% 105% OLOLTP TP A-50 Page A-SO 3.5 o FWCF FWCF o LRNB LRNB.
3.0 a CRWE CRWE
..... 2.5 2.5
'E
~~.J n-0.~~
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<.) 0
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0 10 20 30 40 50 . 60 70 80 90 100 100 110 110 .
Power (% (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.52 1.S2 90 1.59 1.S9 50 SO ---
50 SO 1.92 1.92 40 2.00 30 2.24 30 at >
30 at > 50%F SO%F 2.67
~~2.67 25 at> 50%F~~
2Sat>SO%F 2.90 2.90 30 at S< SO%F 50%F 2.62 25 at 2S at:S<50%F SO%F 2.84 Figure A.9.49 BOe BOC to FFTRICoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion Times NSS Insertion Times PLUOOS PLUOOS AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry Unit 1I Cycle 9 Revision 0 Revision Reload Reload Safety Analysis Analysis for 105% OLTP for*105% OLTP Page A-51 A-51.
3.5 I I . I I I I I o3 o FWCF FWCF o LRNB LRNB 3.0
~~3.0 *A , CRWE~~
+-'
2.5 2.5
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~ 00 0 A 1.5 I " I* " I I I I I I I I 1.0 o0 10 20 30 40 5 0 6 .60 50 0 70 80 90 100 100 110 110 Power (%
Power (% Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.51 90 1.58 1.58 50 ---
50 1.91 40*
40 2.01 30 2.24 30 at > 50%F 2.76 25 at > 50%F 3.00 3.00 at < 50%F 30 ats 2.75 2.75 25 ats at < 50%F 2.96 Figure A.9.50 A.9.S0 BOC to. FFTR/Coastdown to FFTRICoastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion NSS Insertion Times Times PLUOOS PLUOOS AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP}
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Safety Analysis for 105% OLTP OLTP Page A-52 A-52 3.0 , - - - - - - - , - - - - , - - - , - - - - - - - , - - - - , - - - , - - - - - - , - - - - , - - - , - - - - - - r - - - - ,
o FWCF o LRNB 6a CRWE 2.5 1-
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A 1.5 1-III I I I I I I I 1.0 '--_--'-_ _ --'-_ _.l....-_----'-_ _--'-_ _-'--_----'-_ _--'--_ _-'--_----L _ _--'
0o 10 20 30 . 40 50 50 60 70 80 90 100 100 110 110 Power Power (% (% Rated)
Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.53 1.53 90 1.58 1.58 50 --
50 1.89 1.89 40 1.94 1.94 30 2.16 2.16 30 at>
at > 50%F 2.56 25 at at> > 50%F 2.77 30 at <s 50%F 2.53 25 at 50%F 2.65 2.65 25 at > 50%F 50%F 2.86 2.86 at5<50%F 30 ats 50%F 2.65 2.65 25 ats at < 50%F 2.83 2.83 Figure A.9.52 BOC to NEOC Figure A.9.S2 NEOC Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel
~~.GE14 TSSS Times TSSS Insertion Times PLUOOS PLUOOS AREVA NP Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
~~Browns Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 Reload Safety Analysis for 105%~~
~~Reload 105% OL OLTPTP . Page A-54 A-54 3.0 I II I II -~~
~~o FWCF FWCF o LRNB LRNB A~~
~~t:. CRWE CRWE 2.5 I-~~
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~~°-E~~
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A 1.5 I-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)Rated)
Power MCPRp MCPRp
(%
(% of rated) Limit Limit 100 . 1.53 1.53 90 1.58 1.58 50 --
50 1.91 40 1.94 _
1.94 30 _2.16 2.16 30 at >> 50%F 2.56 2.56
.25 25 at >> 50%F 2.77 2.77 30 at <s 50%F-50%F 2.53 2.53 25 at 50%F 2.65 2.65 25 at > 50%F 2.86 at < 50%F 30 ats 2.65 25 at S< 50%F 2.83 Figure A.9.54 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel TSSS TSSS Insertion Times Times PLUOOS PLUOOS
~~.AREVA NP Inc.~~
~~,AREVA~~
~~ANP-2863(NP)~~
Browns Ferry Browns Ferry Unit Unit 11 Cycle 9 Revision Revision 0**0 Reload Safety Reload Safety Analysis Analysis for for 105% OL OLTPTP I Page A-56A-56 3.5 , - - - - - - r - - . . , - - - - . - - - ' - - - - - -IIIIIIr - - . . , - - - - , - - ' - - - - , - - ' - , - - - . - - - - -Ir - - - - ,
~~3 FWCF o LRNB 3.0 1- CRWE~~
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0.. 00
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1.5 1.5 1.0 1.0 o
0 10 10 20 30 40 50 60 70 80 . 90 100.
100 110 110 .
Power (%
.. Power (% Rated)
Power MCPRpp MCPR
(% ofrated)
(% of rated) Limit 100 100 1.56 1.56 90 1.61 .
50 ---
50 1.92 1.92 40 40 2.01 30 2.25 2.25 30 at 30 at >> 50%F 50%F 2.67 2.157 25 atat> > 50%F 50%F 2.90 30 atat s< 50%F 2.62 25 at*
at s 50%F 50%F 2.84 2.84 Figure A.9.55 A.9.55 BOC BOe to FFTR/Coastdown FFTRICoastdown .
Power-Dependent Power-Dependent MCPR Limits MCPR limits.for for ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times .
PLUOOS
. PLUOOS
.AREVA AREVA NP NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit Unit 1 Cycle 9 Revision 0 Revision Reload Reload Safety Analysis for 105% OL OLTPTP' Page A-57A~57 3.S 3.5 , . . . . - - - - , - - -I- - r : - - - r - - - -I - , - - -*- , - - - - rI - - - - , - - : . . - - , - - - - r I- - - - - - r - - - - ,
oO3 FWCF FWCF o LRNB 3.0 A CRWE-CRWE
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! ~ 1.0 '---_-:-'-----'_-'--,--_.L...-_----'-_ _--'-_ _.L...-_----'-_ _--'-_ _-'---_---L_ _...:.J 0o 10 10 20 30 40 SO' 50- 60 70 80 , 90 90 100 110 110 Power (% (% Rated)
Power MCPRp MCPRp
(% of rated)
(%of Limit Limit 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.91 40 2.02 30 '2.25 2.25 30 at > 50%F 50%F 2.76 25 at > 50%F 50%F 3.00 30 at s< 50%F 2.75 at* 50%F 25 ats 2.96 2.96 Figure A.9.56 Figure FFTRICoastdo~n ,
A.9.S6 BOC to FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel, Fuel TSSS TSSS Insertion Times Times PLUOOS PLUOOS AREVA NP Inc.
,AREVANP
, "i ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 Reload Safety Analysis for 105%
105% OL TP .
OLTP Page A-58 A-58 .
3.5 IIIIII I o
o3 FWCF FWCF o LRNB LRNB 3.0 A CRWE CRWE
-+'-'
2.5
'EE
~
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A 03 [
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'I, 0 e IIII I I I I I I 1.0 0 10 20 30 40 50 .60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRpp MCPR
(%
(% of rated) . Limit Limit 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.84 1.84 40 1.96 1.96 30 2.19 2 ..19 at > 50%F 30 at::' 3.01 25 at > 50%F 3.35 3.35 30 at at5<50%F s 50%F 2.71 at < 50%F 25 ats 50%F 3.04 Figure A.9.57 A.9.57 BOC to NEOC Power-Dependent MCPR Limits for Power-Dependent
. ATRIUM-10 Fuel NSS NSS Insertion Insertion TimesTimes EOC-RPT-OOS
. EOC-RPT -OOS and TBVOOSCombined TBVOOS Combined
... AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 I Cycle Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP Page A-59 A-59 3.5 o FWCF FWCF o LRNB LRNB 3.0 3.0 CRWE CRWE
...... 2.5
'E
i
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0... 0 02 S2.0
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0 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPR MCPRpp
(% of rated)rated) Limit 100 1.52 1.52 90 1.58 1.58 50 50 ---
50 1.83 1.83 40 1.96 1.96 30 2.19 2.19 30 at > 50%F 3.03 25 at > 50%F 50%F 3.35 30 ats at < 50%F 50%F 2.83 25 atat5 s<50%F 50%F 3.17 3.17 Figure A.9.S8 A.9.58 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel GE14 NSS Insertion Times Times EOC-RPT-OOS EOC-RPT -OOS and TBVOOS Combined AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% 105% OLOLTP TP . Page PageA-60 A-60 3.5 ,..-------,---,---,-------,----,---,-----,-----,---,------,----:----,
3.5 II I I I I I -
oo FWCF
-FWCF o LRNB 3.0 A CRWE 3.0
..... 2.5
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Rated)
Power MCPRPp MCPR
(% of rated)
(% Limit Limit 100 1.52
--1.52 90 1.58 1.58
.50
.50 --
50 1.86 1.86 40 1.96 1.96 30 2.19 2.19 30at 30 at > 50%F 3.01 25 at > 50%F 3.35 3.35 30 at < S 50%F 50%F-- 2.71 25 at < S 50%F 50%F 3.04 3.04
\ ~ .
Figure A.9.59 Figure A.9.59 BOC to EOCLB -
Power-Dependent MCPR Limits for Power-Dependent for
. ATRIUM*10 ATRIUM-10 Fuel NSS Insertion TimesTimes EOC-RPT-OOS EOC*RPT*005 and TBVOOS TBVOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1. 1*Cycle Cycle 9 Revision 0 Reload Safety Analysis for 105% OL OLTP TP . Page Page A-61 3.S 3.5 , - - - - - - . , . - - - , - - - , - - - - - . , . - - - , - - - , - - - - - , - - - - - - , - - - , . - - - - - - - r - - - - ,
oo] FWCF o LRNB LRNB 3.0
/j,'" CRWE CRWE
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1.0 L - _ - - - L_ _---L-_ _.L.-_----1._ _---L-_ _.L.-_----1._ _----L-_ _.L.-_-,-l_--'----.l o0 10 20 30 40 SO 50 60 60 70 80 90 100 110 110 Power (% Rated) Rated)
Power Power MCPRP
,MCPR p
(% of rated) Limit 100 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.85 1.85 40 1.96 1.96 30 2.19 2.19 30 at >> 50%F 3.03 25 at >> 50%F 3.35 3.35 30 at ats < 50%F 2.83 25 at5 ats <50%F 50%F 3.17 3.17
, Figure A.9.60 BOC to EOCLB Power~Dependent MCPR Limits for Power-Dependent GE14 Fuel .
Insertion Times NSS Insertion Times EOC-RPT-OOS EOC-RPT -OOS and TBVOOS Combined Combined AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 .. Revision Revision 0 Reload Safety Analysis for 105%
105% OL OLTPTP Page A-62 PageA-62 4.0 .------.----r---,-----.----,---~-_.--_._----'-.__-....,...--_,
I - I I I I I I " - .
o FWCF o LRNB 3.5 A
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~~1.0 I II II I-1.0 0 10 20 30 40 50 60 70 80 90.~~
90 . 100.
100 . 110 110
. Power (%(% Rated)
Rated)
Power MCPRp MCPRp
(% of rated) Limit Limit 100 1.55 1.55 90 1.61 50 ---
50 1.87 1.87 40 2.03 2.03 30 2.27 2.27 30at 30 at > 50%F 3.13*
3.13' 25at 25 at >> 50%F 3.47 30 at <s 50%F 2.82 2.82 25 at ~~50%F~~
~~>*SO%F 3.17~~
~~.3.17 25 at>~~
2S at > SO%F 50%F 3.47 30 at ats< SO%F*
50%F, 2.95 2.9S*
t
, . 25 at < 50%F 2S ats SO%F 3.35 3.3S A.9.62 BOC to FFT.RlCoastdown Figure A.9.62 FFTR/Coastdown Power-Dependent MCPR Limits for Power-Dependent MCPR for.
~~GE14 Fuel NSS Insertion Times NSS Insertion Times EOC-RPT-OOS EOC-RPT -OOS and TBVOOS Combined .~~
~~TBVOOS Combined AREVA NP Inc. .'~~
~~ANP-2863(NP)~~
~~ANP-2863(NP}~~
~~.Browns Browns Ferry Unit 1 Cycle 9 . Revision 0 105% OL Reload Safety Analysis for 105% TP.~~
~~OLTP. Page A-64~~
. PageA-64 3.5 3.5 IIIIII I I o FWCF FWCF o LRNB LRNB 3.0 3.0 A CRWE CRWE
~~+""~~
~~2.5 2.5~~
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~~2 0~~
~~2 2.0 2.0 0 0~~
A A 0 1.5 1-0 b..
A 0 0o 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 . MCPRpp MCPR
(% of rated) Limit Limit 100 100 1.56 1.56 90 1.62 1.62 50 50 ---
50 1.85 1.85 40 1.98 1.98 30 2.21 at > 50%F 30 at> 50%F 3.01 25 at > 50%F 25at> 50%F 3.35 30 at s< 50%F . 2.71 25 at S< 50%F 3.04 Figure A.9.63 BOC to NEOC Figure NEOC Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel .
TSSS Insertion Times Times EOC-RPT-OOS EOC-RpT -OOS and TBVOOS Combined AREVA NP Inc.
. ANP-2863(NP}
ANP-2863(NP)
I Cycle Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105%
105% OL OLTPTP . Page A-65 3.S 3.5 o]
o FWCF FWCF o0. LRNB LRNB 3.0 A* CRWE CRWE
...... 2.5 2.S
'E
~
a.
°-
a::: 2r0 0... 00.
() 2.0 00.
~ 2.0
~~00. "~~
0 A
1.5 l.S 1- A l!J. A l!J.
0 0 0
0. 0. o I" I I I I I I I I I 1.0 o0 10 20 30 40 SO 50 60 60 70 80 90 100
~~110 110 Power (%(% Rated)~~
Power MCPRpp MCPR
(%of rated)
(% Limit Limit 100 1.55 1.55 90 1.61 50 ---
50 1.85 1.85 40 1.97 1.97 30 2.20 2.20 30 at at>> 50%F 3.03 3.03 25 at > 50%F 3.35 3.35 30 at s< 50%F 2.83 2.83 25 at*
at s 50%F 3.17 3.17 Figure A.9.64 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel TSSS TSSS Insertion Insertion Times Times EOC-RPT-OOS EOC-RPT -005 and TBVOOS Combined Combined*
AREVA AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit BroWns Unit 1 Cycle 9 Revision Revision 0 Reload Safety Safety Analysis for 105% OLTP OLTP . Page A-66 A-66 3.5 3.5 .--------.----,---..-------.----.----,-----,----.-------'-,-----,----,----,
oo FWCF FWCF o LRNB LRNB 3.0 a CRWE CRWE
-+-'
'E 4-1 2.5
.....J Oa 0.
0:::
fy (L 0 U 0 0
~
2.0 2.0 0 00 O0 O 0 AA 1.5 o A o Il. 0 c 1.0 III I I I I I I I L - _ - - - L_ _--1-_ _. L - _ - - - L_ _.....L-_ _.L-_----L._ _-L..._ _..I..-_---'-_ _---'
o0 10 20 30 30 40 50 60 60 70 80 90 100 100 10 110 Rat~d)
Power (% Rated)
Power MCPRpp MCPR
(%
(% of rated) Limit 100 100 . 1.56 1.56 90 1.62 1.62 50 --
50 1.87 1.87 40 1.98 1.98 30 2.21 30at 30 at >> 50%F 3.01 25 at >> 50%F 3.35 30ats50%F*
30 at5<50%F 2.71 25 at s< 50%F 3.04 Figure A.9.65 A.9.65 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 and TBVOOS CombinedCombined
, AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 1. Cycle 9 Revision 0 Revision Safety Analysis for 105% OLTP Reload Safety OLTP Page A-67 A-67 3.5 3.5 .--------,-----,---.--------,-----,---.--------,----,----,-------r----,
I III I o FWCF FWCF o LRNB LRNB 3.0 1- A CRWE CRWE 2.5 I-
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0.. 00 0 0
~
2.0 [-
00 o A0 AA 1.5 [-
III I I I I I I 1.0
. 60 60 70 o0 10 20 30 40 50 50 70 80 80 90 90 100 100 110 110 Power Power (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated) Limit Limit 100 100 1.55 1.55 90 1.61 50 ---
50 1.85 1.85 40 1.97 1.97 30 2.20 30 at > 50%F 3.03 3.03 25 at > 50%F 3.35 3.35 30 at S< 50%F 2.83 25 atS at S 50%F 3.17 3.17
.Figure A.9.66 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel lSSS Insertion Times TSSS Times EOC-RPT-OOS EOC-RPl -OOS and TBVOOS Combined and lBVOOS Combined AREVA NP Inc. Inc..
ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Reload Safety AnalysisAnalysis for 105%
105% OL OLTP TP Page A-68 PageA:*68*
4.0 oo3 FWCF FWCF o LRNB 3.5 3.5' A CRWE CRWE 3.0 E
~
41
--l Q. ~2.5 2.5 0:::
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1.0 0 10 . 20
~~20. 30 40 50 60 70 80 90 100 110.~~
110 Power (%(% Rated)
Rated)
Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.59 1.59 90 1.64 1.64 50 --
50 1.89 1.89 40 2.05 2.05 30 2.29 2.29 30 at> 50%F 30 at> 50%F 3.13 3.13 25 at > 50%F 3.47 3.47 at!<50%F 30 at s 50%F 2.82 2.82 25 at ~~50%F 50%F 3.17 3.17~~
~~, J at > 50%F 25 at> 50%F 3.47 30 ats~~
~~'30 at < 50%F 50%F 2.95 25 at s< 50%F 3.35~~
. Figure Figure A.9.68A.9.68 BOC BOCto to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel GE14 TSSS Insertion Times TSSS Times EOC-RPT-OOS EOC-RPT -OOS and TB"OOS TBVOOS Combined
~~, AREVA Inc~~~
~~AREVA NP Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Ferry Unit 1 Cycle 9 , Revision Revision 0 Reload Safety Safety Analysis for 105% OLTP OLTP PageA-70 Page A-70
~~'3.5 3.5 , . - - ; - - - ,II- - - - , - - -I. , - - - -I - y - - -I - , - - -I, - - - - -I y---- I y - - -II, - - - - - r - - - ,~~
~~o0 FWCF o ' LRNB 3.0 a CRWE~~
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0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRPp MCPR
(% of rated) Limit Limit 100 1.52 1.52 90 1.59 1.59 50 --
50 1.84 1.84 40 2.00 2.00 30 2.24 30 at > 50%F 50%F 2.67 25 at > 50%F 50%F 2.90 30 at s< 50%F 2.62 25 at at*s 50%F 2.84 Figure A.9.69 BOC to NEOC Figure A.9.69 NEOC Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 ATRIUM*10 Fuel NSS Insertion Insertion Times Times EOC-RPT-OOS and FHOOSCombined EOC*RPT*OOS FHOOSCombined
, AREVA NP Inc. Inc~
ANP-2863(NP)
ANP-2863(NP)
Unit I1 Cycle 9 Browns Ferry Unit 0' Revision 0 Revision Reload Safety Safety Analysis for 105% OLTP OLTP Page A-71 3.5 ....------..---,---..-------..---,---..-------,-----r---..---------r----,
o FWCF o LRNB 3.0 A
~~t. CRWE~~
'E 2.5
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0A 1.5 1.5 1-II . I I I I -. I I 1.0 1.0 I I L...-_---'-_ _. . . . L - - - ' - _ ' - - - _ , , - - ' -_ _- ' -_ _' - - - _ , , - - ' -_ _- ' -_ _'---_----1._ _- '
o 0 10 10 20 30 40 50 60 70 80 90 100 110 110 Power (%(% Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.51 90 1.58 1.58 50 ---
50 1.87 1.87 40 2.01 30 2.24 2.24 30 at > 50%F 2.76 2.76 25 at > 50%F 3.00 30 at ats< 50%F 2.75 2.75 25 at5ats<50%F 50%F' 2.96 2.96 Figure Figure A.9.70 A.9.70 BOC to NEOCNEOC Power-Dependent Power-Dependent MCPRLirriits MCPR Limits for. for
, GE14 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT-OOS EOC-RPT -OOS and FHOOS Combined Combined AREVA NP Inc.
AREVA
ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP . Page A-72 3.5 , . . . . - - - - - r - - - - r - - - . - - - - - - r - - - , - - - r - - - - - - r - - - , - - - r - - - - - r - - - . , . - - - - ,
3.5 o
0 FWCF FWCF o LRNB LRNB 3.0 3.0 " CRWE CRWE
..... 2.5
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a,-
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a.. 0
(.)
~ 2.0 2.0 0 1.5 I I I I I I I I I I 1.0 o0 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power (% (% Rated)
Power MCPRPp MCPR
(% of rated) _ Limit -
100 100 1.52 1.52 90 1.59 1.59 50 --
50 1.86 1.86 40 2.00 30 2.24 30 at > 50%F 50%F 2.67 25 at > 50%F 50%F 2.90 30 at s< 50%F 2.62 25 at s< 50%F -2.84 2.84 Figure A.9.71 A.9.71 BOC to EOCLB Power-Dependent MCPR Limits for Power-Dependent
- ATRIUM-10 ATRIUM*10 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT-OOS EOC*RPT*OOS and FHOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns FerrYFerry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% OL OLTPTP Page A-73A-73 3.5 . - - - - - - - - r - - - - r - - - , - - - - - - - r - - - - r - - - , - - - - - - - r - - - , - - - . - - - - - - - - , . - - - i o FWCF o LRNB 3.0 A
/),. CRWE-CRWE
'EE2.5 2.5 o_
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ry n:::
0.... 0 0 2.0 2.0 0
~~2: 0 0~~
1.5 1.5 F I " II I I I I I I I .
1.0 1.0 L..-.._----L._ _- - ' - -_ _.L...-_----'-_ _--'--_ _.L..-_----'-_ _--L-_ _.L...-_--'"---'-'----'
0o 10 10 20 26 30 40 50 60 70 80 90 100 110 110 Power (% Rated)
Power (% Rated), '
Power MCPRp MCPRp
(% of rated) Limit Limit 100 1.51 90 1.58 1.58 50 ---
50 1.87 1.87 40 2.01 30 2.24
> 50%F 30 at >50%F 2.76
" 25 at > 50%F 50%F 3.00 30 at < 50%F 30ats 50%F 2.75 25 at s< 50%F 2.96 2.96 Figure A.9.72 A.9.72 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for'fore.
GE14 Fuel GE14 NSS Insertion Times NSS Times EOC-RPT-OOS EOC-RPT -005 and FHOOS Combined Combined AREVA NP NP Inc.
.ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 , Re",ision Revision 0 '
Reload Safety Analysis for 105% 105% OL OLTPTP : Page A-74 PageA-74 3.5 , - - - : - r -I- - , - - - , - " ' - - - - - , - -III- , - - - , - - - - - , - - - , - - - , - - - - - . - - - - ,
3.5 oO FWCF FWCF o LRNB '
LRNB 3.0 1- Az CRWE CRWE
..... 2.5 1
'E4ý
~~=i Q.~~
CL 0::
0y 0.. 0 0
() 0
~ 2.0 l- 0 0
06 1.5 I- A 1:>.. 0 o III I I I I I I I.
1.0
.0 10 20 30 30 40 50 60 60 70 80
,80 , 90
~~90. 100 100 110 110 Power (% Rated) Rated)~~
Power MCPR MCPRpp ,
(% of rated) Limit 100 100 1.56 1.56 90 1.61 50 . ,
50 1.86 1.86
, I 40 2.01 30 2.25 30 at >
'30 at > 50%F 50%F 2.67 25 at >> 50%F 2.90 30 atats< 50%F 2.62 25 at <S50%F 50%F 2.84 Figure A.9.73 A.9.73 BOC to NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel '
TSSS Insertion TSSS Insertion TimesTimes '
EOC-RPT-OOS EOC-RPT -005 and FHOOS Combined Combined AREVA NP Inc.
NPlnc:
.. (.,
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1I Cycle 9 , Revision Revision 0 Analysis for 105% OL Reload Safety Analysis OLTP TP " ,Page A-75 Page A-75 3.5 II I I I I - I o FWCF F~CF o LRNB LRNB 3.0 3.0 A CRWE CRWE
+'
2.5
~
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() 0 0 0
~~2 2.0 0 0~~
0O 0 0 " 0F 1.5 0A0 ,A o o o o o o I 1.0
\. j o0 10 20
.20 30 ,40 40 ' 50 60 60 70 80 90
~~90. 100 110 110 Power (% (% Rated)~~
Rated)
Power MCPRpp MCPR
(% of rated)
(% rated) Limit 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.89 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 25at> 3.00 30 at <s 50%F 50%F 2.75 25 at 50%F 2.67 at > 50%F 25 at> 2.90 30 at5 at s<50%F 50%F 2.62 25 at s 50%F 50%F . 2.84 Figure A.9.75 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR for Limits for ATRIUM-10 ATRIUM-10 Fuel. Fuel TSSS Inser1ion Insertion Times Times EOC-RPT EOC-RPT-OOS -OOS and FHOOS FHOOS Combined Combined AREVA NPNP Inc.
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Browns Ferry Unit Unit 1 Cycle 9 Revision Revision 0 Reload Safety Reload Safety Analysis for 105% 105% OLTP OLTP . Page A-77 A-77 3.5 r - - - - - - r - - - - , - - - ' - - , - - - - - r - - - - , - - - , - - - - - , - - - - . - - - , - - - - - - , - - - - ,
~~on FWCF FWCF o LRNB LRNB 3.0 k aA CRWE CRWE~~
~~..... 2.5 I-E~~
~~--l Q-0.~~
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~~a..~~
~~a- 0 00 0~~
~~0 0~~
~~~ 2.0 - 0 0~~
~~1.5 H o 0 6 Q~~
III I I I I I I I 1.0 L . . . - _ - - - - L_ _- - ' - - - - ' - _ ' - _ - - - L_ _--'-_ _. l - _ - - - - ' -_ _----'--_ _-'--_-----'-_ _--'
~~o0 10 20 30 40 50 50 60 70 80 90 100 100 110 110 Power Power (% Rated)~~
~~Rated)~~
~~Power Power MCPRpp MCPR~~
~~(% of rated)~~
~~(% Limit Limit 100 100 1.54 1.54 90 1.60 1.60 50 ---~~
50 1.89 1.89 40 2.02 30 2.25 2.25 30 at >> 50%F 2.76 25 at >> 50%F 3.00 30 at <s 50%F 2.75 2.75 25 at 50%F 50%F 2.56 2.56 25 at > 50%F 50%F 2.77 2.77 at5<50%F 30 ats 50%F . 2.53 2.53 25 ats at < 50%F 2.72 2.72 Figure A.9.77 A.9.77 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for
~~.. *ATRIUM-10 ATRIUM-10 Fuel NSS Insertion NSS. Insertion Times Times EOC-RPT-OOS EOC.;RPT -005 and PLUOOS PLUOOS Combined Combined AREVA AREVA NP Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Ferry Unit 1 Cycle 9 Revision Revision 0 Reload Safety Analysis for 105% 105% OL TP OLTP Page A-79 3.0 ,-----'---r--...,---,-----r--...,---,------,----,---,------,---,
~~oo FWCF FWCF o LRNB A~~
~~I:l. CRWE 2.5~~
~~'EE~~
t
--.l 00 Q
0.. 2.0 0:: 00 0y 0L 0..
()
A
~
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1.5 o A A o 6
IIII I I I I I 1.0 L...-_---L._ _.....1-_ _-'---_---L_ _.....1-_ _-'------'----L_ _--L..._ _.l...-._---LI_ _---l o0 10 20 30 40 50 50 60 70 80 90 100 100 110 110 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 1.87 1.87 40 1.92 1.92 30 2.15 2.15 30 at > 50%F at> 2.65 2.65 25 at >> 50%F 2.86 30 at < 50%F ats 2.65 2.65 25 at < 50%F ats 2.83 Figure A.9.78 A.9;78 BOCto BOC to NEOC Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel .
NSS Insertion.
NSS Insertion Times Times EOC-RPT-OOS EOC-RPT -OOS and PLUOOS Combined Combined AREVA AREVA NP Inc.Inc..
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 CycleCycle 9 Revision 0 Reload Safety Analysis for 105%105% OL OLTP TP ., PageA-80 Page A-80 3.0 I I I I I I I . I 00 FWCF FWCF o0' LR'NB LRNNB
"". CRWE CRWE 2.5 F-
'EE
._j 0
---1 Q_
~~0. 2.0 0 0:::~~
0y 0_
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~~2: 0 0~~
"" 0I ,
0 1.5 [ I ' .0 I ,I I II
,0 1.0 L...-_---L._ _...:.J...:...---'_.l....-_----L_ _----L-_ _L-_----L_~....:.J....._ _..l.._:.._ ____1_ ____l o0 10 20 30 40 ' 50 50 60 60 70 . 80 90
~~90. 100.~~
1,00. . 110 110 Power (% Rated)
Power Rated)
Power MCPR MCPRPp ,
(% of rated) Limit Limit 100 100 . 1.49 1.49 90 1.55 1.55
, 50 50 --
50 1.91 40 1.92 1.92 30 2.15 2.15 30 at > 50%F
>50%F :2.56 2.56 25 at > 50%F 2.77
.2.77 30 at <50%F 30ats50%F' 2.53 25 ats at <50%F 50%F 2.72 Figure A.9.79 A.9.79 .BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 Fuel
~~ATRIUM-10 NSS NSS Insertion Insertion Times Times EOC-RPT~OOS and PLU~OS EOC-RPT-OOS PLUOOS Combined AREVA NP NP Inc.~~
ANP-2863(NP)
ANP-2863{NP}
Browns Ferry Unit 1 Cycle 9 Revision 0
Revision Reload Safety Analysis for 105% OLTP OLTP Page Page A-81 3.0 , - - - - - r - - - -I*IIIIIII r - - - , - - - - - r - - - - r - - - - - ' - ,I - - - - , - - - , - - - , - - - - - , - - - - ,
oo FWCF FWCF o LRNB LRNB A
t:. CRWE CRWE 2.5
~
t
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\ 00 Q.. 2.0 2.0
~ 00 n...Q-) \0 u
~
1.5 I " I I I I I I I I
. 1.0 o0 10 20 30
~~4 0 40 50 60 70 80 90 100 100 1.10 1.10 Power (% Rated)Rated)~~
Power MCPRpp MCPR
(% of rated)
{% rated} Limit Limit 100 1.49 1.49 90 1.55 1.55 50 ---
50 1.91 40 1.92 1.92*
30 2.15 2.15 30 at >> 50%F 2.65 25 at >> 50%F 2.~6 2.86 30 at <S 50%F 2.65 .
25 at ~~> 50%F 2.67 25at 25 at >> 50%F 2.90 30 atats< 50%F 2.62 25 at ~~CRWE CRWE~~~~
~
~~2.5 E~~
~~.:::i 0.~~
0:::
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00 0
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1.5 1-1.0 '--...,...---1._ _....1...---'-_.1....-_----'-_ _....1...-_ _.1....-_----'-_ _-'-'-_ _........_ - - - - 1 ._ _---'
0o .10 10 20 .. 30 40 50 50 60 70 80 80* 90 100 100 110 110 Power (%
Power. (% Rated)
Rated)
I.
Power MCPRpp Power MCPR
(% of rated)
(% rated) Limit 100 1.51 90 1.58 1.58 50 ---
50 1.91 40 40 2.01 30 2.24 30 at > 50%F 2.76 25 at>
at > 50%F . 3.00 30 at <s 50%F 50%F 2.75 25 ats at < 50%F 50%F 2.96 Figure A.9.82 Figure A.9.82 BOC to FFTRICoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for limits for GE14 Fuel NSS NSS Insertion Times Times EOC-RPT-OOS EOC-RPT -OOSand and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
Browns Browns Ferry Unit Unit 1 Cycle 9 Revision 0 Revision Reload Safety Safety Analysis for 105%*
105% OL OLTPTP 'Page A-84 .
Page A-84 3.0 r - - - - - y - - - - , -I - - , - -I - - - y - - -I - , - -
3.0 "
-,--,-- I
- - , - - - , - - -I, - - - - I, - - - ' ,
o FWCF FWCF o LRNB
~~LRNB a~~
.t:. CRWE CRWE 2.5 1-
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~~=J 0~~
Q_ 0 rYa. 2.0 0 0:::
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0
.~ 0A A
1.5 1.5 1-II I I I I I I I 1.0 '--_--'-_ _--'-_ _.L--_--'-_ _--'---'--_.L--_--'-_ _--'-_ _..1...-_---'-_ _- '
1.0 o
0 10 20 30 40 50 50 60 70 80 . 90 100 100 110 110 Power (%.
Power (% Rated)
Power MCPRP MCPRp
(% of rated)
(% Limit Limit 100 1.53 1.53 90 1.58 1.58 50 ---
50 1.89 1,89 40 1.94 1.94 30 2.16 2.16 30 at > 50%F 50%F 2.56 25 at > 50%F 50%F 2.77 30 at~50%F at : 50%F 2.53 25 at s< 50%F 2.72 Figure A.9.83 A.9.83 BOCBOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Liniits for Limits ATRIUM-10 Fuel .
. TSSS TSSS Insertion Times Times EOC-RPT-OOS*and EOC-RPT-OOS PLUOOS Combined and PLUOOS AREVA NP Inc.
AREVA
'~ .
ANP-2863(NP) ,
ANP-2863(NP)
Browns Browns Ferry Unit Unit 1 Cycle 9 Revision Revision 0
,Reload Reload Safety Analysis for 105% OL OLTPTP , PageA-85 Page A-85
,I:
~~3.0 IIIII I I I o0 FWCF FWCF o LRNB A~~
~~I:>. CRWE CRWE 2.5 I-E~~
~
-j
-l 0 0
Q._ 2.0 2.0 0 0::: 0 0y n,"
0...
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I:>.
I:>. AA 1.5 1- e I:>.
e IIII I I 1.0 I I L - _ - - - L_ _--1-_ _.L...-_----L_ _--L..-_ _.L...-_----L_ _--L..-_ _-L------.:---L - I
_ _--l
~~0 0 10 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (%~~
Power (% Rated)
Power MCPRP MCPRp
(% of rated) Limit Limit 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.87 1.87 40 1.94 1.94 30 2.16 2.16 30 at > 50%F 2.65 25 at > 50%F 2.86 30 atsat < 50%F 2.65 I,
25 atsat < 50%F 2.83 2.83 Figure A.9.84 Figure A.9.84BCC BOC to NEOCNECC Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel TSSS Insertion Times TSSS Insertior'l Times EQC-RPT EOC-RPT-OOS -CCS and PLUOOS Combined PLUOOS Combined AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 .. Revision 0 "Revision 105% OL Reload Safety Analysis for 105% OLTP TP PageA-86 Page A-86 3.0 oo] FWCF FWCF oLRNB o LRNB
~~t. A CRWE CRWE 2.5 I-~~
'E
-J 0
...J 0
Q. 2.0 0 0
a_
0::::
0... I 0 . '
()
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. 1.5 1.0 o0 10 20 30 40 . 50 60 60' 70 70 80 90
~~90. 100 100 110 110 Power (%(% Rated)~~
Rated)
Power MCPRpp MCPR
(%
(% of rated) rated) Limit Limit 100 100 1.53 1.53 90 1.58 50 --
50 1.91 40 1.94 30 2.16 2~ 16 30 at > 50%F 2.56 25 at > 50%F 2.77 2.77 30 at5 ats<50%F 50%F 2.53 25 at ats< 50%F 2.72 2.72 Figure Figure A.9.85 A.9.85 BOC to EOCLBEOCLB Power-Dependent MCPR Limits.fof Power-Dependent Limits for ATRIUM-IO ATRIUM-10 Fuel TSSS Insertion TSSS Insertion Times Times EOC-RPT-OOS EOC-RPT-OOS and PLUOOS Combined Combined AREVA NP Inc~ Inc.
ANP-2863(NP)
ANP-2863(NP)
Ferry Unit 1 Cycle Browns Ferry Cycle 9, 9' , Revision 0 105% OL
.Reload Safety Analysis for 105% TP OLTP PageA-87 Page A-87 3.0 3.0 I*I I
~~I "I . I I o0 FWCF FWCF~~
" o0 LRNB LRNB A
/j.
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1.5 1.5 F I~ ~ 0 1.0 0o 10 20 30 40 50 50 60 70 80 , 90 100 110 110 Power (%
Power (% Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.91 40 1.94 1.94 30 2.16 2.16 30 at > 50%F 2.65 2.65 25 at > 50%F 2.86 2.86 30 at s< 50%F 2.65 2.65 25 at < 50%F ats 2.83 2.83 Figure A.9.86 A.9.86 BOC to EOCLB EOCLB, Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel-Fuel .
TSSS TSSS Insertion Times Times EOC-RPT-OOS EOC-RPT -OOS and PLUOOSPLUOOS Combined Combined AREVA NP Inc.
AREVA
, , '" ~
ANP-2863(NP)
~~Browns Browns Ferry Unit 1 Cycle 9 'Revision~~
'Revision 0 Reload Reload Safety Analysis Analysis for, for 1105% OLTP 05% OL TP Page A-88 A-88 3.5 3.S o FWCF FWCF o LRNB LRNB 3.0 a CRWE CRWE
'EE 2.5 2.S
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Rated)
Power Power MCPRPp MCPR
(% of rated) Limit Limit 100 100 1.56 1.56 90 1.61 50 50 ---
50 1.92 1.92 40 2.01 30 2.25 2.25 30 at at>> 50%F 2.67 2.67 25 at > 50%F 2.90 2.90 30 at <s 50%F 2.62 2.62 25 at ats< 50%F 2.84 Figure A.9.87 A.9.87 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 ATRIUM-10 Fuel TSSS TSSS Insertion Times Times EOC-RPT-OOS and PLUOOS Combined EOC-RPT-OOS Combined AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 11.Cycle 9 , Revision Revision 0 Reload Safety Analysis for 105%
105% OL OLTPTP " Page A-89 PageA-89 3.5 ,-------r---.----....--'------r---.----..------..,.----r---..-------,------.
oo] FWCF FWCF o LRNB 3.0 A CRWE
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Power Power MCPRpp MCPR
(% of rated)
(% rated) Limit Limit 100 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.91 40 2.02 30 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at < 50%F ats 2.75 2.75 25 at < 50%F ats ' 2.96 Figure A.9.88 A.9.88 BOe BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR MCPR Limits for for GE14 Fuel '
Insertion Times TSSS Insertion Times EOC-RPT-OOS EOC-RPT -OOS and PLUOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry Ferry Unit 1I Cycle 9 : Revision Revision 0 Reload Safety Analysis Analysis for 105%
105% OL OLTPTP Page A-90 A-90
) !
4.0 IIIIIII , I o3 FWCF FWCF o0 LRNB 3.5 A
t:. CRWE CRWE 3.0
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o 0 10 20 20 30 40 Power 50 60 70 80 90 100 110 110 1:
, . Power (% (% Rated) Rated)
Power MCPRpp MCPR
('(%
Yo of rated) Limit Limit 100 1.55 1.55 .
90 1.61 50 --
50 1.87 1.87 40 2.03
.2.03
, .30 30 2.27 30 at > 50%F . 3.13 3.13 1~ :
25 at >>50%F
~~25 50%F ,3.47 3.47 30 at <s 50%F 50%F 2.82 2.82~~
" 25ats50%F 25 at < 50%F 3.20 Figure A.9;89 A.9.89 BOC to NEOC '
Power-Dependent Power-Dependent MCPR Limits limits for ATRIUM-1 Fuel ATRIUM-tO NSS Insertion Times N$S Times TBVOOS and fHOOS TBVOOS FHOOS Combined Combined AREVA NP Inc.
i I '
ANP-2863(NP)
ANP-2863(NP) 1 Cycle Browns Ferry Unit 1. Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% TP OLTP Page A-91 4.0 I II I I II. .
ro o FWCF FWCF o LRNB LRNB 3.5
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Rated)
Power Power MCPR MCPRpp
(% of rated)
(% rated) Limit Limit 100 100 1.54 1.54 90 1.61 50 50 ---
50 1.90 1.90 40 2.04 30 2.27 30 at >> 50%F 3.17 3.17 25 at > 50%F 3.47 30 at ats< 50%F 2.95 2.95 25 at ats< 50%F 3.35
. Figure A.9.90 A.9.90BOCto BOG to NEOC NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for for GE14 Fuel NSS Insertion Times NSS Insertion Times TBVOOS TBVOOS and fHOOS FHOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Browns Ferry Unit Unit 1 Cycle 9 . Revision Revision 0 Reload Safety Analysis for 105% OL OLTPTP Page PageA-92A-92 4.0 . - - - - - - r - - - , - - - r - - - - - - T - - - , - - ' - - - r - - - - - , - - - - - r - - ' - - - , - - - - - . - - - ,
4.0 o3 FWCF FWCF o LRNB 3.5 6a CRWE 3.0 E
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I.
o 0 10 20 30 40 50 50 60 70 80 90 100 100 110
. Power (% (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated) Limit Limit 100 1.55 1.55 90 1.61 50 --
50 1.87 1.87 40 2.03 30 2.27 30 at > 50%F 3.13
3.13 25 at > 50%F 3.47 3.47 30 at <S 50%F 2.82 25 at ats< 50%F 3.20 3.20 Figure Figure A.,9.91 A,9.91 BOC BOCto to EOCLB Power-Dependent Power-Dependent MCPR Limits forfor ATRIUM-10 Fuel ATRIUM-10 NSS Insertion Times Times TBVOOS TBVOOS and fHOOS FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit I1 Cycle 9 Browns ..Revision Revision 0
.Reload Reload Safety Analysis for 105% OL OLTP TP PageA-93 Page A-93 4.0 I'II
~~I I I "~~
o13 FWCF FWCF 3.5 3.5 o0 LRNB "A
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0o 10 20 30 40 50 60 70 *80 80 . 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp MCPRp
(%of rated)
(% Limit Limit 100 1.54 1.54 90 1.61 50 ---
50 1.90 1.90 40 2.04 2.04 30 2.27 2.27 30 at>
at > 50%F 50%F 3.17 3.17 25 at> 50%F50%F 3.47 30 ats at < 50%F 2.95 2.95 25 at s< 50%F 3.35
.3.35 Figure A.9.92 A.9.92 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion NSS Insertion Times Times .
TBVOOS and FHOOS Combined Combined AREVA AREVA NP Inc. Inc.*
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Ferry Unit Unit 1 Cycle 9 Revision 0 Revision Reload Safety Safety Analysis for 105% OL OLTP TP Page PageA-94A-94 4.0 , - - - - , - - - , - - - - , . - - - - - , - - - - . - - - , . - - - - - - , - - - - . - - - , . - - - - - - , - - - - ,
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Power MCPRp MCPRp ,
(%
(% of rated) rated) Limit Limit 100 1.59 1.59 90 1.64 1.64 50 -
50 1.89 1.89 40 2.05 2.05 30 2.29 2.29 30 at >> 50%F 3.13 3.13 25 at >> 50%F 3.47 30 at s< 50%F 2.82 2.82 25 at s< 50%F 3.20 A~9.93 BOC to NEOC Figure A.9.93 NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel TSSS Insertion TSSS Insertion TimesTimes TBVOOS and fHOOS FHOOS Combined Combined AREVA NP Inc. ,
ANP-2863(NP)
ANP-2863(NP)
Browns Browns FerryFerry Unit I Cycle 9 Unit 1 Revision 0 Revision Reload Safety Analysis for 105% OL OLTPTP Page A-95 A-95 4.0 r - - - - , - - - - - , - - - , - - - : - . - - - - , - - - . - - - - - - , - - - . - - - . - - - - - - , - - - ,
o0 FWCF FWCF 3.5 o0 LRNB
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.30 40 50 60 60 70 80 90 100 100 110 110 Power (% (% Rated)
Power MCPRp MCPRp
(%
(% of rated) Limit Limit 100 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 2.05 30 2.29 2.29 30 at > 50%F 3.17 3.17 25 at > 50%F 3.47 30 at s< 50%F 2.95
2.95 25 at s< 50%F 3.35 3.35 Figure Figure A.9.94 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for GE14Fuei GE14 Fuel TSSS TSSS Insertion Times Times TBVOOS and FHOOS Combined Combined AREVA NP Inc.
ANP-2863(NP) ..
ANP-2863(NP)
Browns Browns Ferry Unit Unit 1 Cycle 9 , Revision Revision 0 .
Reload Reload Safety Safety Analysis for 105% OL OLTPTP Page A-96 PageA-96 4.0 II I II, oO FWCF FWCF.
o LRNB 3.5 a
I>. CRWE CRWE 3.0
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0o 10 20 30 40 50 50 60 70 80 90 100 110 110 Power Power (% (% Rated)
Rated)
. Power ..MCPRP MCPRp
(%
(% of rated)'
rated) . Limit Limit 100 1.59 1.59 90 1.64 1.64 50 --
50 1.89 1;89 40 2.05 2.05
'30
'30 2.29 2.29 30 at >> 50%F 3.13
.3.13 25 at >>50%F 50%F 3.47 30 at s5 50%F 50%F 2.82 2.82
. 25 at s-<50%F 50%F 3.20 3.20 Figure A.9.95A.9.95 BOC to EOCLB EOCLB Power-Dependent MCPR Ljmits
. Power-Dependent Limits for for .
ATRIUM-10 ATRIUM-10 Fuel Fuel.,'
Insertion Times TSSS Insertion Times TBVOOS TBVOOS and FHOOS Combined Combined AREVA NP Inc.
NP Inc.,
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1I Cycle Browns Cycle 9 Revision 0 Reload Reload Safety Analysis for 105% OLOLTP TP Page A-97 4.0 IIIIIII . I o FWCF FWCF 0.
o* LRNB 3.5 t.
A* CRWE CRWE 3.0
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A AA 1.5 t. 6 o I I I I I I I I I I 1.0 o0 10 20 30 40 50 60 70 80 90 100 110 110 Power (% Rated)
Rated)
Power MCPRpp MCPR
(%
(% of rated) Limit Limit 100 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 3.17 25 at > 50%F 50%F 3.47 30 ats 50%F at <50%F 2.95 at: <50%F 25 ats 50%F 3.35
.Figure A.9.96 A.9.96 BOC to EOCLB EOCLB' .
Power-Dependent Power-Dependent MCPR Limits for for .
GE1.4 Fuel GE14 TSSS Insertion Times lSSS Insertion Jimes TBVOOS and lBVOOS and FHOOS Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit'1Unit 1 Cycle 9. 9* '. Revision 0 Reload Safety An'alysis Analysis for 105%105% OL OLTP TP Page PageA-98A-98 3.5 . . . - - - - - , - - - - . - - - - , - - - - - - T - - - . - - - - , - - - - - , - - - - , - - - - . . , - - - - - , - - - - ,
o FWCF FWCF o0 LRNB LRNB 3.0 A CRWE CRWE
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1.0 o
0 10 10 20 30 40 50 60 70 70 80 80 . 90 90 .100
~~100 110~~
'.110 Power (% (% Rated).
Rated).
Power rv1CPR*
MCPRp .p .
(% of rated)
(% Limit Limit 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.89 1.89 40 .. 1.96 1.96 30 2.19 2.19 30 at >
30 at > 50%F 50%F 3.01 25 at > 50%F 50%F 3.35 30 ats at < 50%F 50%F 2.71 25 ats at < 50%F 50%F 3.04 Figure A.9.97 A.9.97 SOCBOC to NEOC Power-Dependent MCPR Limits for Power-Dependent for
. ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Times TSVOOS and PLUOOS TBVOOS PLUOOS CombinedCombined AREVA NP Inc.
NPlnc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 10S% 105% OL OLTP TP . Page A~99 A-99 3.5 , - - - - - - , - - - - , - - - , - - -II- - , - - - - .. III o FWCF FWCF o LRNB LRNB 3.0 3.0 A I>. CRWE CRWE
..... 2.5
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.10 20 30 40 50 60 60 70 80 90 *100 100 110 110 Power (% (% Rated)
Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.52 1:S2 90 1.58 1.S8 50 SO ---
50 SO 1.87 1.87 40 1.96 1.96 30 2.19 2.19 30 at > SO%F 50%F 3.03 3.03 25 2S at > SO%F 50%F 3.35 3.3S 30 at S< 50%F SO%F 2.83 2.83 25 at*
2S 50%F at S SO%F 3.17 3.17 Figure Figure A.9.98 A.9.98 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel
~~GEI4 NSS Insertion NSS Insertion Times Times TBVOOS and PLUQOS TBVOOS PLUOOS Combined AREVA Inc.~~
AREVA NP Inc.*
ANP-2863(NP}
ANP-2863(NP)
Revision
. Revision 0 Browns Ferry Unit 1 Cycle 9 Browns Reload Safety Analysis Reload Analysis for 105% OL TP OLTP Page A-100 3.S 3.5 o0 FWCF FWCF o LRNB 3.0 AA CRWE CRWE
-+-'
~~EE2.52.S~~
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0 10 20 30 40 50 SO 60 60 70 80 90 100 110 110 Power (% Rated)
Rated)
Power MCPRpp MCPR
(%
(% of rated) rated) Limit Limit 100 100 1.52 1.52 90 1.58 1.58 50 --
50 1.91 40 1.96 1.96 30 2.19 2.19 30 at >> 50%F 3.01 25 at >> 50%F 3.35 30 at <s 50%F 2.71 25 at SO%F 50%F 3.03 3.03 25 2S at > SO%F 50%F 3.35 3.3S 30 at < SO%F 30ats 50%F 2.83 25at5 2Sats <50%F SO%F 3.17 3.17 Figure A.9.1 A.9.10000 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for .
~~GE14 Fuel GE14 Fuel NSS Insertion NSS Insertion TimesTimes TBVOOS and PLUOOS Combined TBVOOS Combined~~
~~. AREVA NP Inc Inc...~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Browns Ferry Unit 1 Cycle Cycle 9 , Revision 0 Reload 105% OL Reload Safety Analysis for 105% OLTP TP Page A-102 Page A-1 02 4.0 IIIIIII - I -
~~o FWCF FWCF 0o ' LRNB LRNB.~~
~~3.5 3.5 A~~
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ry 0:::
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Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 100 1.55 1.55 90 1.61 50 ---
50 1.92 1.92 40 2.03 30 2.27 30 at > 50%F 3.13 3.13 25 at > 50%F
~~25 3.47 3.47 30 at:~~
~~at <50%F~~
~~S 50%F . 2.82 25 at < 50%F at:S 3.20 Figure A.9.101 A.9.101 BOC to FFTRICoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for MCPR for~~
. ATRIUM-10 ATRIUM-10 Fuel NSS Insertion NSS Insertion Times Times
. TBVOOS and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1. 1 Cycle 9 Revision 0 Reload Safety Analysis for 105%105% OL TP OLTP Page A-103 A-103 4.0 IIIIIII . , I.
o FWCF FWCF o LRNB LRNB 3.5 3.5 at:. CRWE CRWE 3.0 3.0
+J
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0o 10 . 20 30 40 50 50 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% Limit Limit 100 1.54 1.54 90 1.61 50 ---
50 1.91 40 2.04 30 2.27 30 at >> 50%F 3.17 3.17 25 at > 50%F 3.47 30 at <s 50%F 2.95 25 ats at < 50%F 3.35 Figure* A.9.1 Figure 02 BOC to FFlRlCoastdown A.9.102 FFTR/Coastdown Power-Dependent MCPR limits Power-Dependent MCPR for Limits for GE14 Fuel NSS Insertion NSS Insertion TimesTimes TBVOOS and PLUOOS lBVOOS PLUOOS Combined Combined AREVA NP Inc Inc...
ANp-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0
.** Revision 105% OL Reload Safety Analysis for 105% OLTPTP Page A-104 3.5 3.5 r-----,---__r_--.__-___r-~__r_-'--.__-___r--_,_-~..___-___,.--....,
IIIIIIII o[
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CRWE
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A 1.5 t.A Q III I I I - I I " II 1.0 o0 10 20 20 . 30 30 40 50 6.0' 60 70 70 80 90 100 100 110 110
. Power (% Rated) Rated)
Power .. MCPR MCPRpp
(%of
(% of rated) rated) Limit Limit 100 100 1.56 1.56 90 1.62 1.62 50 50 ---
50 1.89 1.89 40 1.98 1.98 30
'30 2.21 30 at>
at > 50%F 3.01 3.01 25 at > 50%F 3.35 30 at*
ats 50%F 2.71 25 ats at < 50%F 3.04 Figure A.9.103 A.9.1 03 BOC to NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel Insertion Times TSSS Insertion Times TBVOOS and PLUOOS
.. TBVOOSand PLUOOS Combined Combined NP'lnc.
~~AREVA Np'lnc:~~
,ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 I Cycle 9 Revision 0 Reload Safety Analysis for 105% 10S% OLTP OLTP Page A-105 A-10S 3.5 , - - - - - r - - - . - - - y - - - - - , - - - - , - - - . , - - - - - , - - - - , - - - . , - - - - - - , - - - - - ,
o3 o FWCF FWCF o LRNB LRNB
, 3.0 A
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1.0 o0 10 20 30 40 50 60 70 80 90 100 1,110 110 Power (% Rated)
Power MCPRpp MCPR
(%
(% of rated) Limit Limit 100 1.55 1.SS 90 1.61 50 SO ---
50 SO .1.87 1.87 .
40 1.97 1.97 30 2.20 30 at > SO%F 50%F 3.03 3.03 25 2S at> SO%F 50%F ' 3.35 3.3S' 30 at < 50%F ats SO%F 2.83 2.83 25 at 2S ats< SO%F 50%F 3.17 3.17 Figure A.9.104 A.9.1 04 BOC to NEOC Power-Dependent MCPR Limits Power-Dependent Limits for GE14 Fuel TSSS TSSS Insertion Insertion TimesTimes TBVOOS and PLUOOS PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 . Revision Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP Page A-106 3.S 3.5
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~ 2.0 0 A.0 1.5 l.S IIIII I I I I I 1.0 o0 10 20 30 40 . SO 50 60 70 80 90 100 110 110 Power (%(% Rated)
Rated)
Power MCPRpp MCPR
(% of rated) Limit 100 1.56 1.56 90 1.62 1.62 50 ---
50 1.91 40 1.98 1.98 30 2.21 30 at > 50%F 50%F 3.01 25 at > 50%F 50%F 3.35 at:<50%F 30 ats 50%F 2.71 25 at s< 50%F 50%F 3.04 Figure A.9.105 Figure A.9.105 BOC to EOCLB EOCLB Power-Dependent MCPR Limits for Power-Dependent ATRIUM*10 ATRIUM-10 Fuel
. TSSS Insertion Times TSSS Times TBVOOS TBVOOS and and PLUOOS ,Combined Combined AREVA NP NP Inc:
ANP-2863(NP)
ANP-2863(NP)
Revision Browns Ferry Unit 1I Cycle 9. 9 . Revision 0 Reload Reload Safety Analysis Analysis for 105%
105% OL OLTP TP Page A-107 3S 3.5' .--------r----,---,---__r---,----~-__r--_,__--~-___,_--__,
o FWCF FWCF o LRNB LRNB 3.0 3.0 A CRWE CRWE
..... 2.5 2.5
'E
~
n Q.
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CL 00 002 0
~ M2.02.0 00 0 OA Aa 1.5 F- 6 A 6 I I I I I I I 1.0 L...-_----'-_ _
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....l..----'-_.L..-_----L_--'-....L.-_ _.L..-_----L_ _....L.-_ _.L..-_---1_ _--l 0o 10 20 30 40 50 60 60 70 80 90 100 110 110
. Power (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 100 1.55 1.55 90 1.61 50 ---
50 1.91 40 1.97 1.97 30 2.20 30 at > 50%F 3.03 3.03 25 at > 50%F 3.35 3.35 30 at ats< 50%F 2.83 25 ats at 5 50%F 3.17 3.17 Figure A.9.106 A.9.106 .BOC BOC to EOCLB Power-Dependent
. Power-Dependent MCPR MCPR Limits for for GE14 Fuel TSSS Insertion TSSS Insertion Times Times TBVOOS TBVOOS and PLUOOS PLUOOS Combined.
AREVA AREVA NP NP Inc.
, ANP-2863(NP)
ANP-2863(NP)
Unit 1 Cycle 9 Browns Ferry Unit Revision 0 Revision Reload Reload Safety Analysis for 105% OL OLTP TP Page A-108 4.0 oo3 FWCF FWCF 3~5 ' .
0O LRNB 3.5 A* CRWE 3.0
+J o-E E
_j
--l 0_ 2.5
~~a. 2.5 Of 0::~~
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tJ. g 1.5 tJ. C 9 II , I I I . I I I I" I 1.0 '--_---L.--'-_....L--'--_.L...-_--'-_ _....L---'-_.L...-_--'-_ _--'-_~.L..----'-1-__,.--'
0o 10 20 ,30 30 40 50 60 70 80 90 100 110 110 Power (%
'Power (%, Rated)
Rated)
Power MCPRpp MCPR
(% of rated) Limit 100 1.59 1.59 90 1.64 1.64 50 50 ---
50 1.92 1.92 40 2.05, 2.05 30 2.29 30 at > 50%F 50%F 3.13 3.13 25 at > 50%F 50%F 3.47 3.47 30 at:S at < 50%F 50%F 2.82 25 at:S at < 50%F 50%F 3.20 Figure Figure A.9.107 A.9;107, BOC to FFTR/Coastdown FFTRICoastdown Power-Dependent MCPR, Limits for Power-Dependent MCPR for ATRIUM-100. Fuel '
, 'ATRIUM-1 Insertion Times TSSS Insertion Times . .
" TBVOOS PLUOOS Combined TBVOOS and PLUOOSCombined
" AREVA NPNP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1. 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% OL OLTP TP Page A-109 A-'109 4.0 , - - - - - , - - - - , - - - . - - - - - , - - - ' - - - - . - - - , - - - , - - - , - - - , - - - , - - - ,
oO FWCF FWCF 3.5 o LRNB LRNB A
~~b. CRWE CRWE 3.0~~
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1.0 0o 10 10 20 30 . 40 50 50 60 70 80 . 90 100 110 110 Power Power (% (% Rated)
Rated)
Power MCPRP MCPR p
(% of rated)
(% rated) Limit 100 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 3.17 at'> 50%F 25 at> 3.47 30 ats at < 50%F 50%F 2.95 25 at ~~. 0 I0 I 0o 1.0 o0 10 20 30 40 50 ,60 60 ,70 70 80 90, 90, 100 100 110 110 Power (% Rated)~~
~~Rated)~~
~~Power Power MCPR~~~
~~MCPRp "~~
~~(% of rated) Limit Limit 100 100 1.52 1.52 90 1.59 1.59 50 --- "~~
50 1.89 1.89 40 2.00 30 2.24 30 at >> 50%F 30at 2.67 at > 50%F 25 at::> 2.90 30 at <s 50%F 50%F 2.62 25 at
~~'25 S 50%F< 50%F 2.84 Figure A.9.109 BOC to NEOC, FigureA.9.109BOC NEOC Power-Dependent Power-Oependent,MCPR MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel~~
~~NSS Insertion Times, NSS Times FHOOS and PLUOOS PLUOOS Combined "~~
AREVA NP
, 'AREVA NP Inc:
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 . Revision Revision 0 105% OLTP Reload Safety Analysis for 105% OLTP Page A-111 A-111 3.S 3.5 IIII
~~III oo FWCF FWCF o LRNB LRNB~~
~~3.0 3.0 A CRWE CRWE~~
~~+J 2.5 2.S~~
~
41
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1.S 1.0 o0 10 .20 20 30 40 40 50 SO 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPRpp MCPR
(%
(% of rated) Limit Limit 100 100 1.51 90 1.58 1.58 .
50 50 ---
50 1.87 1.87 40 2.01 30 2.24 2.24 30 at > 50%F 2.76 2.76 25 at,>
at'> 50%F 3.00 3.00 30 at s< 50%F 2.75 2.75 25 at s< 50%F 2.96 Figure A.9.1 10 BOC to NEOC A.9.110 Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel .
NSS Insertion NSS Insertion Times Times
.. , FHOOS and PLUOOS Combined Combined Inc.
AREVA NP Inc.*
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% TP.
OLTP. Page A-1 Page A-112 12 3.5 o3 o FWCF FWCF o . LRNB LRNB 3.0 A CRWE CRWE
'E 2.5 2.5
...J c..
a::::
01 0... 0 0
~ S2.02.0 0 0
1.5 I- 0 I I I II I I 1.0 '--_---'-_ _---1-_ _.l....-_----'-_ _--'--_ _-'--_----'-_ _--'--_ _-'--_----'._ _.....J 0o 10 20 30 . 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRpp MCPR
. (%
(% of rated) Limit Limit 100 1.52 1.52 90 *1.59 1.59 50 --
50 1.91 40 2.00 30 2.24 30 at > 50%F 30at 50%F 2.67 25 at > 50%F 50%F 2.90 30 at s< 50%F 2.62 25 ats
.25 at < 50%F 2.84 Figure A.9.111 A.9.111 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM-10 NSS Insertion NSS Insertion Times Times FHOOS and PLUOOS Combined Combined AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 *; Revision 0 Reload Safety Analysis for 105% OL OLTP TP Page A-1 Page A-113 13 3.5 I III II I o
O FWCF FWCF o LRNB LRNB 3.0 A t:. CRWE _
..... 2.5 2.5 E
~~J a..~~
et:
D-0~ o 0
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00 1.5 F SA 0 I . I . I I I I I . I I I 1.0 o0 . 10 20 . 30 40 50 50 60 60 70 80 90 100 110 110 Power Power (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 100 1.51 90 1.58 1.58 50 ---
50
.50 1.91 1.9.1 40 2.01 30 2.24 30 at > 50%F 2.76 at > 50%F 25 at> 3.00 30 at <s 50%F 50%F 2.75 25 ats .'
at < 50%F 50%F 2.96 Figure Figure A.9.112 A.9.112 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for for
. GE14 Fuel .
NSS Insertion Times
. NSS Times FHOOS and PLUOOS PLUOOS Combined Combined NP Inc.
AREVA NPlnc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 11,Cycle 9 . . Revision 0 Reload Safety Analysis Analysis for 105%
105% OLOLTP TP . Page A-114 A-1 14 3.5 I III o FWCF FWCF o LRNB LRNB 3.0 3.0 A CRWE CRWE
~~E 2.5~~
~~.:J 0..~~
a_
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_-'--_---L I I
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I I_ _--I o
0 10 10 20 30 40
~. 50
~ 60
~ m.oo
~~70. 80 90 100 110 110 Power (%~~
Power (% Rated)
Rated)
Power . MCPRp MCPRp
(% of rated)
(% rated) Limit Limit 100 1.56 1.56 90 1.61 50 ---
50 1.89 1.89 40 2.01 30 2.25 30 at > 50%F 50%F 2.67 25 at > 50%F at>50%F 2.90 at < 50%F 30 ats 2.62
. 25 at s< 50%F 2.84 2.84 Figure A.9.113 A.9.113 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR limits for Limits
. ATRIUM-10 ATRIUM-10 Fuel Fuel. .
TSSS Insertion Times TSSS Times FHOOS and PLUOOS Combined Combined AREVA AREVA NP Inc.
ANP";2863(NP)
ANP-2863(NP)
I *Cycle Browns Ferry Unit 1. Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP Page A-1 15 Page A-115 3.5
.3.S I I I II I Oo FWCF FWCF 0o LRNB LRNB 3.0
.3.0 a6 CRWE CRWE
+J 2.5 2.S
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2 2.0 00 0 00 1.5 1-1.S 8 A III I I I I I I " I" 1.0 o0 10 20 .30 30 40 SO 50 60 60 70 80 90 100 100 110 110 Power (%
Power (% Rated)
Power MCPRpp MCPR
(% of rated) Limit Limit 100 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.89 1.89 40 2.02 2.02 30 2.25 2.25 30 at > 50%F 2.76 2.76 25 at > 50%F 3.00 3.00 30 at<
ats 50%F 2.75 2.75 25 at ats< 50%F 2.96 2.96 A.9.114* BOC to NEOC Figure A.9.114 NEOC Power-Dependent MCPR Limits for Power-Dependent GE14 Fuel TSSS TSSS Insertion Insertion Times Times FHOOS and PlUOOS PLUOOS Combined Combined
~~AREVA NP Inc.~~
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 , Revision 0 Reload Safety Analysis Analysis for 105%
105% OL OLTP TP Page A-.116 Page A-116
, ~
i I 3.5
" o FWCF FWCF oo LRNB LRNB 3.0 1- A
/),. CRWE CRWE 2.5 F nj 0~ 0 0
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m A
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I. _-'--_---'-_-"--'-_
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i I _---'-_
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I I o0 10 10 20 30 40 50 60 60 70 89 80 90
~~90. 100.~~
100 110 110 Power Power (% (% Rated)
Rated)
Power .' MCPRpp MCPR rated)
(% of rated) Limit
. Limit 100 1.56 1.56
,t I 90 1.61 50 ---
50 1.91 1.91 40 2.01 30 2.25 at > 50%F 30 at> 2.67
-25
-25 at > 50%F 2.90 2:90 30 ats50%F at < 50%F 2.62 at5 50%F 25 at'S 50%F 2.84
. Figure Figure A.9.115 A.9.115 BOC to EOCLB EOClB Power-Dependent MCPR Limits for
. Power-Dependent for ATRIUM-10 Fuel ATRIUM-10
'. TSSS Insertion Insertion Times Times '.
'. FHOOS and PlUOOS Combined PLUOOS Combined AREVA NPlInc.
NPlnc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 '\ , Revision Revision 0 Safety Analysis for 105% OLTP Reload Safety OLTP , Page A-117 A-117 3.5 ,----,-----r---,------,----:---:.-..,---,------,---:.---,------,----,
II- I I III o3 o FWCF o LRNB
. 3.0 a I:>. CRWE
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Power Rated)
Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.91 40 2.02 2.02 30 2.25 2.25 30 at > 50%F 2.76 25 at > 50%F 3.00 30 at S< 50%F 2.75 2.75 25 at s< 50%F 2.96
.2.96
, Figure A.9.116 A.9.116 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel
,TSSS InsertionInsertion Times Times FHOOS and PLUOOS Combined Combined AREVA NP Inc., Inc.,
ANP-2863(NP)
ANP-2863(NP) ..
Revision 0
. Revision Browns FerryFerry Unit 1I Cycle 9 Reload Safety Analysis Analysis for 105%
105% OL OLTP TP . Page A-118 A-1 18 4.0 o FWCF FWCF o LRNB LRNB 3.5 A
l>. CRWE CRWE 3.0
E
~~---l~~
~~a. 2.5 0:::~~
0...
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A 1.5 o 6 III I" I I I " I I I , "
LO 1.0 o0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power* (% Rated)
Power Rated)
Power MCPRpp MCPR
(% of rated) Limit 100 100 1.55 1.55 90 1.61 50 50 ---
50 1.87 1.87 40 2.03 30 2.27 30 at >> 50%F 3.13 3.13 25 at >> 50%F 50%F 3.47 30 at s< 50%F *2.82 2.82 25 at s< 50%F 3.20 Figure A.9.117 A.9.117 BOC to NEOC Power-Dependent Power-Dependent MCPR MCPR Limits for ATRIUM-10 ATRIUM-10Fuel Fuel Insertion Times NSS Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and FHOOS Combined Combined AREVA AREVA NP Inc. Inc~
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 OLTP Reload Safety Analysis for 105% OL TP Page A-1 Page A-119 19 4.0 o FWCF FWCF o LRNB LRNB 3.5 A
Il. CRWE CRWE 3.0 3.0
+J
'EE
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1.0 o0 10 20 30 40 50 60 70 80 90 100 110 110 Power (%(% Rated)
Power MCPRpp MCPR
. (%
(% of rated) Limit Limit 100 1.54 1.54 90 1.61 50 ---
50 1.90 1.90 40 2.04 30 2.27 30 at > 50%F 3.17 3.17 25 at > 50%F 3.47 3.47 30 at ats < 50%F 2.95 2.95 25 at s< 50%F 3.35 3.35 Figure A.9.118 Figure A.9.118 BOC toNEOC BOG to NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for GE14 Fuel Fuel* .
NSS Insertion NSS Times Insertion*Times EOC-RPT-OOS, EOC-RPT TBVOOS, an~
-OOS, TBVOOS, FHOOS Combined and FHOOS Combined AREVA NP Inc.
I' ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 . Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP Page A-120 A-120 4.0 J I o]
0 FWCF FWCF o0 LRNB LRNB 3.5 aA CRWE CRWE 3.0
-+-'
'E E
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0-Q..
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1.5 1.5 o A 0 O IIIII I I I I i 1.0 0o 10 20 30 40 50 60 60 70 80 90 100 110 110 Power (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated) Limit 100 100 1.55 1.55 90 1.61 50 --
50 1.87 1.87 40 2.03 30 2.27 30 at >> 50%F 3.13
.3.13 25 at >> 50%F 3.47 30 at s< 50%F . 2.82 25 at ats< 50%F 3.20 Figure A.9.119 BOC to EOCLB* EOCLB.
Power-Dependent Power-Dependent MCPR MCPR Limits for ATRIUM-10 ATRIUM-10 Fuel Insertion Times NSS Ir:-sertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and FHOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit Unit 1
1. Cycle 9 Revision 00 Revision Reload Safety Safety Analysis for 105% 105% OL OLTP TP Page A-121 4.0 , . - - - - , - - - , - - - , - - - - - , - - - . - -IIIIII- , - - - - - - r - - - . - - - , - -, - - - -I r - - - ,
oo] FWCF FWCF ao LRNB 3.5 A
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~~1.0 1.0 '--_----L_ _ --1-_ _.1....-_----'-_ _--1-_ _.1....-_----'-_ _--1-_ _-'---_----L_"""-----'~~
o0 10 20 20 30 . 40 50 60 70 80 90 100 100 110 110 Power (% Rated) Rated)
Power MCPR MCPRpp
(% of rated)
(% rated) Limit Limit 100 100 1.54 1.54 90 1.61 50 ---
50 1.90 1.90 40 2.04
- 30 2.27 30 at >> 50%F 3.17 3.17 25 at >> 50%F 3.47 30 at <s 50%F 2.95 2.95 25 at 50%F 50%F 3.13 3.13 25 at > 50%F 3.47 30 at at s< 50%F 2.82 25 25 at5 at s<50%F 50%F .~ 3.20 Figure A.9.121 A.9.12.1 BO Cto NEOC BOC.to NEOC Power-Dependent MCPR Power-Dependent MCPR limits for Limits for ATRIUM-10 ATRIUM*10 Fuel Fuel'
~~. TSSS TSSS Insertion Insertion Times Times .~~
~~EOC-RPT-OOS, EOC*RPT*OOS, TBVOOS,TBV.OOS, and FHOOS FHOOS Combined Combined AREVA AREVA NP Inmc NPlnc:~~
~~ANP-2863(NP)~~
~~ANP-2863(NP) .~~
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP PageA-123 Page A-123 4.0 II *l I o3 o FWCF FWCF o LRNB LRNB 3.5 A
~~I> CRWE CRWE 3.0~~
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~~-l 2.5~~
~~a. 2.5 0:::~~
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o 1.5 I>
0 8 0
, I~~~ 0 1.0 0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 30 2.29 30 at > 50%F 50%F 3.17 3.17 25 at > 50%F 50%F 3.47 30 at s< 50%F 2.95 .
2.95 at* 50%F 25 ats 3.35 Figure A.9.122 A.9.122 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for
.GE14 GE14 Fuel TSSS TSSS Insertion Times Times EOC-RPT-OOS, EOC*RPT -OOS, TBVOOS, TBVOOS, and FHOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 , Revision 0 Reload Safety Analysis Analysis for 105%
105% OL OLTPTP . Page A-124 Page 4.0 III I I I I i
'j)
O0 FWCF F'v'{CF o0 LRNB 3.5
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A* CRWE CRWE 3.0
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III I I I IIII 1.0 o0 10 20 20 30 40 50 60 60 70 80 90 100 100 110 110 Rated)
Power (% Rated)
Power MCPRp MCPRp
(% of rated)
(% . Limit Limit 100 1.59 1.59 90 1.64 1.64 50 ---
50 1.89 1.89 40 2.05 2.05 30 2.29 2.29 30 at > 50%F 3.13 3.13 at > 50%F 25 at> 3.47 30 at <s 50%F 50%F 2.82 2.82 25 at 50%F 3.17 3.17 at>> 50%F 25 at 3.47 3.47' ats 30 at < 50%F 2.95 25 at ats< 50%F 3.35 Figure A.9.124 A.9.124 BOC to EOCLBEOCLB Power-Dependent MCPR Lirriitsfor Power-Dependent Limits for ,
~~GE14 Fuel~~
~~" ., TSSS' TSSS Insertion Insertion Times Times EOC-RPT-OOS,~~
~~EQC-RPT -OOS, TBVOOS, and FHOOS Combined* Combined~~
. AREVA NP Inc...
NPlnc
ANP-2863(NP)
ANP-2863(NP)
I Cycle 9 Browns Ferry Unit 1 Revision Revision 0 105% OL Reload Safety Analysis for 105% TP .
OLTP Page A-126 A-126 3.5 3.5 ~---'----'---'-----'----'---'-----'-----'---T---'---'
I IIII -
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Power Power MCPRpp MCPR
(% of rated) Limit Limit 100 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.89 1.89 40 1.96 1.96 30 2.19 2.19 30 at at>> 50%F 3.01 25 at> 50%F
.25at>50%F 3.35 3.35 30 at5 ats<50%F 50%F . 2.71 25 at5<50%F
.25 ats 50%F 3.04 3.04 A.9.125 BOC to NEOC Figure A.9.12S Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 ATRIUM*10 Fuel NSS Insertion Times NSS Insertion Times EOC-RPT-OOS, EOC*RPT TBVOOS, and
~~OOS, TBVOOS, andPLUOOS~~
.PLUOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Unit I1Cycle 9 Browns Ferry Unit1Cycie Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP Page A-127 A-127 3.5 3.5 o FWCF FWCF oo LRNB LRNB 3.0 3.0 A6 CRWE CRWE
+J 2.5
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0o 10 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Power MCPRP MCPRp
(% of rated) Limit Limit 100 1.52 1.52 90 1.58 1.58 50 ---
50 1.87 1.87 40 1.96 1.96 30 2.19 2.19
> 50%F 30 at > 3.03 25 at >
> 50%F 3.35 3.35 30 at s< 50%F 50%F 2.83 25 at at:s<50%F 50%F 3.17 3.17
. Figure A.9.126 A.9.126 BOC to NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for for GE14 GEl4 Fuel NSS Insertion Times NSS Insertion Times EOC-RPT;.OOS, EOC-RPT-OOS, TBVOOS,and TBVOOS, and PLUOOSPLUOOS Combined AREVA NP Inc.
ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Unit I1 Cycle Browns Cycle 9 .. Revision Revision 0 Reload Reload Safety Safety Analysis for 105% OLTP OLTP Page A-128 3.5 .--------r----,----..---,,------r----r---,------r--"-r---,------.----,
I II II I o
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0.. 00 U 2.0
~ 2.0 0 A 8 1.5 F-III I I I I I " " I I I 1.0 '--_--'-_ _--1....._--,--.1.-_----'-_ _--1....._ _- ' - - - _ - - - - ' -_ _-'--,---.,--'---_-1'--_---'I' o0 10 20 30 40 50 50 . 60 60 70 80 90.
~~90. 100 . 110 110~~
. Power (% Rated)
Power (% Rated)
Power . MCPR MCPRpp
(% of rated)
. (% ~imit Limit 100 1.52 1.52 90 1.58 1.58 50 50 ---
50 1.91 40 1.96 1.96 30 2.19 2.19 30 at > 50%F 3.01*
3.01 25 at > 50%F 3.35*
3.35 30 at s< 50%F 50%F 2.71 25 ats at5<50%F50%F 3.04 Figure Figure A.9.127 A.9.127 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 Fuel ATRIUM-10 .
NSS Times NSS Insertion Times EOC-RPT-OOS, EOC-RPT TBVOOS, and PLUOOS
-OOS, TBVQOS,.and PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision Revision 0 Reload Safety Analysis for for*1105%
05% OLTP OLTP Page A-129 A-129 3.5 , - - - - r - - - - r - - - r -I ' - - - -I r - - - ,I - - - - ,I- - - - -I, - - - - I, - - - , -
I o FWCF o LRNB
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1.5 1.0 '--_--'-_ III 1.0 _....L-_ _.L..-_---'-_ I I
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o 0 10 10* 20 30 40 50 60 70 . 80 90 100 100 110 110 Power (%
Power (% Rated)
Power MCPRp MCPRp
(% of rated)
(% Limit*
Limit 100 .1.52 1.52 90 1.58 1.58 50 ---
50 1.91 40 1.96 1.96 30 2.19 2.19 30 at > 50%F 50%F 3.03 3.03 25 at > 50%F 50%F 3.35 3.35 at < 50%F 30 ats 2.83 25 ats at:<.50%F 50%F 3.17 3.17 Figure A.9.128 A.9.128 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion Times NSS Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, and PLUOOS Combined Combined AREVA NP.lnc.
AREVA NP Inc.,
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP Page A-1 30 A-130 4.0 , - - - - - r - - - y - - - , - - - - , - - - , - - - - . - - - - , - - - - , - - - . - - - - - - , - - - - - ,
o O FWCF FWCF o LRNB LRNB 3.5 A CRWE 3.0
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1.0 II I
_--'-_ I
_'---_--'-_ I I
_--'-_ I .I 0o 10 20 _ 30 40 50 60 70.
70 80 90 100 110 110 Power (% (% Rated)
_Power MCPRp MCPRp
(% of rated) Limit Limit 100 1.55 -
1.55 90 1.61 50 ---
50 1.92 1.92 40 2.03 2.03 30 2.27 2.27 30 at;:' 50%F at > 50%F 3.13 3.13 25 at > 50%F 50%F 3.47 3.47 30 at s< 50%F 50%F 2.82 25 at s: 50%F 3.20 Figure A.9.129 A.9.129 BOC to FFTR/Coastdown FFTRlCoastdown Power-Dependent Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and PLUOOS PLUOOS CombinedCombined AREVA NP Inc.
- - -AREVA
ANP-2863{NP}
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP Page A-131 4.0 , . . . . . - - - - - - r - - . . , - - : - - , - - - - - - - r - - . . , - - - , - - - , - - . . , - - - , . - - - , - - - - ,
4.0 oo FWCF FWCF o LRNB LRNB 3.5 AIl. CRWE
'CRWE 3.0
+'
E
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U
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0 0
2.0 0 0 0 00 A0 A 6 A 6 1.5 III I I I I I I I 1.0 o
0 10 20 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Power MCPRpp MCPR
(% of rated}
{% rated) Limit Limit 100 1.54 1.54 90 1.61 50 ---
50 1.91 40 2.04 2.04*
30 2.27 2.27 30 at > 50%F50%F 3.17 3.17 25 at > 50%F 3.47
3.47 at < 50%F 30 ats 2.95 2.95 25 ats at < 50%F 3.35 3.35 Figure A.9.130 A.9.130 BOC to FFTRICoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel .
. NSS Insertion NSS Insertion Times Tim.es EOC-RPT-OOS, EOC*RPT *OOS, TBVOOS, and PLUOOS Combined Combined AREVA AREVA NP Inc.
I ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry Unit Unit 1 Cycle 9 Revision 0 Reload Reload Safety Safety Analysis Analysis for 105%
105% OL OLTP TP Page Page A-132.
3.5 3.5 I II II II oo FWCF FWCF o LRNB LRNB 3.0 A CRWE CRWE
+-'
2.5 2.5
'E
°--
~~=i r__~~
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0:::
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() 00
~ 2.0 2.0 0 00 00 1.5 I I I I I I I 1.0 o0 10 20 30 30 40 50 60 70 80 90 100 110 110 Power (% (% Rated)
Power MCPRpp MCPR
(%
(% of rated) Limit Limit 100 1.56 1.56 90 1.62 1.62 50 ---
50 1.89 1.89 40 1.98 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 25 3.35 30 at s< 50%F 2.71 25 at s< 50%F 3.04 3.04 Figure A.9.131 Figure A.9.131 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS TSSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, and PLUOOS Combined Combined AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP Page A-133 A-133 3.5 I I I I I I. I.
o FWCF FWCF o LRNB LRNB 3.0 3.0 A CRWE CRWE
...., 2.5
'E41
~~.=i 0 E Q..~~
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00 i
1.5 1.5 1.0 o0 10 20 30 40 50 60 70 80.
80 90 100 110 110 Power (% (% Rated)
Power MCPRP MCPRp
(% of rated)
(% Limit Limit 100 1.55 1.55 90 1.61 50 50 1.87 50 1.87 40 40 19
.1.97 30 2.20 30 2.20 30 at>
at > 50%F .3.03 3.03 25 at > 50%F 3.35 3.35 25 at > 50%F 30 at < 50%F 2.83 30 at s 50%F 2.83 25 at S< 50%F 50%F 3.17 3.17
.Figure A.9.132*
A.9.132 BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent for GE14 Fuel GE14 .
TSSS Insertion Times Insertion Times EOC-RPT ~OOS, TBVOOS, EOC-RPT-OOS, TBVOOS, and PLUOOS Combined PLUOOS Combined
. AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry Unit Unit 1 Cycle 9 . Revision Revision 0 Reload Reload Safety Safety Analysis for 105% OL OLTP TP Page A-134 A-134 .
3.5 , - - - - - - , - - - - , - - - , - - - - - , - - - -
I
- . - - - . -IIII*I

~~,-----,---.------y---,~~

o O FWCF FWCF o LRNB LR*NB 3.0 k ORWE-CRWE
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~ 2.0 1 0 00 00 00 Ao0 1.5 F I " I I II 1.0 '--_---'-_ _-'--_ _.L...-_--'-_ _-'----_ _.L...-_--'-_ _-'----_ _.L...-_---1._ _-.J 0o 10 10 20 *30 30 40 50 60 70 80 *90 90 100 110 110
. Power (% (% Rated)
Rated)
Power MCPRpp
. MCPR
(%of rated)
(% Limit 100 1.56 1.56 90 1.62 1.62 50 ---
50 1.91 .
40:
40. 1.98 1.98 30 2.21 30 at > 50%F 3.01 25 at > 50%F 3.35 at5<50%F 30 ats 50%F 2.71 at < 50%F 25 ats 3.04 Figure A.9.133 A.9.133 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel TSSS TSSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, and PLUOOS Combined Combined AREVA NPlnc.
AREVA NPlInc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 '. Revision 0 Reload Safety Analysis for 105% OL OLTP TP Page A-135 A-135 3,5 , - - - - - - . - - - - , - - -I , . - - - - - .I- - -I - , I-- - - , . - - - - , - - - , - - - , -
3.5 I

~~I oo1 FWCF FWCF o LRNB LRNB 3.0~~

~~3.0 SA CRWE CRWE~~
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~~) 0~~
~ 2.0 00 0 0I 1.5 1.5 1- 6 A6 I I I II I6 1.0 0o 10 20 30 40 50 60 70 80 90 100 110 110 Power (% Rated) Rated).
Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 1.55 1.55 90 1.61 50 50 ---
50 1.91 40 1.97 1.97 30 2.20 2.20 30 at > 50%F 3.03
,I -'
25 at> 50%F 3.35 30 at s<50%F 2.83 2.83 25 at5 ats<50%F 50%F .3.17 3.17 Figure A;9.134 A.9.134 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel TSSS TSSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT -ods, TBVOOS, TBVOOS, and PLUOOS Combined Combined AREVA NP Inc.
ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Unit 1 I Cycle 9 Revision Revision 0 Reload Safety Analysis for 105% 105% OLTP OLTP . Page A-136 A-136
. 4.0 .---------r-----r---.-------.,.----r---r----.,.----r---r--~--___,
oO3 FWCF FWCF 3.5 o LRNB LRNB A CRWE CRWE 3.0 1'-'
'E,_E
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1.5 III 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)
Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.59 1.59 90 1.64 1.64 50 ---
50 1.92 1.92 40 2.05 2.05 30 2.29 2.29 30 at > 50%F 3.13 3.13 25 at > 50%F 3.47 3.47 30 at s< 50%F 2.82 25 at s* 50%F 3.20 3.20 A.9.135 BOC to FFTRICoastdown Figure A.9.135 FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10Fuel ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOeS, and PLUeOSPLUOOS Combined Combined AREVA NP Inc: Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 Reload Reload Safety Analysis Analysis for 105%
105% OL OLTP TP Page A-137 A-1 37 4.0 oO FWCF FWCF ao LRNB 3.5 A
I:>. CRWE CRWE 3.0 3.0
+J
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~
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a0 2.0 2.0 a0 . 0 1.5 6 I:>. 06 9 III 1.0 '--_-:--'-_ _ --'---'-_-'--_----LI _ _---'--_
I I
_-'--_----L I I
_ _---'--_ I
_-'--_----1I o0 10 20 30 40 50 60 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power MCPRP MCPR p rated)
(% of rated) Limit 100 100 . 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 30 2.29 30 at >> 50%F 3.17 3.17 25 at > 50%F 3.47 30 at <s 50%F 50%F 2.95 25 at <s 50%F 50%F 3.35 Figure Figure A.9.136 A.9.136 BOC to FFTRlCoastdown FFTR/Coastdown Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel
. Insertion Times TSSS Insertion Times EOC-RPT-OOS,
. EOC*RPT TBVOOS, and PLUOOS
~~OOS, TBVOOS, Combined PLUOOS Combined AREVA NP NP Inc.~~
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 I Cycle 9 Revision Revision 0 Reload Safety Safety Analysis for 10S% 105% OLTP OLTP Page A-138 3.5 3.5 ,------r----r----,.-----,----,---.,-----,-----r---.,------.----,
o FWCF FWCF o LRNB 3.0 3.0 A
/j. CRWE
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Power MCPRp MCPRp
(% of rated)
(% Limit Limit 100 1.52 1.S2 90 1;S9 1.59 50 SO ---
50 SO 1.89 1.89 40 2.00 2.00 30 2.24 2.24 30 at > 50%F SO%F 2.67 2.67 25at > 50%F 2Sat> SO%F 2.90 2.90 at<50%F 30 ats SO%F 2.62 2.62 25 ats 2S at < SO%F 50%F 2.84 2.84 Figure Figure A.9.137 A.9.137 . B()C toNEOC BOC to NEOC Power-Dependent Power*Dependent MCPR Limits for for.
A TRIUM*1 0 Fuel .
ATRIUM-10 NSS Insertion NSS Insertion Times Times EOC-RPT-OOS, EOC*RPT *OOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit I1 Cycle 9 Revision Revision 0 Safety Analysis for 105% OLTP Reload Safety OLTP Page A-139 "
3.5 .-------,-----r---..------,-----r---..-------r----,---...--------r---,
IIIIIII . I o FWCF FWCF o LRNB LRNB 3.0 1- A CRWE CRWE
..... 2.5 F
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~~.::::i 0..~~
0:::
0.. 00 0
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~~I I I L - _ - - - - L_ _.:...1-_ _.l...--_---L_ _....l.-_ _.l...--_---L_-'--....l.-_ _..L.-_---l._ _--J o0 10 20 30 30 40 50.~~
50" 60 60 70 80 90 100 100 110 110 Power (% (% Rated)
Rated)
Power MCPR MCPRpp
(% of rated)
(% rated) Limit Limit 100 100 1.51 90 1.58 1.58 50 ---
50 1.87 1.87 40 2.01 30 2.24 30 at > 50%F 2.76 25 at >> 50%F 3.00 3.00 30 at < 50%F ats 2.75 25 at5<50%F ats 50%F 2.96 "Figure A.9.138 BOC to NEOC Figure A.9.138 Power-Dependent Power-Dependent MCPR MCPR"Lirriits for Limits for
" GE14 Fuel NSS Insertion Times NSS Insertion Times EOC-RPT-OOS, "EOC-RPT-OOS, FHOOS, and PLUOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 I Cycle 9 : Revision 0 105% OL Reload Safety Analysis for 10S% OLTP TP Page Page A-140A-140 3.5 3.5 o FWCF.
FWCF o LRNB LRNB 3.0 3.0 A CRWE CRWE
+J
'EE 2.5 2.5
~
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0:::
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~~1.5 1-1.0 '--_----'-_ _..:.J...;..._ _'--_----L_ _- ' -_ _'--_----L_ _- ' - _ - . , . . . - ' - - _ - - " ' - _ - - '~~
o 0 10 20 30 40 50 60 70 80 90 100 100 110 110 Power (%
Power (% Rated)
Rated)
Power MCPRP MCPRp
(%of rated)
(% Limit Limit 100 1.52 1.S2 90 1.59 1.S9 50 SO ---
50.
SO 1.91 40 2.00 2.00 30 2.24 2.24 30 at > SO%F 50%F **2.67 2.67 25 at > SO%F 2S 50%F 2.90 2.90 at5<50%F 30 ats SO%F 2.62 2.62 25 ats 2S at5<50%F SO%F 2.84 2.84 Figure A.9.139 A.9.139 BOC to EOCLB Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, FHOOS, and PLUOOSPLUOOS CombinedCombined
. , AREVA AREVA NPlnc:
NP lnc.
ANP-2863(NP)
ANP-2863(NP}
Browns Ferry Unit 1 I Cycle 9 Revision 0 Reload Safety Analysis for 105% 105% OL OLTP TP Page A-141 3.S 3.5 . - - - - - , - - - . . , - - - . . - - - - , - - - . . , - - - . . - - - - - - , - - - - . - - - , - - - - - - . - - . . . . . ,
o FWCF o LRNB 3.0
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~~I I 1.0 L - _ - - - L ._ _....L..-_ _.L....._---L_ _....l..-_ _. L . . . . . _ - - - L _ - ' - - L_ _..l-.-_--1._ _-J I~~
0o 10 20 30 40 SO 50 60 70 80 90 100 110 110 Power (% (% Rated)
Rated)
Power . MCPRp MCPRp
(% of rated) Limit Limit 100 1.51 90 1.58 1.58 50 ---
50 1.91 40 2.01 30 2.24 30 at > 50%F 2.76 at> 50%F 25 at'> 3.00 3.00 30 at s< 50%F 50%F 2.75 25 ats at5<50%F 50%F 2.96
.2.96 Figure A.9.146 A.9.140 BOC to EOCLB EOCLB Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel Fuel NSS Insertion Times NSS Insertion Times EOC-RPT-OOS, EOC-RPT -OOS, FHOOS, and PLUOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
.Browns Browns Ferry Ferry Unit Unit 11 Cycle Cycle 9 Revision 00 Revision Reload Safety Reload Safety Analysis Analysis for for 105% OLTP.
105% OLTP Page Page A-142 A-142 3.5 o FWCF FWCF oo LRNB LRNB 3.0 A CRWE CRWE
+-'
'EE2.5 2.5
~
a.
0:::
0_
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. A . z* .
1.5 l 1.0 '--_----'-_ _-'-_ _-'--_---'-_ _- - L - _ _- ' - - _ - - - ' - _ _----'- _ _- ' - - _ - - L _ _---'
o0 10 20 30 40 50 60 60 70 80 90 100 100 110 110 Power (%(% Rated)
Power MCPRPp MCPR
(% of rated)
(% Limit Limit 100 1.56 1.56 90 1.61 50 ---
50 1.89 1.89 40 2.01 30 2.25 2.25 30 at > 50%F 2.67 25 at > 50%F 2.90 at < 50%F 30 ats 2.62 25 ats at < 50%F 2.84, 2.84 Figure A.9.141 BOC to NEOC Power.Dependent MCPR Limits for Power-Dependent ATRIUM-10 Fuel ATRIUM*10
. TSSS TSSS Insertion Times Times .
EOC*RPT *005, FHOOS, and PLUOOS EOC-RPT-OOS, PLUOOS CombinedCombined AREVA NP Inc:
AREVA. Inc:
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit Unit 1 Cycle 9 Revision 0 Revision Reload Safety Safety Analysis for 105%
105% OLTP OLTP Page A-143 A-143 3.5 ,....------r----.---..-------r----.---..----,.----r----r-----r----,
o FWCF FWCF ao LRNB 3.0 A t;. CRWE CRWE 2.5 2.5
EE
~~.:::::i~~
__1 0.
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2
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~~06 1.5 F-Q 1.0 '---_--L._I_-'---'--_L..-_---'-_~~
~~I I _- 'I -_ _..l...-_---'-_~~
I I I
_--L-_ I
_..L...-_---LI_ _ ' --l 0o 10 10 20 30 40 50 60 60 70 80 90 100 110 .
110 Power (% (% Rated)
Rated)
Power MCPRpp MCPR
(% of rated) Limit 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.89 1.89 40 2.02 30 2.25 30 at > 50%F 2.76 2.76.
25 at > 50%F 50%F 3.00 3.00 30 ats at:<50%F 50%F 2.75 25 at s< 50%F 50%F 2.96 Figure A.9.142 BOC toNEOC to NEOC Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel GE14 Insertion Times TSSS Insertion Times EOC-RPT-OOS, FHOOS, and PLUOOS Combined EOC-RPT-QOS, Combined AREVA NP NP Inc.
ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Unit Browns Unit 1 Cycle 9 Revision Revision 0 Reload Safety Reload Safety Analysis Analysis for 105%
105% OL OLTP TP . Page A-144 3.5 I II II II
o FWCF FWCF oo LRNB LRNB 3.0*
3.0, aI:J. CRWE CRWE
...... 2.5 2.5
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~~.::J ryQ..~~
0:::
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~ 0
~~Q 1.5 IIII I" I I I I I 1.0 o0 10 20 30~~
.30 40 50 60 70 80 90 100 100 110 110 Power (%
Power (% Rated)
~~Power MCPRp Power MCPRp~~
(% of rated)
(% Limit Limit 100 1.56 1.56 90 1.61 1.61 50 ---
50 1.91 40 2.01 30 2.25 2.25 at > 50%F 30 at> 50%F 2.67 2.67 25 at > 50%F 50%F 2.90 30 at S< 50%F 2.62 2.62 25 at S5 50%F 50%F. 2.84
2.84 FigureA.9.143 Figure A.9.143 BOC BOC to EOClB EOCLB Power.Dependent Power-Dependent MCPR Limits for for ATRIUM*10 ATRIUM-10 Fuel TSSS Insertion Times TSSS Insertion Times EOC-RPT-OOS, EOC*RPT *OOS, FHOOS, and PlVOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2863{NP)
ANP-2863(NP)
Browns Ferry Unit Unit 1.1 Cycle 9 Revision 0 Revision Reload Reload Safety Safety Analysis Analysis for 105% OL OLTP TP Page A-145 3.5 3.5 I I I.I II .
o 0 FWCF FWCF 0
o LRNB LRNB 3.0 A t:. CRWE CRWE
+-'
'41E 2.5
~~.J 0..~~
ct:
0... 0 0 0
~ 2.0 0
1.5 6 A 6 IIII I I I I I I I 1.0 o0 10 20 30 40 50 50 60 70 80 90 100 100 110 110 Power (% Rated)
Power Power MCPRpp MCPR
(%
(% of rated) Limit Limit 100 100 1.54 1.54 90 1.60 1.60 50 ---
50 1.91 40 2.02 30 2.25 30 at at>> 50%F 2.76 25 at > 50%F 3.00 3.00 30 at s< 50%F 2.75 2.75 25 at ats< 50%F 2.96 Figure A.9.144 BOC to EOCLB BOCto Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel TSSS TSSS Insertion Times.
Times EOC-RPT-OOS, EOC-RPT -OOS, FHOOS, and PLUOOSPLUOOS CombinedCombined AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit I1 Cycle 9 R~vision 0
. Revision Reload Safety Analysis for 105% OLTP OLTP Page A-146 4.0 , - - - - , - - - , - - - , . . - - ' - - - , - - - - - - , - - , - - - . - - - - - , - - - - - - , - - - . - - - - - - r - - - ,
oo] FWCF FWCF o LRNB 3.5 3.5 A
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Power MCPRpp MCPR *
(% of rated) Limit 100 1.55 1.55 90 1.61 1.61 50 ---
50 1.89 1.89 40 2.03 30 2.27 30 at >
30 at > 50%F 50%F 3.13*
3.13 25 at > 50%F 50%F 3.47 at < 50%F 30 ats 50%F 2.82 25 at s: 50%F
25 50%F 3.20 Figure A,9.145 A.9.145 BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion Times NSS Times TBVOOS, FHOOS,
. lBVOOS, FHOOS, and PLUO,OSCombined PLUOOS Combined AREVA AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit Browns Unit 1 Cycle 9ycle 9 " Revision ()0 Reload Reload Safety Safety Analysis Analysis for 105% OL OLTP TP Page A-147 4.0 r-------r----r---.--------r--......---.-------.~-__._-----'-.___-__r--_,
IIII
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Rated)
Power MCPRpp MCPR
(% of rated) Limit Limit 100
,100 1.54 1.54 90 1.61 50 ---
50 1.90 1.90 40 2.04 30 2.27 at > 50%F 30 at> 50%F' 3.17 3.17 I,
at > 50%F 25 at> 50%F 3.47 30 ats at < 50%F 2.95 25 at < 50%F 25ats 3.35 3.35 Figure A.9.146 BOC BOC to NEOC NEOC
" Power-Dependent Power-Dependent MCPR MCPR Limits for
, GE14 Fuel Fuel NSS Insertion,Times NSS Insertion Times TBVOOS, FHOOS, and PLUOOS Combined
,'.,TBVOOS, AREVA AREVA NP Inc.
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 , Revision Revision 0 Reload Safety Analysis for 105% OLTP OLTP . Page A-148 A-148 4.0 ,....----,..----.---.---'--;---.---0'----,----.---,-----,----,
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Power Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 100 1.55 1.55 90 1.61 50 50 ---
50 ' 1.91 40 2.03 30 2.27 30 at at>> 50%F 3.13 3.13 25 at at>> 50%F 3.47 30 at ats< 50%F 2.82 25 at<:
ats 50%F 3.20 Figure A;9.147 A.9.147 ,BOC BOC to EOCLB Power-Dependent MCPR Power-Dependent MCPR Limits for for ATRIUM-10 ATRIUM-10 Fuel NSS Insertion NSS Insertion Times Times TBVOOS, FHOOS, and PLUOOS Combined PLUOOS Combined
, AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry UnitUnit 1 Cycle 9 Revision Revision 0 Reload Reload Safety Safety Analysis for 105% OLOLTP TP Page A-149 4.0 o
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(% of rated)
(% Limit Limit 100 100 1.54 1.54 90 1.61 50 ---
50 1.91 40 2.04 30 2.27 2.27 30 at >> 50%F 3.17 3.17 25 at >> 50%F 3.47 3.47 30 at ats< 50%F 2.95 2.95 25 at ~~> 50%F 3.13 3.13 25 at >> 50%F 3.47 3.47 at* 50%F 30 ats50%F~~
30 2.82 2.82*
25 ats at < 50%F 50%F 3.20
.Figure A.9.149 BOC"to BOC'to NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for for .
ATRIUM-10 ATRIUM-10 Fuel
, Insertion Times TSSS Insertion Times ...
TBVOOS, TBVOOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit Unit 1 Cycle 9 Revision Revision 0 Safety Analysis for 105% OL Reload Safety OLTP TP Page A-151 .
4.0 , - - - - - , - - - . - - - - , - - - - - - - , - - - - . - - - - , - - - - - - - , - - - - - . - - - , - - - - - , - - - - ,
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Power MCPRpp MCPR
(% of rated)
(% Limit Limit 100 100 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 2.05 30 2.29 30 at > 50%F 3.17 3.17 25 at at> > 50%F 3.47 30 at < s 50%F 2.95 2.95 25 at ats < 50%F 3.35
~~FigureA.9.150 Figure A.9.150 BOe BOC to NEOC NEOC Power-Dependent Power-Dependent MCPR Limits for for GE14 Fuel Fuel. .~~
TSSS TSSS Insertion Insertion TimesTimes TBVOOS, FHOOS,and TBVOOS, FHOOS, and PLUOOS PLUOOS Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Browns Ferry Unit 1 Cycle Cycle 9 ;';'Revision Revision 0 Reload Reload Safety Analysis 105% OL Analysis for 105% OLTP TP Page A-152 Page 4.0 o FWCF FWCF 3.5 3.5 o LRNB LRNB A
A CRWE CRWE 3.0
~~t E~~~
2.5 ry 0
2.0 00 O AO 1.5 II- I I I I I 1.0 I ' I I L - . _ - l . ._ _...L..._ _.L..-_----L_ _....L.-_ _.L..-_----L_ _--l...._ _.L..-_----1'---_--I 0o 10 20 30 40 50 ' 60 70 80 90 100 110 110 Power (% Rated)
Rated)
Power MCPRPp MCPR
(%of rated)
(% Limit Limit 100 100 1.59 1.59 90 1.64 1.64 50 50 ---
50 1.91 40 2.05 30 2.29 30 at > 50%F 3.13 3.13' 25 at > 50%F 3.47 3.47 30 at*
at s 50%F 2.82 25 at ats< 50%F 3.20 Figure A.9.151 A.9.1S1 BOC to EOCLB Power-Dependent Power.Dependent MCPR MCPR Limits for for ATRIUM-10 ATRIUM*10 Fuel TSSS Insertion TSSS Insertion Times Times TBVOOS, TBVOOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Np'lnc.
lnc.
.ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 105% OL Reload Safety Analysis for 105% OLTPTP Page A-1 A-153 53 4.0 I "I I I II o.
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(% of rated) Limit Limit 100 100 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 3.17 25 at > 50%F 3.47 3.47 30 ats at < 50%F 2.95 25 at 50%F 3.13 3.13 25 at > 50%F 50%F 3.47 at < 50%F 30 ats 2.82 2.82 25 ats at 5 50%F 3.20 3.20 Figure Figure A.9.153 BOC to NEOC NEOC Power-Dependent MCPR Limits for Power-Dependent ATRIUM-10 Fuel ATRIUM*10 NSS Insertion Times Times EOC-RPT-OOS, EOC*RPT TBVOOS, FHOOS, and PLUOOS Combined
~~OOS, TBVOOS, AREVA NP Inc.~~
ANP-2863(NP}
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision 0 Reload Safety Analysis Analysis for 105%
105% OL OLTPTP Page A-155 Page 4.0 II I II 0o FWCF FWCF, o LRNB LRNB 3.5 At. CRWE CRWE 3.0
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Power MCPRpp MCPR
(% of rated)
(% Limit 100 100 1.54 1.54 '
90 1.61 50 ---
-50 50 1.90 1.90 40 2.04 30 2.27 30 at >> 50%F 3.17 3.17 25 at > 50%F .3.47
,3.47 30 at <s 50%F 50%F 2.95 at < 50%F 25 ats 50%F 3.35 3.35 Figure A.9.154 BOC to,NEOC to NEOC Power-Dependent MCPR Power-Dependent MCPR Limits for for GE14 Fuel GE14
, ,.' NSS NSS Insertion TimesTimes ' . '
EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, FHOOS, and PLUOOS Combined Combined AREVA NP NP Inc. *'i:
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Ferry Unit Unit 1 Cycle 9 Revision 0 Revision Safety Analysis for 105% OLTP Reload Safety OLTP Page A-156 4.0 ,-----r--.,---,-------r----.---,-------r----.---.------,---:---,
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.30 40 50 60 70 70 80 90 100 100 110 110 Power (% Rated)
Rated)
Power MCPRp Power MCPRp
(% of rated)
(% rated) Limit Limit 100 100 . 1.55 1.55 90 1.61 50 ---
50 1.91 40 2.03 30 2.27 30at 30 at >> 50%F 50%F 3.13 3.13 25 at >> 50%F 3.47 3.47 30 at ats< 50%F 2.82 25 at ~~50%F 3.17 3.17 25 at > 50%F 3.47 3.47 30 at s* 50%F 2.95 2.95 25 at~~
.25 ats< 50%F 3.35 A.9.156 BOC*to Figure A.9.156 BOC.to EOCLB Power-Dependent Power-Dependent MCPR Limits for GE14 Fuel NSS Insertion NSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, FHOOS, and PLUOOS PLUOOS Combined AREVA AREVA NP Inc.
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
Browns Ferry Unit Browns Unit 1 Cycle 9 : Revision Revision 0 Reload Reload Safety Safety Analysis Analysis. for 105% OL OLTP TP Page A-158 A-1 58 4.0 O] FWCF o LRNB 3.5 A CRWE 3.0 E.
~~2.5 o~~
~~0 0 2.0 0 A~~
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~~Power. (% Rated)~~
~~Rated)~~
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~~(% of rated)~~
~~(% Limit Limit 100 1.59 1.59 90 1.64 1.64 50 50 ---~~
~~50 1.89 1.89 40 2.05~~
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~~. ATRIUM-10 Fuel TSSS TSSS Insertion Insertion Times Times EOC-RPT-OOS, EOC-RPT-OO~, TBVOOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.~~
~~ANP-2863(NP)~~
~~ANP-2863(NP)~~
~~Browns Ferry Unit Browns Unit 1 Cycle 9 Revision 0~~
.: Revision Reload Reload Safety Safety Analysis for 105% OL OLTP TP Page A-159 Page 4.0 I III II II
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Power MCPRpp MCPR
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(0,(0 Limit Limit 100 100 1.57 1.57 90 1.63
. 1.63 50 50 1.92 1.92 40 2.05 30 2.29 30 at > 50%F 3.17 3.17 25 at > 50%F 3.47 30 at :S< 50%F50%F . 2.95 25 at:S at < 50%F 50%F 3.35 A.9.158 BOC to NEOC Figure A.9.158 Power-Dependent Power-Dependent MCPR MCPR Limits .for for GE14 GE14 Fuel
. TSSS Insertion Insertion Times'.
Times . .'
EOC-RPT-OOS, TBVOOS, EOC.;.RPT;'OOS, TBVOOS, FHOOS, and PLUOOS Combined ~ombined AREVA NP Inc.
. AREVANP
ANp-2863(NP)
ANP-2863(NP)
Browns I Cycle 9 Browns Ferry Unit 1 . Revision Revision 0 105% OL Reload Safety Analysis for 105% OLTP TP A-1 60 Page A-160 4.0 o FWCF FWCF o LRNB LRNB 3.5 3.5
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(% of rated) Limit Limit 100 1.59 1.59 90 1.64 1.64 50 ---
50 1.91 40 2.05 2.05 30 2.29 2.29 30 at > 50%F 3.13 3.13 25 at at> > 50%F . 3.47 30 at ats < 50%F 2.82 2.82 25 at s< 50%F 3.20 Figure A.9.159 A.9.159 BOC to EOCLB Power-Dependent Power*Dependent MCPR Limits for ATRIUM-10 Fuel ATRIUM*10 TSSS Insertion Times Times EOC-RPT-OOS, EOC*RPT *OOS, TBVOOS, FHOOS, and PLUOOS Combined PLUOOS Combined AREVA AREVA NP Inc.Inc:
ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle Cycle 9 Revision O*
0 Reload Safety Analysis for 105% 105% OL TP OLTP Page A-161 Page A':161 4.0 o]o FWCF FWCF o LRNB LRNB 3.5 A
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Rated)
Power Power MCPRpp MCPR
(% of rated)
(% rated) Limit Limit 100 100 1.57 1.57 90 1.63 1.63 50 ---
50 1.92 1.92 40 2.05 2.05 30 2.29 2.29 30 at > 50%F 3.17 3.17 25 at > 50%F 3.47 3.47 30 at ats< 50%F 2.95 2.95 25 at ats< 50%F 3.35 3~35 A.9.160 BOC to EOCLB Figure A.9.160 Power-Dependent Power-Dependent MCPR MCPR Limits for for GE14 Fuel .
TSSS Insertion TSSS Insertion Times Times EOC-RPT-OOS, EOC-RPT -OOS, TBVOOS, TBVOOS, FHOOS, and PLUOOS PLUOOS Combined Combined AREVA NP Inc.
ANP-2863(NP)
ANP-2863(NP)
Browns Unit 1 Cycle 9 Browns Ferry Unit . Revision Revision 0 Analysis for 105% OL Reload Safety Analysis Reload TP OLTP Page A-162 1.4 I III o FWCF FWCF o LRNB LRNB 1.2
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(%
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0.47 Figure A.9.161 All Exposures Exposures Power-Dependent Power-Dependent LHGR Multipliers for Multipliers for ATRIUM-10 ATRIUM-10 Fuel NSS/TSSS Insertion NSSITSSS Insertion Times Times EOOS with TBV In-Service In-Service AREVA AREVA NP Inc.
ANP:'2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1.
Browns FerrY 1 Cycle 9
~~Revision 0 Reload Reload Safety Safety Analysis Analysis for 105%~~
105% OL TP OLTP Page A-163 PageA:'163 1.5 r------..--_._--y-------..--..:,-,--y--~__r--_._--.___-__r-_____,
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Rated)
Power LHGRFACpp LHGRFAC
(%
(% of rated) Multiplier Multiplier 100 1.00 1.00 75 0.78 0.78 30 0.60 0.60 at.> 50%F 30 at> 50%F 0.44 0.44 25 at > 50%F 50%F 0.42 0.42 30 at s< 50%F 0.44 25 at s5 50%F 0.44 Figure A.9.162 Exposures A.9.162 All Exposures Power-Dependent Power-Dependent LHGR Multipliers Multipliers for
. GE14 Fuel' GE14 Fuel NSSITSSS Insertion Times NSSITSSS Times EOOS with TBV In-Service TBV In-Service AREVA NP Inc.
.AREVANP
ANP-2863(NP)
ANP-2863(NP}
Browns Ferry Unit Browns I Cycle 9 Unit 1 .. Revision Revision 0 Reload Safety Reload Safety Analysis for 105%
105% OLTP OLTP Page A-164 A-164 1.5 .------,----,------,,-----r---.-------,----,--"---,-------r----.---,--,----,
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Power LHGRFAC LHGRFACpp *
(% of rated)
(% Multiplier Multiplier 100 0.90 0.90 90 0.83 30 0.62 at > 50%F 30 at> 0.43 0.43 25 at > 50%F 0.39 0.39 30 at <s 50%F' 50%F' 0.47 25 at S< 50%F 50%F 0.46*
0.46 Figure A.9.163 Figure A.9.163 All Exposures All Exposures Power-Dependent Power-Dependent LHGR Multipliers for ATRIUM-10 ATRIUM-10 Fuel
. NSS/TSSS NSSITSSS Insertion TimesTimes EOOS with TBVOOS TBVOOS AREVA NPlnc.
NP Inc.
,ANP-2863(NP)
ANP-2863(NP)
Browns Ferry Unit 1 Cycle 9 . Revision Revision 0 Reload Safety Safety Analysis for 105% OLTP OLTP A-165 Page A-165 1.5 I I o Required LHGRFAc LHGRF AC I 1.25 1.25 1.0
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(% Multiplier Multiplier 100 0.99 75 0.77 30 0.58 30 at > 50%F 0.37 25 at > 50%F 0.31 30 at <s 50%F 0.44 25 at ~~> from the public.~~
I.
~~AFFIDAVIT AFFIDAVIT.~~
~~COMMONWEALTH OF VIRGINIA COMMONWEALTH VIRGINIA })~~
~~}) ssss...~~
~~CITY OF LYNCHBURG LYNCHBURG })~~
~~1. My name is Gayle Gayle F. Elliott. I am Manager, Product Licensing, for AREVA NP Inc. and as such I am authorized authorized to execute execute this Affidavit.~~
~~2. II am familiar with the criteria applied by AREVANP AREVA NP to determine whether whether.~~
certain AREVA NP information certain AREVA information is proprietary. I am familiar with the policies establishe~by established by AREVA NP to'ensure j\REVA to*ensure the proper application application of these criteria.
3.
3: I am familiar with the AREVAAREVA NP information contained contained in the report ,
ANP-2877(P),
ANP-2877(P}, Revision 0, entitled "Mechanical Design Report for for Browns Ferry Ferry Unit 1 Reload
, BFE1-9 ATRIUM-10 ATRIUM-10 Fuel Assemblies Assemblies (105%
(105% OLTP},"OLTP)," dated dated November November 2009 and referred to herein as "Document." Information contained herein contained in this Document has been classified by AREVA .
NP as proprietary NPas proprietary in accordance accordance with the policies established established by AREVA AREVA NP for the control and forthecontrol protection of proprietary
. protection proprietary and confidential information.
~~4. This Document Document contains information information of a proprietary proprietary and confidential nature nature *.~~
and is of the type customarily held held in confidence by AREVA NP and not made available availabl~ to the the Based on my experience, public. Based experience, I am aware that other companies regard information c;>f regard information of thethe kind contained in this Document Document as proprietary proprietary and confidential.
confidential.
~~5. Document has been made available This Document the U.S:~~
available to the U.S. Nuclear Nuclear Regulatory, Regulatory ,.
Commission in confidence with the request that the information therequest information contained Document be contained in this Docu":lent be
. ' '. . .. . . . ~ . ,
withheld from public disclosure. The request requestfor for withholding of proprietary information made in information is made,
,'f' .
accordance with 10 CFR 2.390. The accordance The information information for which withholding from disclosure is requested qualifies qualifies under 10 CFR 2.390(a)*(4) 2.390(a)(4) "Trade secrets and commercial commercial or financial financial. ..
~~information."~~
6. The following criteria are customarily applied by AREVA AREVA NP to determine determine*
whether whether information information should be classified as proprietary:
(a) The information information reveals details of AREVA NP's research and development development plans and programs or their results.
(b) Use of the information by a competitor competitor would permit the competitor to to*
significantly significantly reduce its expenditures, in in time or resources, to design, produce, or market market a similar product or service.
(c) The information information includes data or analytical includes test data analytical techniques concerning concerning a process, methodology, or component, the application of which which results in in a competitive advantage for AREVA AREVA NP.
(d) information reveals certain distinguishing aspects of a process, ..
The information methodology, or component, the exclusive use of which provides a advantage for AREVA
. competitive advantage AREVA NP in in productdptimization product optimization or marketability marketability...
(e)
(e) The information is vital to aa competitive The competitive-advantage '
advantage held.
by AREVA AREVANP, NP, would would be heipful be helpful to competitors competitors to AREVA NP, and would likely cause substantial substantial harm to the competitive position of AREVA NP.
The information The information in in the the Document Document is considered considered. proprietary for the reasons reasons set forth in setforth in paragraphs paragraphs 6(b) and 6(c) above above...
with AREVA NP's policies governing the protection and control 7.
~~7. In accordance with In accordance AREVA NP'spolicies governing the protection arid control of information, of information, proprietary proprietary .~~
information contained information contained in in this Document Document have been made available,ava.'ilable, on aa limited on basis, to limited basis; to others outside AREVA NP only as required and under suitable others outsideAREVA suitableag~eement agreement providing for providing for nondisclosure nondisclosure and limited use of the information.
8. AREVA NP policy requires that proprietary information be kept in a secured 8.' AREVA NP policy requires that proprietary information be kept in a secured file or area and distributed on a need-to-know basis.
~~file or area and distributed on a need-to-know basis ..~~
~~9. The foregoing statements are true and correct to the best of my knowledge,~~
~~9. The foregoing statements are true and correct to: the best of my knowledge,* .~~
information, and belief.
information, and belief.
SUBSCRIBED before me this 5`k SUBSCRIBED before me this ~_'--_ _
day of November 2009.
5--*tb day of November 2009.
Sherry L. McFaden NOTARY SherryPUBLIC, L. McFaden COMMONWEALTH
. OF VIRGINIA COMMISSION MY NOTARY EXPIRES: 10/31/10 PUBLIC, COMMONWEALTH OF VIRGINIA Reg. . MY # 7079129 COMMISSION EXPIRES: 10/31/10 Reg. #7079129 .
-m a~ - - -
--. SlERRY
..... ~- L.MCADENI Notary Pubflc q
i Commonwealth SHERRY L. MC'ADE~
of V11ginia Notary pubnc 7079129 Commonwealth of 31,20100 Vl,glnla t My Commission . 1019129 Expires Oct My Commission Expires Oct 31. 20'0
.~
AFFIDAVIT AFFIDAVIT COMMONWEALTH COMMONWEALTH OF VIRGINIA VIRGINIA )
) ss.
CITY CITY OF OF LYNCHBURG LYNCHBURG )
1. My Gayle F. Elliott. I am Manager, Product Licensing, My name is Gayle Licensing, for AREVA NP Inc. and as such I am authorized authorized to execute execute this Affidavit.
2. I am familiar with the criteria criteria applied applied by AREVA AREVA NP to determine determine whether whether certain AREVA information is proprietary. I am familiar with the policies AREVA NP information policies established established by AREVA NP to ensure ensure the proper proper application application of these criteria.
~~3. II am familiar with the AREVA familiarwith information contained AREVA NP information contained in the report ANP-2863(P),~~
ANP-2863(P), Revision Revision 0, entitled entitled "Browns Ferry Unit 1 Cycle 9 Reload Safety Safety Analysis for 105% OLTP," dated November November 2009 ard and referred to herein herein as "Document." Information Information contained in this Document Document has been classified classified by AREVA AREVA NP as proprietary proprietary in accordance accordance with the policies policies established ,byby AREVA NP for the control and protection protection of proprietary proprietary and' and confidential information.
4.
4: Document contains information ota This Document of a proprietary and confidential nature '
customarily held in confide~ce and is of the type customarily confidence by AREVA AREVA NP and not made available to"the to the public. Based on my experience, II am aware that other companies regard information ofthe of the
.' kind contained in this Document Document as proprietary proprietary and confidential.
,, 5. This Document has been been made made ayailable available to the U.S. Nuclear Regulatory Commission in confidence Commission confidence with the request that the information contained in this Document be be withheld from public disclosure. The request withheld request for withholding of proprietary proprietary information information is made inin
accordance with 10 accordance 10 CFR 2.390. The information for which withholding from disclosure disclosure is _
requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets secrets and commercial or o~financial financial information."
~~6. The following criteria are customarily customarily applied by AREVA NP to determine determine information should be classified as proprietary:~~
whether information (a) The information reveals details details of AREVA AREVA NP's research and development plans and programs programs or their results.
(b) Use of the information information by a competitor would permit the competitor competitor to significantly reduce its expenditures, in significantly in time or resources, to design, produce, or market a similar product or service.
(c) includes test data or analytical The information includes analytical techniques techniques concerning a methodology, or component, the application process, -methodology, application of which results in in a competitive advantage for AREVA NP.
competitive advantage (d) The information information reveals certain certain distinguishing aspects of a process, methodology, or component, the exclusive use of which provides provides a competitive competitive advantage for AREVA NP in product optimization optimization or marketability.
(e) The information information is vital to a competitive ~dvantage advantage held by AREVA AREVA NP, would be helpful to competitors to AREVA NP, and would likely cause substantial sUbstantial harm harm to the competitive position of AREVA NP.
The information in in the Document is considered proprietary proprietary for the reasons set forth in in paragraphs 6(b) and 6(c) above.
paragraphs
~~7. In accordance~~
- In accordance with AREVA NP's policies governinggoverning the protection and control of information,
-,of information, proprietary proprietary information information contained contained inin this this Document Document have been available, .
been made available..
on a limited basis, to others outsideAREVA outside AREVA NP only as required and under suitable -agreementagreement providing for nondisclosure providing for nondisclosure and limited use of the information. -
~~8. AREVA NP policy policy requires that proprietary information information be kept in in a secured file or area and distributeddistributed on a need-to-know need-to-know basis.~~
~~9. The foregoing statements statements are true and correct to the best of my knowledge, information, and belief.~~
SUBSCRIBED SUBSCRIBED before me this this ----'~::....~_.;..._. __
November 2009.
day of November Sherry L. L. McFaden McFaden NOTARY PUBLIC, COMMONWEALTH NOTARY COMMONWEALTH OF VIRGINIA VIRGINIA
~~I COMMISSION EXPIRES:~~
MY COMMISSION EXPIRES: 10/31/10. 10/31/10 Reg. # 7079129 Reg. 7079129
.- -- --SHERRY
... --- --L.MCFADIN I.
~
SNIRRY ...
Notary MCFADUN Public Notary PUblic Commonwoelth of Virginia commonwealth 707912 l
Virginia
~.
J 7079129
~~My IImy Commlilion t,.vuuiiililllllli~~
=_ %' 1T11*_
Expire.
WA[JIIUUI Oct VhI 31. 2010
. * . I. £UIlUl
- .I
AFFIDAVIT AFFIDAVIT
. STATE OF WASHINGTON WASHINGTON ))
.)) ss.
COUNTY COUNTY OF BENTON BENTON )
1.
~~1. My name is Alan B. Meginnis. II am Manager, Product Licensing, for.AREVA for*AREVA NP Inc. and as such . I am authorized to execute execute this Affidavit. ,~~
2. I am familiar with the criteria criteria applied by AREVA NP to determine whether whether*
certain AREVA AREVA NP information information is proprietary. I am familiar with the policies established established by AREVA NP to-ensure AREVA to.ensure the proper application of these criteria.
~~3. information contained in~~
. II am familiar with the AREVA NP information in the report report EMF~ EMF-2859(P), Revision 0, entitled, "Browns Ferry Unit 1 Cycle 9 Fuel Cycle Design," dated: dated September September 2009 and referred to herein as "Document." Information Information contained in in this Document Document has ha~ been classified by AREVA NP as proprietary been proprietary inin accordance accordance with the policies establishedestablished by AREVA AREVA NP for the control and protection protection of proprietary proprietary and confidential information.
information.
4. This Document contains information of a proprietarY proprietary and confidential confidential nature nature and is of the type type customarily confidence by AREVA customarily held in confidence AREVA NP NP and not made available t~ to the the public.
public
...Based on my experience, experience, I am aware aware that other companies regard information information of the the kind contained contained in in this Document
.Document as proprietary proprietary and confidential.
. . 5. This Document Document has been made made available to the U.S. Nuclear Regulatory Regul~tory Commission in confidence with the request that the information in confidence information contained in in this Document*be Document be withheld from public disclosure. The request for withholding of proprietary proprietary information .is is made made in accordance in accordance with ~ith1100 CFR 2.390. The information for which withholding from disclos~re information for-which disclosure is
requested qualifies under requested qualifies under 10 10 CFR 2.390(a)(4) "Trade secrets CFR2.390(a)(4) secrets and commercial commercial or financial finanqial information."
information."
6. The following criteria are following criteria are customarily customarily applied AREVA NP to determine applied by AREVA determine whether whether information information should be classified classified as proprietary:
(a) The information information reveals reveals details details of AREVA AREVA NP's research research and development development plans plans and programs or or their results.
(b) Use Use of the information information by aa competitor competitor would permitpermit the the competitor competitor to to significantly reduce significantly expenditures, in reduce its expenditures, time or resources, to design, produce, in -time produce, or market a similar product or service.
(c) information includes test data The information analytical techniques data or analytical techniques concerning concerning a process, methodology, or component, the application application of which results in in a competitive competitive advantage advantage for AREVA NP.
(d) The information information reveals reveals certain distinguishing distinguishing aspects of a process, methodology, or component, the exclusive exclusive use of which provides provides a '
competitive advantage advantage for AREVA NP in in product optimization optimization ormarketability.
ormarketability.
(e)
(e) The information information is vital Vital to a competitive competitive advantage advantage held by by AREVA ~~,
AREVA NP, would '
be helpful to competitors to AREVA NP NP,j and would' would likely' likely cause cause substantial harm to the competitive harm position of AREVA NP.
competitive position' The information in Document is considered proprietary in the Document proprietary for the reasons set forth in in paragraphs 6(b), 6(d) and 6(e) above.
paragraphs
7. accordance with AREVA NP's policies governing the protection and control In accordance In of information, proprietary information contained in in this Document have been made available, limited basis, to others outsideAREVA on a limited outside AREVA NP only. only as required required and under suitable agreement providing for nondisclosure and limited use of the information.
, 8. AREVA NP policy requires that proprietary information be kept in' in a secured' secured need-to-know basis.
file or area and distributed on a need-to-know
~~9. The foregoing statements statements are true and correct correct to the best of my knowledge, information, and belief.~~
2-? p SUBSCRIBED before me this __
SUBSCRIBED before 5_("_~_
o~-t~b.ll("',
day of*i rU Pz 2009.
A -ACN
~~~\MrLCs~~
. Susan Susan K.MCCOY' K. McCoy c::::::::: ~
NOTARY PUBLIC, STATE OF WASHINGTON NOTARY WASHINGTON COMMISSION EXPIRES:
MY COMMISSION EXPIRES: 1/10/12 1/10/12
AFFIDAVIT AFFIDAVIT STATE WASHINGTON )
STATE OF WASHINGTON
) ss.
COUNTY COUNTY OF BENTON BENTON )
1.
~~1. My name is Alan B. B. Meginnis.~~
~~Meginnis. II am Manager, Product Licensing, for AREVA NP Inc. and as such II am authorized authorized to execute execute this Affidavit.~~
~~2. II am familiar with the criteria applied by AREVA NP to determine determine whether 1.~~
certain AREVA AREVA NP information is proprietary. II am familiar with the policies established by
\ .
AREVA NP to ensure ensure the proper application of these criteria.criteria ..
3. .. II am familiar with the AREVA NP NP information information contained contained in in the report ANP-2821P, Revision 0, entitled "Browns Ferry Unit 1 Thermal-Hydraulic ANP-2821P, thermal-Hydraulic Design ReportReport for ATRIUM-10 ATRIUM-10 Fuel Assemblies (105% OLTP)," dated June 2009 and referred to herein herein as as "Document." Information "Document." Information contained contained in in this this Document Document hashas been classified by AREVA'NP been classified AREVA NP as as proprietary proprietary in in accordance accordance with the the policies policies established established by AREVA NP for the control and. and protection protection of proprietary proprietary and confidential confidential information.
4.
~~4. This Document Document contains contains information of a proprietary and confidential nature nature.~~
and is and is of the type type customarily held in confidence customarily held confidence by AREVA NP and and not made made available to thethe public.
public. Based Based on on my experience, II am aware that my experience, that other companies companies regard information of the.
regard information the kind contained in in this Document as proprietary and and confidential.
confidential.
5.
5.* This Document Document has been made available U.S. Nuclear available to the U.s. Nuclear Regulatory Commission in Commission in confidence confidence with the request with the request that that the the information information contained in in this Docl.iment Document be be withheld from public disclosure. The request for withholding* withholding of proprietary proprietary information made .
information is made in accordance in accordance with with 10 10 CFR CFR 2.390.
2.390. The information for The information for which which withholding withholding from disclosure is
requested qualifies under 10 CFR 2.390(a)(4) "Trade secrets and commercial commercial or financial information."
~~6. The following criteria are customarily applied applied by AREVA AREVA NPto determine NP to determine whether information information should be classified classified as proprietary:~~
(a) The information reveals details of AREVA NP's research and development development plans and programs or their results.
(b) Use of the information information by a competitor competitor would permit permit the competitor to reduce its expenditures, in time or resources, to design, produce, significantly reduce.
or market market a similar product or service.
(c) The information information includes test data or analytical techniques concerning a techniques concerning process, methodology, or component, the application application of which results in a advantage f~r competitive advantage for AREVA NP.
(d)
(d). information reveals certain distinguishing aspects The information aspects of a process, methodology, or component, the exclusive exclusive use of which provides aa which provides competitive advantage advantage for AREVA AREVA NP in product optimization marketability~
optimization or marketability.
(e) The information information is vital to a competitive competitive advantage advantage held by AREVA NP, would be helpful to competitors to AREVA AREVA NP, and would likely causecausesub~tantial substantial harm to the competitive competitive position of AREVA AREVA NP.
The information information in the Document is considered considered proprietary for the reasons set forth in .
r .
paragraphs 6(b), 6(d) and 6(e) above.
paragraphs
7. In In accordance accordance with AREVA policies governing AREVA NP's pOlicies governing the protection protection and control of information, proprietary proprietary information contained in this Document information contained Document have been been made available, available, on a limited basis, basis,,to to others others outside AREVA NP only as required and under under suitable agreement agreement providing for nondisclosure nondisclosure and limited use of the information.
8. proprietary information.be AREVA NP policy requires that proprietary information be kept in aa- secured file or area and distributed distributed on a need-to-know need-to-know basis.
~~9. The foregoing statements statements are true and correct to the best of my knowledge, information, and belief.~~
,information,
('
SUBSCRIBED before me SUBSCRIBED me this this _-I./_J-J __
Of-.:j~~~::.....*......-_,2009.
day of ' 2009.
CS Susan K. McCoy .'
Susan K. McCoy ( ,
NOTARY PUBLIC, STATE OF WA'NGTON w'/ts NGTON COMMISSION EXPIRES: 1/10/12 MY COMMISSION 1/10/12
"

ML093350653

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