ML093140266

Attachment 15, Browns Ferry Unit 1 - Technical Specification Change 467, EMF-2950(NP), Revision 0, Extended Power Uptate, LOCA Break Spectrum Analysis Report

ML093140266
Person / Time
Site:	Browns Ferry
Issue date:	08/31/2009
From:	Schnepp R AREVA NP
To:	Office of Nuclear Reactor Regulation
References
L32 090904 802, TS 467 EMF-2950(NP), Rev 0
Download: ML093140266 (155)

Text

{{#Wiki_filter:ATTACHMENT 15 Browns Ferry Nuclear Plant (BFN) Unit 1 Technical Specifications (TS) Change 467 Revision of Technical Specifications to allow utilization of AREVA NP fuel and associated analysis methodologies LOCA Break Spectrum Analysis Report Attached is the non-proprietary version of the LOCA break spectrum analysis report for 120% OLTP conditions. ATTACHMENT 15 Browns Ferry Nuclear Plant (BFN) Unit 1 Technical Specifications (TS) Change 467 Revi~ion of Technical Specifications to allow utilization of AREVA NP fuel and associated analysis methodologies LOCA Break Spectrum Analysis Report Attached is the non-proprietary version of the LOCA break spectrum analysis report for 120% OLTP conditions.

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0 C (D X - x CD C C/) ~0c CD >3DC I-0 Co 0 Co 0 C,) (D m no L32 090904 802 EMF-2950(NP) Revision 0 Browns Ferry Units 1, 2, and 3 Extended Power Uprate . LOCA Break Spectrum Analysis A August 2009 AREVA

AREVA NP Inc. ISSUED IN ON-UNE-DOCUMENT SYSTEM IJ EMF-2950(NP) Revision 0 Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Prepared: R.R. Schnepp, Supervisor Thermal-Hydraulics Richland Date Reviewed: Reviewed: Approved: M.S. Stricker, Engineer Thermal-Hydraulics Richland A.B. Meginnis, Manager Product Licensing 9a-31e Date Date Date D.3Vrrd, Manager Thermal-Hydraulics Richland paj /20030619150244v18 AREVA NP Inc. Prepared: Reviewed: Reviewed: Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis R. R. Schnepp, Supervisor Thermal-Hydraulics Richland M.S. Stricker, Engineer Thermal-Hydraulics Richland A.B. Meginnis, Manager Product Licensing Approved: ~n§. ..,.~~-- Thermal-Hydraulics Richland paj 120030619150244v18 ISSUED IN ON-UNE-DOCUMENT SYSTEM DATE: 11/31 /()'1 r Date EMF-2950(NP) Revision 0 r/3 1/;Jr Date Date

Customer Disclaimer Important Notice Regarding Contents and Use of This Document Please Read Carefully AREVA NP, Inc.'s warranties and representations concerning the subject matter of this document are those set forth in the agreement between AREVA NP, Inc. and the Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such agreement, neither AREVA NP, Inc. nor any person acting on its behalf:

a. makes any warranty or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information, apparatus, method, or process disclosed in this document will not infringe privately owned rights; or

b.

assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this document. The information contained herein is for the sole use of the Customer. In order to avoid impairment of rights of AREVA NP, Inc. in patents or inventions which may be included in the information contained in this document, the recipient, by its acceptance of this document, agrees not to publish or make public use (in the patent use of the term) of such information until so authorized in writing by AREVA NP, Inc. or until after six (6) months following termination or expiration of the aforesaid Agreement and any extension thereof, unless expressly provided in the Agreement. No rights or licenses in or to any patents are implied by the furnishing of this document. Customer Disclaimer Important Notice Regarding Contents and Use of This Document Please Read Carefully AREVA NP, Inc.'s warranties and representations concerning the subject matter of this document are those set forth in the agreement between AREVA NP, Inc. and the Customer pursuant to which this document is issued. Accordingly, except as otherwise expressly provided in such agreement, neither AREVA NP, Inc. nor any person acting on its behalf:

a.

makes any warranty or representation, express or implied, with respect to the accuracy, completeness, or usefulness of the information contained in this document, or that the use of any information, apparatus, method, or process disclosed in this document will not infringe privately owned rights; or

b.

assumes any liabilities with respect to the use of, or for damages resulting from the use of, any information, apparatus, method, or process disclosed in this document. The information contained herein is for the sole use of the Customer. In order to avoid impairment of rights of AREVA NP, Inc. in patents or inventions which may be included in the information contained in this document, the recipient, by its acceptance of this document, agrees not to publish or make public use (in the patent use of the term) of such information until so authorized in writing by AREVA NP, Inc. or until after six (6) months following termination or expiration of the aforesaid Agreement and any extension thereof, unless expressly provided in the Agreement. No rights or licenses in or to any patents are implied by the furnishing of this document.

browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page i Nature of Changes This document is the nonproprietary version of document EMF-2950(P) Revision 2. The following items list the changes which were made in Revision 2 of EMF-2950(P): Item Page Description and Justification

1.

All Added brackets for proprietary items.

2.

vi, 1-1, Removed statements that CLTP was only applicable for Units 2 and 3 4-5, 4-20, since Unit 1 was subsequently licensed to CLTP. CLTP is applicable for 6-2 all three units.

3.

1-2 Clarified that future licensing of MELLLA+ is supported via [ ]. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Item

1.

Nature of Changes This document is the* nonproprietary version of document EMF-2950{P) Revision 2. The following items list the changes which were made in Revision 2 of EMF-2950(P): Page Description and Justification All Added brackets for proprietary items. EMF-2950(NP) Revision 0 Page i

2.

vi, 1-1, 4-5,4-20, 6-2 Removed statements that CL TP was only applicable for Units 2 and 3 since Unit 1 was subsequently licensed to CL TP. CL TP is applicable for all three units.

3.

1-2 Clarified that future licensing of MELLLA+ is supported via [ ]. AREVA NP Inc.

Browns Ferry Units 1,2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page ii Contents 1.0 Introduction 1-1 2.0 Sum mary of Results....................................................................................................... 2-1 3.0 LOCA Description.......................................................................................................... 3-1 3.1 Accident Description........................................................................................... 3-1 3.2 Acceptance Criteria............................................................................................ 3-2 4.0 LOCA Analysis Description...................................................................................... 4-1 4.1 Blowdown Analysis............................................................................................. 4-1 4.2 Refill / Reflood Analysis...................................................................................... 4-2 4.3 Heatup Analysis................................................................................................. 4-2 4.4 Plant Parameters................................................................................................ 4-3 4.5 ECCS Parameters.............................................................................................. 4-3 5.0 Break Spectrum Analysis Description............................................................................ 5-1 5.1 Lim iting Single Failure.................................................................................... 5-1 5.2 Recirculation Line Breaks................................................................................... 5-1 5.3 Non-Recirculation Line Breaks........................................................................... 5-3 5.3.1 HPCI Line Breaks................................................................................. 5-3 5.3.2 LPCS Line Breaks................................................................................ 5-4 5.3.3 LPCI Line Breaks................................................................................. 5-4 5.3.4 Main Steam Line Breaks.................................................................. 5-4 5.3.5 Feedwater Line Breaks........................................................................ 5-5 5.3.6 RCIC Line Breaks................................................................................. 5-5 5.3.7 RW CU Line Breaks.............................................................................. 5-6 5.3.8 Instrum ent Line Breaks........................................................................ 5-6 6.0 Recirculation Line Break LOCA Analyses...................................................................... 6-1 6.1 Lim iting Break Analysis Results......................................................................... 6-1 6.2 Break Location Analysis Results........................................................................ 6-2 6.3 Break Geometry and Size Analysis Results....................................................... 6-2 6.4 Lim iting Single-Failure Analysis Results............................................................. 6-2 6.5 Axial Power Shape Analysis Results.................................................................. 6-2 6.6 State Point Analysis........................................................................................... 6-2 7.0 Non-Recirculation Line LOCA Analysis.......................................................................... 7-1 7.1 Lim iting ECCS Line Break Results..................................................................... 7-1 8.0 Single-Loop Operation LOCA Analysis.......................................................................... 8-1 8.1 SLO Analysis Modeling Methodology............................................................ 8-1 8.2 SLO Analysis Results......................................................................................... 8-2 9.0 Long-Term Coolability.................................................................................................... 9-1 10.0 Conclusions.................................................................................................................. 10-1 11.0 References................................................................................................................... 11-1 Appendix A Supplemental Information........................................................................... A-1 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate EMF-2950(NP) Revision 0 Page ii LOCA Break Spectrum Analysis Contents 1.0 Introduction.................................................................................................................... 1-1 2.0 Summary of Results....................................................................................................... 2-1 3.0 LOCA Description.......................................................................................................... 3-1 3.1 Accident Description........................................................................................... 3-1 3.2 Acceptance Criteria............................................................................................ 3-2 4.0 LOCA Analysis Description............................................................................................4-1 4.1 Blowdown Analysis............................................................................................. 4-1 4.2 Refill! Reflood Analysis............................ :.........................................................4-2 4.3 Heatup Analysis................................................................................................. 4-2 4.4 Plant Parameters................................................................................................ 4-3 4.5 ECCS Parameters.............................................................................................. 4-3 5.0 Break Spectrum Analysis Description............................................................................ 5-1 5.1 Limiting Single Failure........................................................................................ 5-1 5.2 Recirculation Line Breaks................................................................................... 5-1 5.3 Non-Recirculation Line Breaks........................................................................... 5-3 5.3.1 HPCI Line Breaks................................................................................. 5-3 5.3.2 LPCS Line Breaks................................................................................ 5-4 5.3.3 LPCI Line Breaks................................................................................. 5-4 5.3.4 Main Steam Line Breaks...................................................................... 5-4 5.3.5 Feedwater Line Breaks........................................................................ 5-5 5.3.6 RCIC Line Breaks................................................................................. 5-5 5.. 3.7 RWCU Line Breaks.............................................................................. 5-6 5.3.8 Instrument Line Breaks........................................................................ 5-6 6.0 Recirculation Line Break LOCA Analyses...................................................................... 6-1 6.1 Limiting Break Analysis Results......................................................................... 6-1 6.2 Break Location Analysis Results........................................................................ 6-2 6.3 Break Geometry and Size Analysis Results....................................................... 6-2 6.4 Limiting Single-Failure Analysis Results............................................................. 6-2 6.5 Axial Power Shape Analysis Results.................................................................. 6-2 6.6 State Point Analysis........................................................................................... 6-2 7.0 Non-Recirculation Line LOCA Analysis.......................................................................... 7-1 7.1 Limiting ECCS Line Break Results..................................................................... 7-1 8.0 Single-Loop Operation LOCA Analysis.......................................................................... 8-1 8.1 SLO Analysis Modeling Methodology................................................................. 8-1 8.2 SLO Analysis Results......................................................................................... 8-2 9.0 Long-Term Coolability.................................................................................................... 9-1 10.0 Conclusions.................................................................................................................. 10-1 11.0 References................................................................................................................... 11-1 Appendix A Supplemental Information............................................................................... A-1 AREVA NP Inc.

Browns Ferry Units 1,2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page iii Tables 4.1 In itia l C o n d itio ns............................................................................................................. 4 -5 4.2 Reactor System Param eters.......................................................................................... 4-6 4.3 ATRIUM-10 Fuel Assembly Parameters........................................................................ 4-7 4.4 High-Pressure Coolant Injection Parameters................................................................. 4-8 4.5 Low-Pressure Coolant Injection Parameters.................................................................. 4-9 4.6 Low-Pressure Core Spray Parameters........................................................................ 4-10 4.7 Automatic Depressurization System Parameters......................................................... 4-11 4.8 Recirculation Discharge Isolation Valve Parameters................................................... 4-12 5.1 ECCS Single Failure......... .......... 5-7 5.2 Available ECCS for ECCS Line Break LOCAs............................................................... 5-8 6.1 Results for Limiting TLO Recirculation Line Break 0.5 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial 102% EPU 105% Flow..................................... 6-3 6.2 Event Times for Limiting TLO Recirculation Line Break 0.5 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial 102% EPU 105% Flow..................................... 6-4 6.3 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow S F -B A T T........................................................................................................................ 6 -5 6.4 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow S F-LO C A /D G E N............................................................................................................ 6-6 6.5 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow S F -H P C I......................................................................................................................... 6 -7 6.6 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow S F -L P C I.......................................................................................................................... 6 -8 6.7 TLO Recirculation Line Break Spectrum Results for 102% EPU [ ] S F -B A T T........................................................................................................................ 6 -9 6.8 TLO Recirculation Line Break Spectrum Results for 102% CLTP 105% Flow S F -B A T T...................................................................................................................... 6 -10 6.9 Summary of TLO Recirculation Line Break Results Highest PCT Cases.................... 6-11 7.1 Event Times for Limiting ECCS Line Break 0.4 ft2 Double-Ended Guillotine SF-BATT Top-Peaked Axial 102% EPU 105% Flow...................................... 7-2 7.2 Non-Recirculation Line Break Spectrum Results for 102% EPU................................... 7-3 8.1 Results for Limiting SLO Recirculation Line Break 0.6 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial [ ]................................ 8-3 8.2 Event Times for Limiting SLO Recirculation Line Break 0.6 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial [ ]................................ 8-4 8.3 SLO Recirculation Line Break Spectrum Results........................................................... 8-5 8.4 Single-and Two-Loop Operation PCT Summary........................................................... 8-6 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Tables EMF-2950(NP) Revision 0 Page iii 4.1 Initial Conditions............................................................................................................. 4-5 4.2 Reactor System Parameters..........................................................................................4-6 4.3 ATRIUM-10 Fuel Assembly Parameters........................................................................4-7 4.4 High-Pressure Coolant Injection Parameters.................................................................4-8 4.5 Low-Pressure Coolant Injection Parameters..................................................................4-9 4.6 Low-Pressure Core Spray Parameters........................................................................4-10 4.7 Automatic Depressurization System Parameters.........................................................4-11 4.8 Recirculation Discharge Isolation Valve Parameters...................................................4-12 5.1 ECCS Single Failure...................................................................................................... 5-7 5.2 Available ECCS for ECCS Line Break LOCAs............................................................... 5-8 6.1 Results for Limiting TLO Recirculation Line Break 0.5 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial 102% EPU 105% Flow..................................... 6-3 6.2 Event Times for Limiting TLO Recirculation Line Break 0.5 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial 102% EPU 105% Flow..................................... 6-4 6.3 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-BATT......................................................................................................................... 6-5 6.4 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-LOCAIDGEN............................................................................................................ 6-6 6.5 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-HPCI......................................................................................................................... 6-7 6.6 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-LPCI......................................................................................................................... 6-8 6.7 TLO Recirculation Line Break Spectrum Results for 102% EPU [ ] SF-BATT............................................................... ~........................................................ 6-9 6.8 TLO Recirculation Line Break Spectrum Results for 102% CL TP 105% Flow SF-BATT...................................................................................................................... 6-10 6.9 Summary of TLO Recirculation Line Break Results Highest PCT Cases.................... 6-11 7.1 Event Times for Limiting ECCS Line Break 0.4 ft2 Double-Ended Guillotine SF-BATT Top-Peaked Axial 102% EPU 105% Flow...................................... 7-2 7.2 Non-Recirculation Line Break Spectrum Results for 102% EPU................................... 7-3 8.1 Results for Limiting SLO Recirculation Line Break 0.6 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial [ ]................................ 8-3 8.2 Event Times for Limiting SLO Recirculation Line Break 0.6 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial [ ]................................ 8-4 8.3 SLO Recirculation Line Break Spectrum Results........................................................... 8-5 8.4 Single-and Two-Loop Operation PCT Summary........................................................... 8-6 AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page iv Figures 4.1 Flow Diagram for EXEM BWR-2000 ECCS Evaluation Model................. 4-13 4.2 RELAX System Blowdow n M odel................................................................................ 4-14 4.3 RELAX Hot Channel Blowdown Model Top-Peaked Axial........................................... 4-15 4.4 RELAX Hot Channel Blowdown Model Mid-Peaked Axial........................................... 4-16 4.5 E C C S S chem atic......................................................................................................... 4-17 4.6 Axial Power Distributions at 102% EPU/105% Flow.................................................... 4-18 4.7 Axial Power Distributions at 102% EPU/[ I.................................................. 4-19 4.8 Axial Power Distribution at 102% CLTP/105% Flow.................................................... 4-20 6.1 Limiting TLO Recirculation Line Break Upper Plenum Pressure.................................. 6-12 6.2 Limiting TLO Recirculation Line Break Total Break Flow Rate.................................... 6-12 6.3 Limiting TLO Recirculation Line Break Core Inlet Flow Rate....................................... 6-13 6.4 Limiting TLO Recirculation Line Break Core Outlet Flow Rate.................................... 6-13 6.5 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate........... 6-14 6.6 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Suction Flow Rate........ 6-14 6.7 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Exit Flow Rate.............. 6-15 6.8 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate......... 6-15 6.9 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate..... 6-16 6.10 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate........... 6-16 6.11 Limiting TLO Recirculation Line Break ADS Flow Rate............................................... 6-17 6.12 Limiting TLO Recirculation Line Break HPCI Flow Rate............................................. 6-17 6.13 Limiting TLO Recirculation Line Break LPCS Flow Rate............................................. 6-18 6.14 Limiting TLO Recirculation Line Break Intact Loop LPCI Flow Rate............................ 6-18 6.15 Limiting TLO Recirculation Line Break Broken Loop LPCI Flow Rate......................... 6-19 6.16 Limiting TLO Recirculation Line Break Upper Downcomer Mixture Level.................... 6-19 6.17 Limiting TLO Recirculation Line Break Lower Downcomer Mixture Level.................... 6-20 6.18 Limiting TLO Recirculation Line Break Lower Downcomer Liquid Mass...................... 6-20 6.19 Limiting TLO Recirculation Line Break Intact Loop Discharge Line Liquid Mass......... 6-21 6.20 Limiting TLO Recirculation Line Break Upper Plenum Liquid Mass............................. 6-21 6.21 Limiting TLO Recirculation Line Break Lower Plenum Liquid Mass............................. 6-22 6.22 Limiting TLO Recirculation Line Break Hot Channel Inlet Flow Rate........................... 6-22 6.23 Limiting TLO Recirculation Line Break Hot Channel Outlet Flow Rate........................ 6-23 6.24 Limiting TLO Recirculation Line Break Hot Channel Coolant Temperature at the L im iting N o d e............................................................................................................... 6 -2 3 6.25 Limiting TLO Recirculation Line Break Hot Channel Quality at the Limiting Node....... 6-24 6.26 Limiting TLO Recirculation Line Break Hot Channel Heat Transfer Coef. at the L im iting N o d e.............................................................................................................. 6 -24 6.27 Limiting TLO Recirculation Line Break Cladding Temperatures.................................. 6-25 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Figures EMF-2950(NP) Revision 0 Page iv 4.1 Flow Diagram for EXEM BWR-2000 ECCS Evaluation Model............................. :.......4-13 4.2 RELAX System Blowdown Model................................................................................4-14 4.3 RELAX Hot Channel Blowdown Model Top-Peaked Axial...........................................4-15 4.4 RELAX Hot Channel Blowdown Model Mid-Peaked Axial...........................................4-16 4.5 ECCS Schematic......................................................................................................... 4-17 4.6 Axial Power Distributions at 102% EPU/105% Flow....................................................4-18 4.7 Axial Power Distributions at 102% EPU/ [ ].................................................. 4-19 4.8 Axial Power Distribution at 102% CL TP/1 05% Flow....................................................4-20 6.1 Limiting TLO Recirculation Line Break Upper Plenum Pressure.................................. 6-12 6.2 Limiting TLO Recirculation Line Break Total Break Flow Rate.................................... 6-12 6.3 Limiting TLO Recirculation Line Break Core Inlet Flow Rate....................................... 6-13 6.4 Limiting TLO Recirculation Line Break Core Outlet Flow Rate.................................... 6-13 6.5 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate........... 6-14 6.6 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Suction Flow Rate........ 6-14 6.7 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Exit Flow Rate.............. 6-15 6.8 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate......... 6-15 6.9 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate..... 6-16 6.10 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate........... 6-16 6.11 Limiting TLO Recirculation Line Break ADS Flow Rate............................................... 6-17 6.12 Limiting TLO Recirculation Line Break HPCI Flow Rate.............................................. 6-17 6.13 Limiting TLO Recirculation Line Break LPCS Flow Rate............................................. 6-18 6.14 Limiting TLO Recirculation Line Break Intact Loop LPCI Flow Rate............................ 6-18 6.15 Limiting TLO Recirculation Line Break Broken Loop LPCI Flow Rate......................... 6-19 6.16 Limiting TLO Recirculation Line Break Upper Downcomer Mixture LeveL................... 6-19 6.17 Limiting TLO Recirculation Line Break Lower Downcomer Mixture LeveL................... 6-20 6.18 Limiting TLO Recirculation Line Break Lower Downcomer Liquid Mass...................... 6-20 6.19 Limiting TLO Recirculation Line Break Intact Loop Discharge Line Liquid Mass......... 6-21 6.20 Limiting TLO Recirculation Line Break Upper Plenum Liquid Mass............................. 6-21 6.21 Limiting TLO Recirculation Line Break Lower Plenum Liquid Mass............................. 6-22 6.22 Limiting TLO Recirculation Line Break Hot Channel Inlet Flow Rate........................... 6-22 6.23 Limiting TLO Recirculation Line Break Hot Channel Outlet Flow Rate........................ 6-23 6.24 Limiting TLO Recirculation Line Break Hot Channel Coolant Temperature at the Limiting Node..................................................... ;......................................................... 6-23 6.25 Limiting TLO Recirculation Line Break Hot Channel Quality at the Limiting Node....... 6-24 6.26 Limiting TLO Recirculation Line Break Hot Channel Heat Transfer Coef. at the Limiting Node............................................................................................................... 6-24 6.27 Limiting TLO Recirculation Line Break Cladding Temperatures.................................. 6-25 AREVA NP Inc.

Browns Ferry Units 1,2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page v Figures (Continued) 8.1 Limiting SLO Recirculation Line Break Upper Plenum Pressure................................... 8-7 8.2 Limiting SLO Recirculation Line Break Total Break Flow Rate................. 8-7 8.3 Limiting SLO Recirculation Line Break Core Inlet Flow Rate......................................... 8-8 8.4 Limiting SLO Recirculation Line Break Core Outlet Flow Rate...................................... 8-8 8.5 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate............. 8-9 8.6 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Suction Flow Rate.......... 8-9 8.7 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Exit Flow Rate.............. 8-10 8.8 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate......... 8-10 8.9 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate..... 8-11 8.10 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate........... 8-11 8.11 Limiting SLO Recirculation Line Break ADS Flow Rate............................................... 8-12 8.12 Limiting SLO Recirculation Line Break HPCI Flow Rate.............................................. 8-12 8.13 Limiting SLO Recirculation Line Break LPCS Flow Rate............................................. 8-13 8.14 Limiting SLO Recirculation Line Break Intact Loop LPCI Flow Rate............................ 8-13 8.15 Limiting SLO Recirculation Line Break Broken Loop LPCI Flow Rate......................... 8-14 8.16 Limiting SLO Recirculation Line Break Upper Downcomer Mixture Level................... 8-14 8.17 Limiting SLO Recirculation Line Break Lower Downcomer Mixture Level................... 8-15 8.18 Limiting SLO Recirculation Line Break Lower Downcomer Liquid Mass...................... 8-15 8.19 Limiting SLO Recirculation Line Break Intact Loop Discharge Line Liquid Mass......... 8-16 8.20 Limiting SLO Recirculation Line Break Upper Plenum Liquid Mass............................. 8-16 8.21 Limiting SLO Recirculation Line Break Lower Plenum Liquid Mass............................. 8-17 8.22 Limiting SLO Recirculation Line Break Hot Channel Inlet Flow Rate........................... 8-1.7 8.23 Limiting SLO Recirculation Line Break Hot Channel Outlet Flow Rate........................ 8-18 8.24 Limiting SLO Recirculation Line Break Hot Channel Coolant Temperature at the L im iting N o d e....................................................................................... ....................... 8 -18 8.25 Limiting SLO Recirculation Line Break Hot Channel Quality at the Limiting Node....... 8-19 8.26 Limiting SLO Recirculation Line Break Hot Channel Heat Transfer Coef. at the L im iting N o d e............................................................................................................... 8-19 8.27 Limiting SLO Recirculation Line Break Cladding Temperatures.................................. 8-20 This document contains a total of 154 pages. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Figures (Continued) EMF-2950(NP) Revision 0 Page v 8.1 Limiting SLO Recirculation Line Break Upper Plenum Pressure................................... 8-7 8.2 Limiting SLO Recirculation Line Break Total Break Flow Rate...................................... 8-7 8.3 Limiting SLO Recirculation Line Break Core Inlet Flow Rate......................................... 8-8 8.4 Limiting SLO Recirculation Line Break Core Outlet Flow Rate.................................. ;... 8-8 8.5 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate............. 8-9 8.6 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Suction Flow Rate.......... 8-9 8.7 Limiting SLO Recirculation Line Break lritact Loop Jet Pump Exit Flow Rate.............. 8-10 8.8 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate......... 8-10 8.9 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate..... 8-11 8.10 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate........... 8-11 8.11 Limiting SLO Recirculation Line Break ADS Flow Rate............................................... 8-12 8.12 Limiting SLO Recirculation Line Break HPCI Flow Rate.............................................. 8-12 8.13 Limiting SLO Recirculation Line Break LPCS Flow Rate............................................. 8-13 8.14 Limiting SLO Recirculation Line Break Intact Loop LPCI Flow Rate............................ 8-13 8.15 Limiting SLO Recirculation Line Break Broken Loop LPCI Flow Rate......................... 8-14 8.16 Limiting SLO Recirculation Line Break Upper Downcomer Mixture Level................... 8-14 8.17 Limiting SLO Recirculation Line Break Lower Downcomer Mixture Level................... 8-15 8.18 Limiting SLO Recirculation Line Break Lower Downcomer Liquid Mass...................... 8-15 8.19 Limiting SLO Recirculation Line Break Intact Loop Discharge Line Liquid Mass......... 8-16 8.20 Limiting SLO Recirculation Line Break Upper Plenum Liquid Mass............................. 8-16 8.21 Limiting SLO Recirculation Line Break Lower Plenum Liquid Mass............................. 8-17 8.22 Limiting SLO Recirculation Line Break Hot Channel Inlet Flow Rate........................... 8-17 8.23 Limiting SLO Recirculation Line Break Hot Channel Outlet Flow Rate........................ 8-18 8.24 Limiting SLO Recirculation Line Break Hot Channel Coolant Temperature at the Limiting Node............................................................................................................... 8-18 8.25 Limiting SLO Recirculation Line Break Hot Channel Quality at the Limiting Node....... 8-19 8.26 Limiting SLO Recirculation Line Break Hot Channel Heat Transfer Coef. at the Limiting Node............................................................................................................... 8-19 8.27 Limiting SLO Recirculation Line Break Cladding Temperatures.................................. 8-20 This document contains a total of 154 pages. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page vi Nomenclature ADS ADSVOOS ANS BOL BWR CFR CHF CLTP CMWR DEG DG ECCS EOB EPU FFWTR FHOOS FSAR HPCI automatic depressurization system ADS valve out of service American Nuclear Society beginning of life boiling water reactor Code of Federal Regulations critical heat flux current licensed thermal power (3458 MWt) core average metal-water reaction double-ended guillotine diesel generator emergency core cooling system end of blowdown extended power uprate final feedwater temperature reduction feedwater heaters out of service Final Safety Analysis Report high-pressure coolant injection LOCA LPCI LPCS loss-of-coolant accident low-pressure coolant injection low-pressure core spray MAPLHGR MCPR MELLLA MELLLA+ MSIV MWR maximum average planar linear heat generation rate minimum critical power ratio maximum extended load line limit analysis MELLLA-plus (EPU extension of MELLLA) main steam isolation valve metal-water reaction NRC OLTP PCT RCIC RDIV RWCU Nuclear Regulatory Commission, U.S. original licensed thermal power peak cladding temperature reactor core isolation cooling recirculation discharge isolation valve reactor water cleanup AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis ADS ADSVOOS ANS BOL BWR CFR CHF CLTP CMWR DEG DG ECCS EOB EPU FFWTR FHOOS FSAR HPCI LOCA LPCI LPCS MAPLHGR MCPR MELLLA MELLLA+ MSIV MWR NRC OLTP PCT RCIC RDIV RWCU AREVA NP Inc. Nomenclature automatic depressurization system ADS valve out of service American Nuclear Society beginnIng of life boiling water reactor Code of Federal Regulations critical heat flux current licensed thermal power (3458 MWt) core average metal-water reaction double-ended guillotine diesel generator emergency core cooling system end of blowdown extended power uprate final feedwater temperature reduction feedwater heaters out of service Final Safety Analysis Report high-pressure coolant injection loss-of-coolant accident low-pressure coolant injection low-pressure core spray maximum average planar linear heat generation rate minimum critical power ratio maximum extended load line limit analysis MELLLA-plus (EPU extension of MELLLA) main steam isolation valve metal-water reaction Nuclear Regulatory Commission, U.S. original licensed thermal power peak cladding temperature reactor core isolation cooling recirculation discharge isolation valve reactor water cleanup EMF-2950(NP) Revision 0 Page vi

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page vii Nomenclature (Continued) SF-ADS single failure of an ADS valve SF-BATT single failure of battery (DC) power SF-DGEN single failure of a diesel generator SF-HPCI single failure of the HPCI system SF-LOCA single failure of opposite unit false LOCA signal SF-LPCI single failure of a LPCI valve SLO single-loop operation TLO two-loop operation. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis SF-ADS SF-BATT SF-DGEN SF-HPCI SF-LOCA SF-LPCI SLO TLO AREVA NP Inc. Nomenclature (Continued) single failure of an ADS valve single failure of battery (DC) power single failure of a diesel generator single failure of the HPCI system single failure of opposite unit false LOCA signal single failure of a LPCI valve single-loop operation two-loop operation. EMF-2950(NP) Revision 0 Page vii

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 1-1 1.0 Introduction The results of a loss-of-coolant accident (LOCA) break spectrum analysis for Browns Ferry Units 1, 2, and 3 are documented in this report. The purpose of the break spectrum analysis is to identify the parameters that result in the highest calculated peak cladding temperature (PCT) during a postulated LOCA. The LOCA parameters addressed in this report include the following: Break location Break type (double-ended guillotine (DEG) or split) Break size 0 Limiting emergency core cooling system (ECCS) single failure 0 Axial power shape (top-or mid-peaked) The analyses documented in this report were performed with LOCA Evaluation Models developed by AREVA NP* and approved for reactor licensing analyses by the Nuclear Regulatory Commission, U.S. (NRC). The models and computer codes used by AREVA for LOCA analyses are collectively referred to as the EXEM BWR-2000 Evaluation Model. The EXEM BWR-2000 Evaluation Model and NRC approval are documented in Reference 1. A summary description of the LOCA analysis methodology is provided in Section 4.0. The calculations described in this report were performed in conformance with 10 CFR 50 Appendix K requirements and satisfy the event acceptance criteria identified in 10 CFR 50.46. The break spectrum analyses documented in this report were performed for a core composed entirely of ATRIUMTM-10t fuel at beginning-of-life (BOL) conditions. Calculations assumed an initial core power of 102% of 3952 MWt as per NRC requirements. 3952 MWt corresponds to 120% of the original licensed thermal power (OLTP) and is referred to as the extended power uprate (EPU). In addition to the EPU power level, an additional analysis was made for the limiting single failure and break size for 102% of 3458 MWt. 3458 MWt corresponds to the current licensed thermal power (CLTP), which is 105% OLTP. CLTP analysis is presented to demonstrate that the limiting EPU case is bounding for CLTP operation. Based on similar limiting break sizes of EPU 105% and [ ] and SLO, the limiting break CLTP analysis was chosen as 0.5 ft2. The limiting assembly in the core was assumed to be at a maximum axial planar heat generation rate (MAPLHGR) limit of 12.5 kW/ft. The analyses assumed a generic AREVA NP Inc. is an AREVA and Siemens company. t ATRIUM is a trademark of AREVA NP. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 1.0 Introduction EMF-2950(NP) Revision 0 Page 1-1 The results of a loss-of-coolant accident (LOCA) break spectrum analysis for Browns Ferry Units 1, 2, and 3 are documented in this report. The purpose of the break spectrum analysis is to identify the parameters that result in the highest calculated peak cladding temperature (PCT) during a postulated LOCA. The LOCA parameters addressed in this report include the following: Break location Break type (double-ended guillotine (OEG) or split) Break size Limiting emergency core cooling system (ECCS) single failure Axial power shape (top-or mid-peaked) The analyses documented in this report were performed with LOCA Evaluation Models developed by AREVA NP* and approved for reactor licensing analyses by the Nuclear Regulatory Commission, U.S. (NRC). The models and computer codes used by AREVA for LOCA analyses are collectively referred to as the EXEM BWR-2000 Evaluation Model. The EXEM BWR-2000 Evaluation Model and NRC approval are documented in Reference 1. A summary description of the LOCA analysis methodology is provided in Section 4.0. The calculations described in this report were performed in conformance with 10 CFR 50 Appendix K requirements and satisfy the event acceptance criteria identified in 10 CFR 50.46. The break spectrum analyses documented in this report were performed for a core composed entirely of ATRIUMTM-10t fuel at beginning-of-life (BOL) conditions. Calculations assumed an initial core power of 102% of 3952 MWt as per NRC requirements. 3952 MWt corresponds to 120% of the original licensed thermal power (OL TP) and is referred to as the extended power uprate (EPU). In addition to the EPU power level, an additional analysis was made for the limiting single failure and break size for 102% of 3458 MWt. 3458 MWt corresponds to the current licensed thermal power (CL TP), which is 105% OL TP. CL TP analysis is presented to demonstrate that the limiting EPU case is bounding for CL TP operation. Based on similar limiting break sizes of EPU 105% and [ ] and SLO, the limiting break CL TP analysis was chosen as 0.5 ff. The limiting assembly in the core was assumed to be at a maximum axial planar heat generation rate (MAPLHGR) limit of 12.5 kW/ft. The analyses assumed a generic t AREVA NP Inc. is an AREVA and Siemens company. ATRIUM is a trademark of AREVA NP. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 1-2 ATRIUM-10 neutronic design. Other initial conditions used in the analyses are described in Section 4.0. This report identifies the limiting LOCA break characteristics (location, type, size, single failure, and axial power shape) that will be used in future analyses to determine the MAPLHGR limit versus exposure for ATRIUM-10 fuel contained in Browns Ferry Units 1, 2, and 3. Even though the limiting break will not change with exposure or ATRIUM-10 nuclear fuel design, the value of PCT calculated for any given set of break characteristics is dependent on exposure and local power peaking. Therefore, heatup analyses are performed to determine the PCT versus exposure for each ATRIUM-10 nuclear design in the core. The heatup analyses are performed each cycle using the limiting boundary conditions determined in the break spectrum analysis. The maximum PCT versus exposure from the heatup analyses are documented in the MAPLHGR report. All analyses were performed assuming automatic depressurization system (ADS) valves in-service. This report does not support ADS valve out-of-service (ADSVOOS) operation. [ ] Future EPU maximum extended load line limit analysis (MELLLA+) licensing and operation is supported via analyses [ ] The operating domain of the power/flow map of Reference 6 (which includes MELLLA+ and bounds MELLLA) is applicable for the ATRIUM-10. This report also presents results for single-loop operation (SLO). AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 1-2 'ATRIUM-10 neutronic design. Other initial conditions used in the analyses are described in Section 4.0. This report identifies the limiting LOCA break characteristics (location, type, size, single failure, and axial power shape) that will be used in future analyses to determine the MAPLHGR limit versus exposure for ATRIUM-10 fuel contained in Browns Ferry Units 1, 2, and 3. Even though the limiting break will not change with exposure or ATRIUM-10 nuclear fuel design, the value of PCT calculated for any given set of break characteristics is dependent on exposure and local power peaking. Therefore, heatup analyses are performed to determine the PCT versus exposure for each ATRIUM-10 nuclear design in the core. The heatup analyses are performed each cycle using the limiting boundary conditions determined in the break spectrum analysis. The maximum PCT versus exposure from the heatup analyses are documented in the MAPLHGR report. All analyses were performed assuming automatic depressurization system (ADS) valves in-service. This report does not support ADS valve out-of-service (ADSVOOS) operation. [ ] Future EPU maximum extended load line limit analysis (MELLLA+) licensing and operation is supported via analyses [ ] The operating domain of the power/flow map of Reference 6 (which includes MELLLA+ and bounds MELLLA) is applicable for the ATRIUM-10. This report also presents results for single-loop operation (SLO). AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 2-1 2.0 Summary of Results Based on analyses presented in this report, the limiting break characteristics are identified below. Limiting LOCA Break Characteristics Location recirculation discharge pipe Type / size split / 0.5 ft2 Single failure battery (DC) power Axial power shape mid-peaked Reactor operation [ I Initial state 102% EPU / 105% rated flow A more detailed discussion of results is provided in Sections 6.0 - 8.0. ] The break characteristics identified in this report can be used in subsequent fuel type specific LOCA hot channel and heatup analyses to determine the MAPLHGR limit appropriate for the ATRIUM-1 0 fuel type. The SLO LOCA analyses support operation with an ATRIUM-10 MAPLHGR multiplier of 0.85 applied to the normal two-loop operation MAPLHGR limit. All analyses support operation with six ADS valves. No ADS valves are assumed out-of-service. A ] All analyses were performed assuming nominal feedwater temperature. [ AREVA NP Inc. [ Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 2.0 Summary of Results EMF-2950(NP) Revision 0 Page 2-1 Based on analyses presented in this report, the limiting break characteristics are identified below. Limiting LOCA Break Characteristics Location recirculation discharge pipe Type I size split I 0.5 fe Single failure battery (DC) power Axial power shape mid-peaked Reactor operation [ ] Initial state 102% EPU I 105% rated flow A more detailed discussion of results is provided in Sections 6.0 - 8.0. ] The break characteristics identified in this report can be used in subsequent fuel typ~ specific LOCA hot channel and heatup analyses to determine the MAPLHGR limit appropriate for the ATRIUM-10 fuel type. The SLO LOCA analyses support operation with an ATRIUM-10 MAPLHGR multiplier of 0.85 applied to the normal two-loop operation MAPLHGR limit. All analyses support operation with six ADS valves. No ADS valves are assumed out-of-service. [ ] All analyses were performed assuming nominal feedwater temperature. [ AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 2-2 ] The conclusions of this report are applicable for operation with six ADS, [ ], MELLLA+, FHOOS, FFWTR, and SLO. While the fuel rod temperatures in the limiting plane of the hot channel during a LOCA are dependent on exposure, the factors that determine the limiting break characteristics are primarily associated with the reactor system and are not dependent on fuel-exposure characteristics. Fuel parameters that are dependent on exposure (e.g., stored energy, local peaking) have an insignificant effect on the reactor system response during a LOCA. The limiting break characteristics determined using BOL fuel conditions are applicable for exposed fuel. Fuel exposure effects are addressed in heatup analyses performed to determine or verify MAPLHGR limits versus exposure for each ATRIUM-10 fuel design. The break spectrum analysis was performed using the NRC-approved AREVA EXEM BWR-2000 LOCA methodology. All SER restrictions and ranges of applicability for the EXEM BWR-2000 methodology were reviewed prior to final documentation of the LOCA analysis to ensure compliance with NRC requirements and methodology limitations. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis operation with six ADS, [ FFWTR, and SLO. EMF-2950(NP) Revision 0 Page 2-2 ] The conclusions of this report are applicable for ], MELLLA+, FHOOS, While the fuel rod temperatures in the limiting plane of the hot channel during a LOCA are dependent on exposure, the factors that determine the limiting break characteristics are primarily associated with the reactor system and are not dependent on fuel-exposure characteristics. Fuel parameters that are dependent on exposure (e.g., stored energy, local peaking) have an insignificant effect on the reactor system response during a LOCA. The limiting break characteristics determined using BOL fuel conditions are applicable for exposed fuel. Fuel exposure effects are addressed in heatup analyses performed to determine or verify MAPLHGR limits versus exposure for each ATRIUM-10 fuel design. The break spectrum analysis was performed using the NRC-approved AREVA EXEM BWR-2000 LOCA methodology. All SER restrictions and ranges of applicability for the EXEM BWR-2000 methodology were reviewed prior to final documentation of the LOCA analysis to ensure compliance with NRC requirements and methodology limitations. AREVA NP Inc.

Browns Ferry Units 1,2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 3-1 3.0 LOCA Description 3.1 Accident Description The LOCA is described in the Code of Federal Regulations 10 CFR 50.46 as a hypothetical accident that results in a loss of reactor coolant from breaks in reactor coolant pressure boundary piping up to and including a break equivalent in size to a double-ended rupture of the largest pipe in the reactor coolant system. There is not a specifically identified cause that results in the pipe break. However, for the purpose of identifying a design basis accident, the pipe break is postulated to occur inside the primary containment before the first isolation valve. For a BWR, a LOCA may occur over a wide spectrum of break locations and sizes. Responses to the break vary significantly over the break spectrum. The largest possible break is a double-ended rupture of a recirculation pipe; however, this is not necessarily the most severe challenge to the emergency core cooling system (ECCS). A double-ended rupture of a main steam line causes the most rapid primary system depressurization, but because of other phenomena, steam line breaks are seldom limiting with respect to the criteria of 10 CFR 50.46. Special analysis considerations are required when the break is postulated to occur in a pipe that is used as the injection path for an ECCS (e.g. core spray line). Although these breaks are relatively small, their existence disables the function of an ECCS. In addition to break location dependence, different break sizes in the same pipe produce quite different event responses, and the largest break area is not necessarily the most severe challenge to the event acceptance criteria. Because of these complexities, an analysis covering the full range of break sizes and locations is required. Regardless of the initiating break characteristics, the event response is conveniently separated into three phases: the blowdown phase, the refill phase, and the reflood phase. The relative duration of each phase is strongly dependent upon the break size and location. The last two phases are often combined and will be discussed together in this report. During the blowdown phase of a LOCA, there is a net loss of coolant inventory, an increase in fuel cladding temperature due to core flow degradation, and for the larger breaks, the core becomes fully or partially uncovered. There is a rapid decrease in pressure during the blowdown phase. During the early phase of the depressurization, the exiting coolant provides core cooling. Low-pressure core spray (LPCS) also provides some heat removal. The blowdown phase is defined to end when LPCS reaches rated flow. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 3.0 LOeA Description 3.1 Accident Description EMF-2950(NP) Revision 0 Page 3-1 The LOCA is described in the Code of Federal Regulations 10 CFR 50.46 as a hypothetical accident that results in a loss of reactor coolant from breaks in reactor coolant pressure boundary piping up to and including a break equivalent in size to a double-ended rupture of the largest pipe in the reactor coolant system. There is not a specifically identified cause that results in the pipe break. However, for the purpose of identifying a design basis accident, the pipe break is postulated to occur inside the primary containment before the first isolation valve. For a BWR, a LOCA may occur over a wide spectrum of break locations and sizes. Responses to the break vary significantly over the break spectrum. The largest possible break is a double-ended rupture of a recirculation pipe; however, this is not necessarily the most severe challenge to the emergency core cooling system (ECCS). A double-ended rupture of a main steam line causes the most rapid primary system depressurization, but because of other phenomena, steam line breaks are seldom limiting with respect to the criteria of 10 CFR 50.46. Special analysis considerations are required when the break is postulated to occur in a pipe that is used as the injection path for an ECCS (e.g. core spray line). Although these breaks are relatively small, their existence disables the function of an ECCS. In addition to break location dependence, different break sizes in the same pipe produce quite different event responses, and the largest break area is not necessarily the most severe challenge to the event acceptance criteria. Because of these complexities, an analysis covering the full range of break sizes and locations is required. Regardless of the initiating break characteristics, the event response is conveniently separated into three phases: the blowdown phase, the refill phase, and the reflood phase. The relative duration of each phase is strongly dependent upon the break size and location. The last two phases are often combined and will be discussed together in this report. During the blowdown phase of a LOCA, there is a net loss of coolant inventory, an increase in fuel cladding temperature due to core flow degradation, and for the larger breaks, the core becomes fully or partially uncovered. There is a rapid decrease in pressure during the blowdown phase. During the early phase of the depressurization, the exiting coolant provides core cooling. Low-pressure core spray (LPCS) also provides some heat removal. The blowdown phase is defined to end when LPCS reaches rated flow. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 3-2 In the refill phase of a LOCA, the ECCS is functioning and there is a net increase of coolant inventory. During this phase the core sprays provide core cooling and, along with low-pressure and high-pressure coolant injection (LPCI and HPCI), supply liquid to refill the lower portion of the reactor vessel. In general, the core heat transfer to the coolant is less than the fuel decay heat rate and the fuel cladding temperature continues to increase during the refill phase. In the reflood phase, the coolant inventory has increased to the point where the mixture level reenters the core region. During the core reflood phase, cooling is provided above the mixture level by entrained reflood liquid and below the mixture level by pool boiling. Sufficient coolant eventually reaches the core hot node and the fuel cladding temperature decreases. 3.2 Acceptance Criteria A LOCA is a potentially limiting event that may place constraints on fuel design, local power peaking, and in some cases, acceptable core power level. During a LOCA, the normal transfer of heat from the fuel to the coolant is disrupted. As the liquid inventory in the reactor decreases, the decay heat and stored energy of the fuel cause a heatup of the undercooled fuel assembly. In order to limit the amount of heat that can contribute to the heatup of the fuel assembly during a LOCA, an operating limit on the MAPLHGR is applied to each fuel assembly in the core. The Code of Federal Regulations prescribes specific acceptance criteria (10 CFR 50.46) for a LOCA event as well as specific requirements and acceptable features for Evaluation Models (10 CFR 50 Appendix K). The conformance of the EXEM BWR-2000 LOCA Evaluation Models to Appendix K is described in Reference 1. The ECCS must be designed such that the plant response to a LOCA meets the following acceptance criteria specified in 10 CFR 50.46: The calculated maximum fuel element cladding temperature shall not exceed 2200°F. The calculated local oxidation of the cladding shall nowhere exceed 0.17 times the local cladding thickness. The calculated total amount of hydrogen generated from the chemical reaction of the cladding with water or steam shall not exceed 0.01 times the hypothetical amount that would be generated if all of the metal in the cladding cylinders surrounding the fuel, except the cladding surrounding the plenum volume, were to react. Calculated changes in core geometry shall be such that the core remains amenable to cooling. After any calculated successful operation of the ECCS, the calculated core temperature shall be maintained for the extended period of time required by the long-lived radioactivity remaining in the core. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 3-2 In the refill phase of a LOCA, the ECCS is functioning and there is a net increase of coolant inventory. During this phase the core sprays provide core cooling and, along with low-pressure and high-pressure coolant Injection (LPCI and HPCI), supply liquid to refill the lower portion of the reactor vessel. In general, the core heat transfer to the coolant is less than the fuel decay heat rate and the fuel cladding temperature continues to increase during the refill phase. In the reflood phase, the coolant inventory has increased to the point where the mixture level reenters the core region. During the core reflood phase, cooling is provided above the mixture level by entrained reflood liquid and below the mixture level by pool boiling. Sufficient coolant eventually reaches'the core hot node and the fuel cladding temperature decreases. 3.2 Acceptance Criteria A LOCA is a potentially limiting event that may place constraints on fuel design, local power peaking, and in some cases, acceptable core power level. During a LOCA, the normal transfer of heat from the fuel to the coolant is disrupted. As the liquid inventory in the reactor decreases, the decay heat and stored energy of the fuel cause a heatup of the undercooled fuel assembly. In order to limit the amount of heat that can contribute to the heatup of the fuel assembly during a LOCA, an operating limit on the MAPLHGR is applied to each fuel assembly in the core. The Code of Federal Regulations prescribes specific acceptance criteria (10 CFR 50.46) for a LOCA event as well as specific requirements and acceptable features for Evaluation Models (10 CFR 50 Appendix K). The conformance of the EXEM BWR-2000 LOCA Evaluation Models to Appendix K is described in Reference 1. The ECCS must be designed such that the plant response to a LOCA meets the following acceptance criteria specified in 10 CFR 50.46: The calculated maximum fuel element cladding temperature shall not exceed 2200°F. The calculated local oxidation of the cladding shall nowhere exceed 0.17 times the local cladding thickness. The calculated total amount of hydrogen generated from the chemical reaction of the cladding with water or steam shall not exceed 0.01 times the hypothetical amount that would be generated if all of the metal in the cladding cylinders surrounding the fuel, except the cladding surrounding the plenum volume, were to react. Calculated changes in core geometry shall be such that the core remains amenable to cooling. After any calculated successful operation of the ECCS, the calculated core temperature shall be maintained for the extended period of time required by the long-lived radioactivity remaining in the core. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 3-3 These criteria are commonly referred to as the peak cladding temperature (PCT) criterion, the local oxidation criterion, the hydrogen generation criterion, the coolable geometry criterion, and the long-term cooling criterion. A MAPLHGR limit is established for the ATRIUM-10 fuel type to ensure that these criteria are met. LOCA PCT results are provided in Sections 6.0 - 8.0 to determine the limiting LOCA event. LOCA analysis results demonstrating that the PCT, local oxidation, and hydrogen generation criteria are met are provided in the follow-on MAPLHGR report and cycle-specific heatup analyses. Cycle-specific heatup analyses are performed to demonstrate that the MAPLHGR limits versus exposure for the ATRIUM-10 fuel remains applicable for cycle-specific nuclear designs. Compliance with these three criteria ensures that a coolable geometry is maintained. Long-term coolability criterion is discussed in Section 9.0. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 3-3 These criteria are commonly referred to as the peak cladding temperature (PCT) criterion, the local oxidation criterion, the hydrogen generation criterion, the coolable geometry criterion, and the long-term cooling criterion. A MAPLHGR limit is established for the ATRIUM-10 fuel type to ensure that these criteria are met. LOCA PCT results are provided in Sections 6.0 - 8.0 to determine the limiting LOCA event. LOCA analysis results demonstrating that the PCT, local oxidation, and hydrogen generation criteria are met are provided in the follow-on MAPLHGR report and cycle-specific heatup analyses. Cycle-specific heatup analyses are performed to demonstrate that the MAPLHGR limits versus exposure for the ATRIUM-10 fuel remains applicable for cycle-specific nuclear designs. Compliance with these three criteria ensures that a coolable geometry is maintained. Long-term coolability criterion is discussed in Section 9.0. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 4-1 4.0 LOCA Analysis Description The Evaluation Model used for the break spectrum analysis is the EXEM BWR-2000 LOCA analysis methodology described in Reference 1. The EXEM BWR-2000 methodology employs three major computer codes to evaluate the system and fuel response during all phases of a LOCA. These are the RELAX, HUXY, and RODEX2 computer codes. RELAX is used to calculate the system and hot channel response during the blowdown, refill and reflood phases of the LOCA. The HUXY code is used to perform heatup calculations for the entire LOCA, and calculates the PCT and local clad oxidation at the axial plane of interest. RODEX2 is used to determine fuel parameters (such as stored energy) for input to the other LOCA codes. The code interfaces for the LOCA methodology are illustrated in Figure 4.1. A complete analysis for a given break size starts with the specification of fuel parameters using RODEX2 (Reference 4). RODEX2 is used to determine the initial stored energy for both the blowdown analysis (RELAX system and hot channel) and the heatup analysis (HUXY). This is accomplished by ensuring that the initial stored energy in RELAX and HUXY is the same or higher than that calculated by RODEX2 for the power, exposure, and fuel design being considered. 4.1 Blowdown Analysis The RELAX code (Reference 1) is used to calculate the system thermal-hydraulic response during the blowdown phase of the LOCA. For the system blowdown analysis, the core is represented by an average core channel. The reactor core is modeled with heat generation rates determined from reactor kinetics equations with reactivity feedback and with decay heating as required by Appendix K of 10 CFR 50. The reactor vessel nodalization for the system blowdown analysis is shown in Figure 4.2. This nodalization is consistent with that used in the topical report submitted to the NRC (Reference 1). The RELAX analysis is performed from the time of the break initiation through the end of blowdown (EOB). The system blowdown calculation provides the upper and lower plenum transient boundary conditions for the hot channel analysis. Following the system blowdown calculation, another RELAX analysis is performed to analyze the maximum power assembly (hot channel) of the core. The RELAX hot channel calculation is used to calculate hot channel fuel, cladding, and coolant temperatures during the blowdown AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 4.0 LOCA Analysis Description EMF-2950(NP) Revision 0 Page 4-1 The Evaluation Model used for the break spectrum analysis is the EXEM BWR-2000 LOCA analysis methodology described in Reference 1. The EXEM BWR-2000 methodology employs three major computer codes to evaluate the system and fuel response during all phases of a LOCA. These are the RELAX, HUXY, and RODEX2 computer codes. RELAX is used to calculate the system and hot channel response during the blowdown, refill and reflood phases of the LOCA. The HUXY code is used to perform heatup calculations for the entire LOCA, and calculates the PCT and local clad oxidation at the axial plane of interest. RODEX2 is used to determine fuel parameters (such as stored energy) for input to the other LOCA codes. The code interfaces for the LOCA methodology are illustrated in Figure 4.1. A complete analysis for a given break size starts with the specification of fuel parameters using RODEX2 (Reference 4). RODEX2 is used to determine the initial stored energy for both the blowdown analysis (RELAX system and hot channel) and the heatup analysis (HUXY). This is accomplished by ensuring that the initial stored energy in RELAX and HUXY is the same or higher than that calculated by RODEX2 for the power, exposure, and fuel design being considered. 4.1 Blowdown Analysis The RELAX code (Reference 1) is used to calculate the system thermal-hydraulic response during the blowdown phase of the LOCA. For the system blowdown analysis, the core is represented by an average core channel. The reactor core is modeled with heat generation rates determined from reactor kinetics equations with reactivity feedback and with decay heating as required by Appendix K of 10 CFR 50. The reactor vessel nodalization for the system blowdown analysis is shown in Figure 4.2. This nodalization is consistent with that used in the topical report submitted to the NRC (Reference 1). The RELAX analysis is performed from the time of the break initiation through the end of blowdown (EOB). The system blowdown calculation provides the upper and lower plenum transient boundary conditions for the hot channel analysis. Following the system blowdown calculation, another RELAX analysis is performed to analyze the maximum power assembly (hot channel) of the core. The RELAX hot channel calculation is used to calculate hot channel fuel, cladding, and coolant temperatures during the blowdown AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 4-2 phase of the LOCA. The RELAX hot channel nodalization is shown in Figure 4.3 for a top-peaked power shape, and in Figure 4.4 for a mid-peaked axial power shape. The hot channel analysis is performed using the system blowdown results to supply the core power and the system boundary conditions at the core inlet and exit. The results from the RELAX hot channel calculation used as input to the HUXY heatup analysis are heat transfer coefficients and fluid conditions in the hot channel. 4.2 Refill / Reflood Analysis The RELAX code is used to compute the system and hot channel hydraulic response during the refill/reflood phase of the LOCA. The RELAX system and RELAX hot channel analyses continue beyond the end of blowdown to analyze system and hot channel responses during the refill and reflood phases. The refill phase is the period when the lower plenum is filling due to ECCS injection. The reflood phase is when some portions of the core and hot assembly are being cooled with ECCS water entering from the lower plenum. The purpose of the RELAX calculations beyond blowdown is to determine the time when the liquid flow via upward entrainment from the bottom of the core becomes high enough at the hot node in the hot assembly to end the temperature increase of the fuel rod cladding. This event time is called the time of hot node reflood. [ ] The time when the core bypass mixture level rises to the elevation of the hot node in the hot assembly is also determined. RELAX provides a prediction of fluid inventory during the ECCS injection period. Allowing for countercurrent flow through the core and bypass, RELAX determines the refill rate of the lower plenum due to ECCS water and the subsequent reflood times for the core, hot assembly, and the core bypass. The RELAX calculations provide HUXY with the time of hot node reflood and the time when the liquid has risen in the bypass to the height of the axial plane of interest (time of bypass reflood). 4.3 Heatup Analysis The HU(XY code (Reference 2) is used to perform heatup calculations for the entire LOCA transient and provides PCT and local clad oxidation at the axial plane of interest. The heat generated by metal-water reaction (MWR) is included in the HUXY analysis. HUXY is used to calculate the thermal response of each fuel rod in one axial plane of the hot channel assembly. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-2 phase of the LOGA. The RELAX hot channel nodalization is shown in Figure 4.3 for a top-peaked power shape, and in Figure 4.4 for a mid-peaked axial power shape. The hot channel analysis is performed using the system blowdown results to supply the core power and the system boundary conditions at the core inlet and exit. The results from the RELAX hot channel calculation used as input to the HUXY heatup analysis are heat transfer coefficients and fluid conditions in the hot channel. 4.2 Refill / Reflood Analysis The RELAX code is used to compute the system and hot channel hydraulic response during the refill/reflood phase of the LOGA. The RELAX system and RELAX hot channel analyses continue beyond the end of blowdown to analyze system and hot channel responses during the refill and reflood phases. The refill phase is the period when the lower plenum is filling due to EGGS injection. The reflood phase is when some portions of the core and hot assembly are being cooled with EGGS water entering from the lower plenum. The purpose of the RELAX calculations beyond blowdown is to determine the time when the liquid flow via upward entrainment from the bottom of the core becomes high enough at the hot node in the hot assembly to end the temperature increase of the fuel rod cladding. This event time is called the time of hot node reflood. [ ] The time when the core bypass mixture level rises to the elevation of the hot node in the hot assembly is also determined. RELAX provides a prediction of fluid inventory during the EGGS injection period. Allowing for countercurrentflow through the core and bypass, RELAX determines the refill rate of the lower plenum due to EGGS water and the subsequent reflood times for the core, hot assembly, and the core bypass. The RELAX calculations provide HUXY with the time of hot node reflood and the time when the liquid has risen in the bypass to the height of the axial plane of interest (time of bypass reflood). 4.3 Heatup Analysis The HUXY code (Reference 2) is used to perform heatup calculations for the entire LOGA transient and provides PGT and local clad oxidation at the axial plane of interest. The heat generated by metal-water reaction (MWR) is included in the HUXY analysis. HUXY is used to calculate the thermal response of each fuel rod in one axial plane of the hot channel assembly. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 4-3 These calculations consider thermal-mechanical interactions within the fuel rod. The clad swelling and rupture models from NUREG-0630 have been incorporated into HUXY (Reference 3). The HUXY code complies with the 10 CFR 50 Appendix K criteria for LOCA Evaluation Models. HUXY uses the end of blowdown time and the times of core bypass reflood and core reflood at the axial plane of interest from the RELAX analysis. [ ] Throughout the calculations, decay power is determined based on the ANS 1971 decay heat curve plus 20% as described in Reference 1. [ ] used in the HUXY analysis. The principal results of a HUXY heatup analysis are the PCT and the percent local oxidation of the fuel cladding, often called the %MWR. 4.4 Plant Parameters The LOCA break spectrum analysis is performed using the plant parameters presented in Reference 6. Table 4.1 provides a summary of reactor initial conditions used in the break spectrum analysis. Table 4.2 lists selected reactor system parameters. The break spectrum analysis is performed for a full core of ATRIUM-10 fuel. Some of the key ATRIUM-10 fuel parameters used in the break spectrum analysis are summarized in Table 4.3. 4.5 ECCS Parameters The ECCS configuration is shown in Figure 4.5. Tables 4.4 - 4.8 provide the important ECCS characteristics assumed in the analysis. The ECCS is modeled as fill junctions connected to the appropriate reactor locations: LPCS injects into the upper plenum, HPCI injects into the upper downcomer, and LPCI injects into the recirculation lines. The flow through each ECCS valve is determined based on system pressure and valve position. Flow versus pressure for a fully open valve is obtained by linearly interpolating the pump capacity data provided in Tables 4.4 - 4.6. No credit for ECCS flow is assumed until ECCS pumps reach rated speed. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-3 These calculations consider thermal-mechanical interactions within the fuel rod. The clad swelling and rupture models from NUREG-0630 have been incorporated into HUXY (Reference 3). The HUXY code complies with the 10 GFR 50 Appendix K criteria for LOGA Evaluation Models. HUXY uses the end of blowdown time and the times of core bypass reflood and core reflood at the axial plane of interest from the RELAX analysis. [ ] Throughout the calculations, decay power is determined based on the ANS 1971 decay heat curve plus 20% as described in Reference 1. [ ] used in the HUXY analysis. The principal results of a HUXY heatup analysis are the PGT and the percent local oxidation of the fuel cladding, often called the %MWR. 4.4 Plant Parameters The LOGA break spectrum analysis is performed using the plant parameters presented in Reference 6. Table 4.1 provides a summary of reactor initial conditions used in the break spectrum analysis. Table 4.2 lists selected reactor system parameters. The break spectrum analysis is performed for a full core of ATRIUM-10 fuel. Some of the key ATRIUM-10 fuel parameters used in the break spectrum analysis are summarized in Table 4.3. 4.5 ECCS Parameters The EGGS configuration is shown in Figure 4.5. Tables 4.4 - 4.8 provide the important EGGS characteristics assumed in the analysis. The EGGS is modeled as fill junctions connected to the appropriate reactor locations: LPGS injects into the upper plenum, HPGI injects into the upper downcomer, and LPGI injects into the recirculation lines. The flow through each EGGS valve is determined based on system pressure and valve position. Flow versus pressure for a fully open valve is obtained by linearly interpolating the pump capacity data provided in Tables 4.4 - 4.6. No credit for EGGS flow is assumed until EGGS pumps reach rated speed. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-4 The ADS valves are modeled as a junction connecting the reactor steam line to the suppression pool. The flow through the ADS valves is calculated based on pressure and valve flow characteristics. The valve flow characteristics are determined such that the calculated flow is equal to the rated capacity at the reference pressure shown in Table 4.7. All six ADS valves are assumed operable. The analyses do not support ADSVOOS operation. In the AREVA LOCA analysis model, ECCS initiation is assumed to occur when the water level drops to the applicable level setpoint. No credit is assumed for the start of HPCI, LPCS, or LPCI due to high drywell pressure. [ ] The recirculation discharge isolation valve (RDIV) parameters are shown in Table 4.8. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-4 The ADS valves are modeled as a junction connecting the reactor steam line to the suppression pool. The flow through the ADS valves is calculated based on pressure and valve flow characteristics. The valve flow characteristics are determined such that the calculated flow is equal to the rated capacity at the reference pressure shown in Table 4.7. All six ADS valves are assumed operable. The analyses do not support ADSVOOS operation. In the AREVA LOCA analysis model, ECCS initiation is assumed to occur when the water level drops to the applicable level setpoint. No credit is assumed for the start of HPCI, LPCS, or LPCI due to high drywell pressure. [ ] The recirculation discharge isolation valve (RDIV) parameters are shown in Table 4.8. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-5 Table 4.1 Initial Conditions* Reactor power (% of rated) Total core flow (% of rated) Reactor power (MWt) 102 EPU 105 4031 102 EPU 4031 102 CLTP 105 3527 Total core flow (Mlb/hr) 107.6 [ ] 107.6 [] Steam flow rate (Mlb/hr) 16.82 16.82 14.47 Steam dome pressure (psia) 1054 1054 1054 Core inlet enthalpy (Btu/lb) 522.9 [ ] 525.0 ATRIUM-10 hot assembly MAPLHGR (kW/ft) 12.5 12.5 12.5 [ ECCS fluid temperature (°F)* 125 125 125 Axial power shape Fig. 4.6 Fig. 4.7 Fig. 4.8 The AREVA calculated heat balance is adjusted to match the 100% power/1 00% flow values given in the plant parameters document (Reference 6). The model is then rebalanced based on AREVA heat balance calculations to establish these LOCA initial conditions at 102% of rated thermal power. t [I Coolant temperature is determined from suppression pool temperature versus time data. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Table 4.1 Initial Conditions* Reactor power (% of rated) 102 EPU 102 EPU Total core flow (% of rated) 105 [ 1 Reactor power (MWt) 4031 4031 Total core flow (Mlb/hr) 107.6 [ 1 [ Steam flow rate (Mlb/hr) 16.82 16.82 Steam dome pressure (psia) 1054 1054 Core inlet enthalpy (Btu/lb) 522.9 [ 1 ATRIUM-10 hot assembly MAPLHGR (kW/ft) 12.5 12.5 [ ECCS fluid temperature (OF):!: 125 125 Axial power shape Fig. 4.6 Fig. 4.7 EMF-2950(NP) Revision 0 Page 4-5 102 CLTP 105 3527 107.6 ] 14.47 1054 525.0 12.5 ] 125 Fig. 4.8 The AREVA calculated heat balance is adjusted to match the 100% power/100% flow values given in the plant parameters document (Reference 6). The model is then rebalanced based on AREVA heat balance calculations to establish these LOCA initial conditions at 102% of rated thermal power. [ ] t

t:

Coolant temperature is determined from suppression pool temperature versus time data. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 4-6 Table 4.2 Reactor System Parameters Parameter Value Vessel ID (in) 251 Number of fuel assemblies 764 Recirculation suction pipe area (ft2) 3.507 1.0 DEG suction break area (ft2) 7.013 Recirculation discharge pipe area (ft2) 3.507 1.0 DEG discharge break area (ft2) 7.013 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. Table 4.2 Reactor System Parameters Parameter Vessel 10 (in) Number of fuel assemblies Recirculation suction pipe area (ft2) 1.0 OEG suction break area (W) Recirculation discharge pipe area (W) 1.0 OEG discharge break area (W) Value 251 764 3.507 7.013 3.507 7.013 EMF-2950(NP) Revision 0 Page 4-6

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-7 Table 4.3 ATRIUM-10 Fuel Assembly Parameters Parameter Value Fuel rod array 1Ox10 Number of fuel rods per 83 (full-length rods) assembly 8 (part-length rods) Non-fuel rod type Water channel replaces 9 fuel rods Fuel rod OD (in) Active fuel length (in) (including blankets) Water channel outside width (in) Fuel channel thickness (in) 0.3957 149.45 (full-length rods) 90 (part-length rods) 1.378 0.075 (minimum wall) 0.100 (corner) 5.278 Fuel channel internal width (in) AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Table 4.3 ATRIUM-10 Fuel Assembly Parameters AREVA NP Inc. Parameter Fuel rod array Number of fuel rods per assembly Non-fuel rod type Fuel rod 00 (in) Active fuel length (in) (including blankets) Water channel outside width (in) Fuel channel thickness (in) Fuel channel internal width (in) Value 10x10 83 (full-length rods) 8 (part-length rods) Water channel replaces 9 fuel rods 0.3957 149.45 (full-length rods) 90 (part-length rods) 1.378 0.075 (minimum wall) 0.100 (corner) 5.278 EMF-2950(NP) Revision 0 Page 4-7

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-8 Table 4.4 High-Pressure Coolant Injection Parameters Parameter Value Coolant temperature (OF)* 125 Initiating Signals and Setpoints Water levelt L2 (448 in) High drywell pressure (psig) 2.6 Time Delays Time for HPCI pump to reach rated speed and injection valve wide open (sec) 50 Delivered Flow Rate Versus Pressure Vessel to Flow Drywell AP Rate (psid) (gpm) 0 0 150 4500 1120 4500 Coolant temperature is determined from suppression pool temperature versus time data. t Relative to vessel zero. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Table 4.4 High-Pressure Coolant Injection Parameters Parameter Coolant temperature CF)* Water levelt Initiating Signals and Setpoints High drywell pressure (psig) Time Delays Time for HPCI pump to reach rated speed and injection valve wide open (sec) Delivered Flow Rate Versus Pressure Vessel to Drywell ~P (psid) o 150 1120 Value 125 L2 (448 in) 2.6 Flow Rate (gpm) o 4500 4500 50 EMF-2950(NP) Revision 0 Page 4-8 t Coolant temperature is determined from suppression pool temperature versus time data. Relative to vessel zero. AREVA NP Inc..

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-9 Table 4.5 Low-Pressure Coolant Injection Parameters Parameter Value Reactor pressure permissive for opening valves (psia) 350 Coolant temperature (OF)* 125 Initiating Signals and Setpoints Water levelt Li (372.5 in) High drywell pressure (psig) 2.6 Time Delays Time for LPCI pumps to reach rated speed (max) (sec)* 44 LPCI injection valve stroke time (sec) 40 Delivered Flow Rate Versus Pressure Flow Rate Vessel (gpm) to Drywell AP 2 Pumps 4 Pumps (psid) Into Into 1 Loop 2 Loops 0 17,240 34,480 20 16,540 33,080§ 319.5 0 0 Coolant temperature is determined from suppression pool temperature versus time data. t Relative to vessel zero. Includes 13-second delay for diesel generator start. 2-second signal processing delay for water level trip Li is assumed in parallel with diesel generator delay. § Conservative value relative to specified value in Reference 6 (33,240 gpm). Modeling limitations require the more conservative value of either the specified 4 pumps into 2 loops flow or twice the specified 2 pumps into 1 loop flow be used. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate EMF-2950(NP) Revision 0 Page 4-9 LOCA Break Spectrum Analysis t

I:

§ Table 4.5 Low-Pressure Coolant Injection Parameters Parameter Reactor pressure permissive for opening valves (psia) Coolant temperature CF)* Water levelt Initiating Signals and Setpoints High drywell pressure (psig) Time Delays Time for LPCI pumps to reach rated speed (max) (sec):!: LPCI injection valve stroke time (sec) Delivered Flow Rate Versus Pressure Value 350 125 L 1 (372.5 in) 2.6 44 40 Vessel Flow Rate to (gpm) Drywell ~P 2 Pumps 4 Pumps (psid) Into Into 1 Loop 2 Loops 0 17,240 34,480 20 16,540 33,080§ 319.5 0 0 Coolant temperature is determined from suppression pool temperature versus time data. Relative to vessel zero. Includes 13-second delay for diesel generator start. 2-second signal processing delay for water level trip L 1 is assumed in parallel with diesel generator delay. Conservative value relative to specified value in Reference 6 (33,240 gpm). Modeling limitations require the more conservative value of either the specified 4 pumps into 2 loops flow or twice the specified 2 pumps into 1 loop flow be used. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-10 Table 4.6 Low-Pressure Core Spray Parameters Parameter Value Reactor pressure permissive for opening valves (psia) 350 Coolant temperature (OF)* 125 Initiating Signals and Setpoints Water levelt Li (372.5 in) High drywell pressure (psig) 2.6 Time Delays Time for LPCS pumps to reach ADS permissive (max) (sec)t 40 Time for LPCS pumps to reach rated speed (max) (sec)t 43 LPCS injection valve stroke time (sec) 33 Delivered Flow Rate Versus Pressure Vessel Flow Rate to (gpm) Drywell AP 2 Pumps 4 Pumps (psid) Into Into 1 Sparger 2 Spargers 0 6,935 13,870 105 5,435 10,870 289 0 0 Coolant temperature is determined from suppression pool temperature versus time data. t Relative to vessel zero. Includes 13-second delay for diesel generator start. 2-second signal processing delay for water level trip Li is assumed in parallel with diesel generator delay. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate EMF-2950(NP) Revision 0 Page 4-10 LOCA Break Spectrum Analysis t

j:

Table 4.6 Low-Pressure Core Spray Parameters Parameter Reactor pressure permissive for opening valves (psia) Coolant temperature CF)* Water levelt Initiating Signals and Setpoints High drywell pressure (psig) Time Delays Time for LPCS pumps to reach ADS permissive (max) (seer!: Time for LPCS pumps to reach rated speed (max) (sec):!: LPCS injection valve stroke time (sec) Delivered Flow Rate Versus Pressure Value 350 125 L 1 (372.5 in) 2.6 40 43 33 Vessel to Drywell ilP (psid) Flow Rate (gpm) o 105 289 2 Pumps Into 1 Sparger 6,935 5,435 o 4 Pumps Into 2 Spargers 13,870 10,870 o Coolant temperature is determined from suppression pool temperature versus time data. Relative to vessel zero. Includes 13-second delay for diesel generator start. 2-second signal processing delay for water level trip L 1 is assumed in parallel with diesel generator delay.. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-11 Table 4.7 Automatic Depressurization System Parameters Parameter Value Number of valves installed 6 Number of valves available 6 Minimum flow capacity of available valves (Mlbm/hr at psig) 4.8 at 1125 Initiating Signals and Setpoints Water level* Li (372.5 in) LPCS ready permissivet Li + 40 sec (max) Time Delays Delay time (from ADS timer permissive to time valves are open) (sec) 120 t Relative to vessel zero. ADS timer initiation occurs after level trip Li is met and LPCS pumps reach the ADS ready permissive (see Table 4.6). Credit is conservatively not taken for the RHR pump ready permissive that would occur 8 seconds earlier. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Table 4.7 Automatic Depressurization System Parameters Parameter Number of valves installed Number of valves available Minimum flow capacity of available valves (Mlbm/hr at psig) Water level* Initiating Signals and Setpoints LPCS ready permissive t Time Delays Delay time (from ADS timer permissive to time valves are open) (sec) Relative to vessel zero. Value 6 6 4.8 at 1125 L 1 (372.5 in) L 1 + 40 sec (max) 120 EMF-2950(NP) Revision 0 Page 4-11 t ADS timer initiation occurs after level trip L 1 is met and LPCS pumps reach the ADS ready permissive (see Table 4.6). Credit is conservatively not taken for the RHR pump ready permissive that would occur 8 seconds earlier. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-12 Table 4.8 Recirculation Discharge Isolation Valve Parameters Parameter Value Reactor pressure permissive for closing valves -- analytical (psia) 215 RDIV stroke time after pressure permissive (sec) 36 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Table 4.8 Recirculation Discharge Isolation Valve Parameters AREVA NP Inc. Parameter Reactor pressure permissive for closing valves -, analytical (psia) RDIV stroke time after pressure permissive (sec) Value 215 36 EMF-2950(NP) Revision 0 Page 4-12

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-13 Neutronic Data (CASMO-4, MICROBURN-B2)

Gap, Reflood lime Hot Node Gap Coefficient, for Canister Coolant Fission Gas

& Hot Node Conditions Heatup Analysis (HUXY) Peak Cladding Temperature, Metal Water Reaction Figure 4.1 Flow Diagram for EXEM BWR-2000 ECCS Evaluation Model AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-13 I Fuel Data 11----------1:~ 1"iI~1----------l1 Plant Data I Neutronic Data (CASM0-4, MICROBURN-B2) System Analysis (RELAX) L...r ___ Core ~P, __ ~RPF,APF Fuel Parameters I--Fuel Stored (RODEX2) Energy

Gap, Gap Coefficient, Fission Gas AREVA NP Inc.

I Plenum Boundary ,Ir Con:ions Hot Assembly Analysis (RELAX) 1 I Reflood Time Hot Node for Canister Coolant & Hot Node Conditions ~ ~ Heatup Analysis (HUXY) I Peak Oadding Temperature, Metal Water Reaction

• Figure 4.1 Flow Diagram for EXEM BWR-2000 ECCS Evaluation Model SS CoreT/H (XCOBRA)

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-14 [ I Figure 4.2 RELAX System Blowdown Model AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ Figure 4.2 RELAX System Blowdown Model AREVA NP Inc. EMF-2950(NP) Revision 0 Page 4-14 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-15 I Figure 4.3 RELAX Hot Channel Blowdown Model Top-Peaked Axial AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Figure 4.3 RELAX Hot Channel Blowdown Model Top-Peaked Axial EMF-2950(NP) Revision 0 Page 4-15 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-16 I Figure 4.4 RELAX Hot Channel Blowdown Model Mid-Peaked Axial AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Figure 4.4 RELAX Hot Channel Blowdown Model Mid-Peaked Axial EMF-2950(NP) Revision 0 Page 4-16 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-17 HPCI Turbine LPCI Injection Valve Discharge Shutoff Valve Recirculation Pump Recirculation Pump "- Closed Valve >K Open Valve Figure 4.5 ECCS Schematic AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis LPCI Injection Valve Discharge Shutoff Valve Break Recirculation Pump AREVA NP Inc. Cross Tie (not credited) Feedwater Spargers Core Spray Spargers Core LPCS Injection Valve Recirculation Pump Figure 4.5 ECCS Schematic LPCI Injection Valve Discharge Shutoff Valve EMF-2950(NP) Revision 0 Page 4-17 HPCI Turbine ~ Closed Valve C><J Open Valve

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-18 [ I Figure 4.6 Axial Power Distributions at 102% EPU/105% Flow AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Figure 4.6 Axial Power Distributions at 102% EPUl105% Flow EMF-2950(NP) Revision 0 Page 4-18 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-19 [ I Figure 4.7 Axial Power Distributions at 102% EPU/[ ] AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ Figure 4.7 Axial Power Distributions at 102% EPu/ [ ] AREVA NP Inc. EMF-2950(NP) Revision 0 Page 4-19 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 4-20 [ I Figure 4.8 Axial Power Distribution at 102% CLTP/105% Flow AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Figure 4.8 Axial Power Distribution at 102% CL TP/1 05% Flow EMF-2950(NP) Revision 0 Page 4-20 ]

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 5-1 5.0 Break Spectrum Analysis Description The objective of this LOCA analyses is to ensure that the limiting break location, break type, break size, and ECCS single failure are identified. The LOCA response scenario varies considerably over the spectrum of break locations. Potential break locations have been separated into two groups: recirculation line breaks and non-recirculation line breaks. The basis for the break locations and potentially limiting single failures analyzed in this report is described in the following sections. 5.1 Limiting Single Failure Regulatory requirements specify that the LOCA analysis be performed assuming that all offsite power supplies are lost instantaneously and that only safety grade systems and components are available. In addition, regulatory requirements also specify that the most limiting single failure of ECCS equipment must be assumed in the LOCA analysis. The term "most limiting" refers to the ECCS equipment failure that produces the greatest challenge to event acceptance criteria. The limiting single failure can be a common power supply, an injection valve, a system pump, or system initiation logic. The equipment identified in the FSAR (Reference 7) that may produce a limiting single failure (SF) is shown below: Battery power (BATT) 0 Opposite unit false LOCA signal (LOCA) 0 Low-pressure coolant injection valve (LPCI) 0 Diesel generator (DGEN) High-pressure coolant injection system (HPCI) The single failures and the available ECCS for each failure assumed in this analysis are summarized in Table 5.1. Other potential failures are not specifically considered because they all result in as much or more ECCS capacity. Table 5.1 clearly demonstrates that a single failure of the battery results in the least amount of ECCS capacity and is therefore limiting. It should be noted that SF-LOCA and SF-DGEN are identical. 5.2 Recirculation Line Breaks The response during a recirculation line LOCA is dependent on break size. ADS operation is an important emergency system for small breaks. The ADS assists in depressurizing the reactor system, and thereby reduces the time required to reach rated LPCS and LPCI flow. For large breaks, rated LPCS and LPCI flow is generally reached before or shortly after the time when the AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 5.0 Break Spectrum Analysis Description EMF-2950(NP) Revision 0 Page 5-1 The objective of this LOCA analyses is to ensure that the limiting break location, break type, break size, and ECCS single failure are identified. The LOCA response scenario varies considerably over the spectrum of break locations. Potential break locations have been separated into two groups: recirculation line breaks and non-recirculation line breaks. The basis for the break locations and potentially limiting single failures analyzed in this report is described in the following sections. 5.1 Limiting Single Failure Regulatory requirements specify that the LOCA analysis be performed assuming that all offsite power supplies are lost instantaneously and that only safety grade systems and components are available. In addition, regulatory requirements also specify that the most limiting single failure of ECCS equipment must be assumed in the LOCA analysis. The term "most limiting" refers to the ECCS equipment failure that produces the greatest challenge to event acceptance criteria. The limiting single failure can be a common power supply, an injection valve, a system pump, or system initiation logic. The equipment identified in the FSAR (Reference 7) that may produce a limiting single failure (SF) is shown below: Battery power (BATT) Opposite unit false LOCA signal (LOCA) Low-pressure coolant injection valve (LPCI) Diesel generator (DGEN) High-pressure coolant injection system (HPCI) The single failures and the available ECCS for each failure assumed in this analysis are summarized in Table 5.1. Other potential failures are not specifically considered because they all result in as much or more ECCS capacity. Table 5.1 clearly demonstrates that a single failure of the battery results in the least amount of ECCS capacity and is therefore limiting. It should be noted that SF-LOCA and SF-DGEN are identical. 5.2 Recirculation Line Breaks The response during a recirculation line LOCA is dependent on break size. ADS operation is an important emergency system for small breaks. The ADS assists in depressurizing the reactor system, and thereby reduces the time required to reach rated LPCS and LPCI flow. For large breaks, rated LPCS and LPCI flow is generally reached before or shortly after the time when the AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 5-2 ADS valves open so the ADS system is not required to mitigate the LOCA. The analyses are performed with six ADS valves in-service. This does not support operation with ADSVOOS. Large recirculation line break analyses are performed for breaks in both the discharge and suction side of the recirculation pump. It is generally expected that the pump suction side break will be more severe due to the more rapid blowdown. The two largest flow resistances in the recirculation piping are the recirculation pump and the jet pump nozzle. For breaks in the discharge piping, there is a major flow resistance in both flow paths to the break. For breaks in the suction piping, there is only one major flow resistance due to the recirculation pump between the break and reactor vessel. As a result, suction side breaks allow the coolant to exit more rapidly and generally result in more severe events than discharge side breaks (if ECCS capacity is equal). Both suction and discharge recirculation pipe breaks are considered in the break spectrum analysis. Two break types (geometries) are considered for the recirculation line break. The two types are the double-ended guillotine (DEG) break and the split break. For a DEG break, the piping is assumed to be completely severed resulting in two independent flow paths to the containment. The DEG break is modeled by setting the break area (at both ends of the pipe) equal to the full pipe cross-sectional area and varying the discharge coefficient between 1.0 and 0.4. The range of discharge coefficients is used to cover uncertainty in the actual geometry at the break. Discharge coefficients below 0.4 are unrealistic and not considered in the EXEM BWR-2000 methodology. The most limiting DEG break is determined by varying the discharge coefficient. A split type break is assumed to be a longitudinal opening or hole in the piping that results in a single break flow path to the containment. Appendix K of 10 CFR 50 defines the cross-sectional area of the piping as the maximum split break area required for analysis. The rate of reactor vessel depressurization is slower for intermediate and small breaks (break area < 1.0 ft2) compared to large break LOCAs. The HPCI and ADS will assist in reducing the reactor vessel pressure to the pressure where the LPCI and LPCS flows start. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 5-2 ADS valves open so the ADS system is not required to mitigate the LOCA. The analyses are performed with six ADS valves in-service. This does not support operation with ADSVOOS. Large recirculation line break analyses are performed for breaks in both the discharge and suction side of the recirculation pump. It is generally expected that the pump suction side break will be more severe due to the more rapid blowdown. The two largest flow resistances in the recirculation piping are the recirculation pump and the jet pump nozzle. For breaks in the discharge piping, there is a major flow resistance in both flow paths to the break. For breaks in the suction piping, there is only one major flow resistance due to the recirculation pump between the break and reactor vessel. As a result, suction side breaks allow the coolant to exit more rapidly and generally result in more severe events than discharge side breaks (if ECCS capacity is equal). Both suction and discharge recirculation pipe breaks are considered in the break spectrum analysis. Two break types (geometries) are considered for the recirculation line break. The two types are the double-ended guillotine (DEG) break and the split break. For a DEG break, the piping is assumed to be completely severed resulting in two independent flow paths to the containment. The DEG break is modeled by setting the break area (at both ends of the pipe) equal to the full pipe cross-sectional area and varying the discharge coefficient between 1.0 and 0.4. The range of discharge coefficients is used to cover uncertainty in the actual geometry at the break. Discharge coefficients below 0.4 are unrealistic and not considered in the EXEM BWR-2000 methodology. The most limiting DEG break is determined by varying the discharge coefficient. A split type break is assumed to be a longitudinal opening or hole in the piping that results in a single break flow path to the containment. Appendix K of 10 CFR 50 defines the cross-sectional area of the piping as the maximum split break area required for analysis. The rate of reactor vessel depressurization is slower for intermediate and small breaks (break area ~ 1.0 ff) compared to large break LOCAs. The HPCI and ADS will assist in reducing the reactor vessel pressure to the pressure where the LPCI and LPCS flows start. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 5-3 The break spectrum analyses in the intermediate and small break region consider break sizes between 1.0 ft2 and 0.05 ft2. Break sizes and single failures are analyzed for both suction and discharge recirculation line breaks. Section 6.0 provides a description and result summary for large, intermediate, and small breaks in the recirculation line. 5.3 Non-Recirculation Line Breaks In addition to breaks in the recirculation line, breaks in other reactor coolant system piping must be considered in the LOCA break spectrum analysis. Although the recirculation line large break results in the largest coolant inventory loss, it does not necessarily result in the most severe challenge to event acceptance criteria. The double-ended rupture of a main steam line is expected to result in the fastest depressurization of the reactor vessel. Special consideration is required when the postulated break occurs in ECCS piping. Although ECCS piping breaks are small relative to a recirculation pipe DEG break, this break disables an ECCS system and therefore, increases the postulated break severity. Table 5.2 summarizes the available ECCS components of the potentially limiting single failures identified in Table 5.1. The following sections address potential LOCAs due to breaks in non-recirculation line piping. Non-recirculation line breaks outside of the containment are inherently less challenging to fuel limits than breaks inside the containment. For breaks outside containment, isolation or check valve closure will terminate break flow prior to the loss of significant liquid inventory and the core will remain covered. If high-pressure coolant inventory makeup cannot be reestablished, ADS actuation may become necessary. [ ] Although analyses of breaks outside containment may be required to address non-fuel related regulatory requirements, these breaks are not limiting relative to fuel acceptance criteria such as PCT. 5.3.1 HPCI Line Breaks AREVA NP Inc. [ Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 5-3 The break spectrum analyses in the intermediate and small break region consider break sizes between 1.0 fe and 0.05 fe. Break sizes and single failures are analyzed for both suction and discharge recirculation line breaks. Section 6.0 provides a description and result summary for large, intermediate, and small breaks in the recirculation line. 5.3 Non-Recirculation Line Breaks In addition to breaks in the recirculation line, breaks in other reactor coolant system piping must be considered in the LOCA break spectrum analysis. Although the recirculation line large break results in the largest coolant inventory loss, it does not necessarily result in the most severe challenge to event acceptance criteria. The double-ended rupture of a main steam line is expected to result in the fastest depressurization of the reactor vessel. Special consideration is required when the postulated break occurs in ECCS piping. Although ECCS piping breaks are small relative to a recirculation pipe DEG break, this break disables an ECCS system and therefore, increases the postulated break severity. Table 5.2 summarizes the available ECCS components of the potentially limiting single failures identified in Table 5.1. The following sections address potential LOCAs due to breaks in non-recirculation line piping. Non-recirculation line breaks outside of the containment are inherently less challenging to fuel limits than breaks inside the containment. For breaks outside containment, isolation or check valve closure will terminate break flow prior to the loss of significant liquid inventory and the core will remain covered. If high-pressure coolant inventory makeup cannot be reestablished, ADS actuation may become necessary. [ ] Although analyses of breaks outside containment may be required to address non-fuel related regulatory requirements, these breaks are not limiting relative to fuel acceptance criteria such as PCT. 5.3.1 HPCI Line Breaks AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 5-4 I The HPCI injection line is connected to the feedwater line outside of the containment. [ ] 5.3.2 LPCS Line Breaks A break in the LPCS line is expected to have many characteristics similar to [ ] However, some characteristics of the LPCS line break are unique and are not addressed in other LOCA analyses. Two important differences from other LOCA analyses are that the break flow will exit from the region inside the core shroud and the break will disable one LPCS system. The LPCS line break is assumed to occur just outside the reactor vessel. [ I 5.3.3 LPCI Line Breaks The LPCI injection lines are connected to the larger recirculation discharge lines. [ I 5.3.4 Main Steam Line Breaks A steam line break inside containment is assumed to occur between the reactor vessel and the inboard main steam line isolation valve (MSIV) upstream of the flow limiters. The break results in high steam flow out of the broken line and into the containment. Prior to MSIV closure, a steam line break also results in high steam flow in the intact steam lines as they feed the break via the steam line manifold. A steam line break inside containment results in a rapid depressurization of the reactor vessel. Initially the break flow will be high quality steam; however, the rapid depressurization produces a water level swell that results in liquid discharge AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis ] EMF-2950(NP) Revision 0 Page 5-4 The HPCI injection line is connected to the feedwater line outside of the containment. [ ] 5.3.2 LPCS Line Breaks A break in the LPCS line is expected to have many characteristics similar to [ ] However, some characteristics of the LPCS line break are unique and are not addressed in other LOCA analyses. Two important differences from other LOCA analyses are that the break flow will exit from the region inside the core shroud and the break will disable one LPCS system. The LPCS line break is assumed to occur just outside the reactor vessel. [ ] 5.3.3 LPCI Line Breaks The LPCI injection lines are connected to the larger recirculation discharge lines. [ ] 5.3.4 Main Steam Line Breaks A steam line break inside containment is assumed to occur between the reactor vessel and the inboard main steam line isolation valve (MSIV) upstream of the flow limiters. The break results in high steam flow out of the broken line and into the containment. Prior to MSIV closure, a steam line break also results in high steam flow in the intact steam lines as they feed the break via the steam line manifold. A steam line break inside containment results in a rapid depressurization of the reactor vessel. Initially the break flow will be high quality steam; however, the rapid depressurization produces a water level swell that results in liquid discharge AREVA NP Inc.

Browns Ferry Units 1,2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 5-5 at the break. For steam line breaks, the largest break size is most limiting because it results in the most level swell and liquid loss out of the break. 5.3.5 Feedwater Line Breaks [ 5.3.6 RCIC Line Breaks The RCIC discharges to the feedwater line, [ The steam supply to the RCIC turbine comes from the main steam line from the reactor vessel; [ ] AREVA NP Inc. [ [ Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 5-5 at the break. For steam line breaks, the largest break size is most limiting because it results in the most level swell and liquid loss out of the break. ] 5.3.5 Feedwater Line Breaks ] 5.3.6 RCIC Line Breaks The RCIC discharges to the feedwater line, [ ] The steam supply to the RCIC turbine comes from the main steam line from the reactor vessel; [ ] AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 5-6 5.3.7 RWCU Line Breaks The RWCU extraction line is connected to a recirculation suction line with an additional connection to the vessel bottom head. [ A break in the RWCU return line is less limiting than a feedwater line break. The RWCU return line is connected to the feedwater line; [ ] 5.3.8 Instrument Line Breaks [ I AREVA NP Inc. [ Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 5.3.7 RWCU Line Breaks EMF-2950(NP) Revision 0 Page 5-6 The RWCU extraction line is connected to a recirculation suction line with an additional connection to the vessel bottom head. [ ] A break in the RWCU return line is less limiting than a feedwater line break. The RWCU return line is connected to the feedwater line; [ ] 5.3.8 Instrument Line Breaks ] AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 5-7 Table 5.1 ECCS Single Failure Systems Assumed Remaining Failure Recirculation* Recirculation Suction Break Discharge Break Battery ADS,t 1 LPCS,l 2 LPCI§ ADS, 1 LPCS Opposite unit false LOCA signal ADS, HPCI, 1 LPCS, 2 LPCI ADS, HPCI, 1 LPCS LPCI injection valve ADS, HPCI, 2 LPCS, 2 LPCI ADS, HPCI, 2 LPCS Diesel generator ADS, HPCI, 1 LPCS, 2 LPCI ADS, HPCI, 1 LPCS HPCI ADS, 2 LPCS, 4 LPCI** ADS, 2 LPCS, 2 LPCI Systems remaining, as identified in this table for recirculation suction line breaks, are applicable to other non-ECCS line breaks. For a LOCA from an ECCS line break, the systems remaining are those listed for recirculation suction breaks, less the ECCS in which the break is assumed. t Analyses are performed with all six ADS valves in-service. Each LPCS means operation of two core spray pumps in a system. It is assumed that both pumps in a system must operate to take credit for core spray cooling or inventory makeup in that loop. § Two LPCI pumps into one loop. Four LPCI pumps into two loops, two per loop. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOGA Break Spectrum Analysis Assumed Failure Battery Opposite unit false LOCA signal LPCI injection valve Diesel generator HPCI Table 5.1 ECCS Single Failure Systems Remaining Recirculation* Suction Break ADS,t 1 LPCS,:J: 2 LPCI§ ADS, HPCI, 1 LPCS, 2 LPCI ADS, HPCI, 2 LPCS, 2 LPCI ADS, HPCI, 1 LPCS, 2 LPCI ADS, 2 LPCS, 4 LPCI** Recirculation EMF-2950(NP) Revision 0 Page 5-7 Discharge Break ADS,1 LPCS ADS, HPCI, 1 LPCS ADS, HPCI, 2 LPCS ADS, HPCI, 1 LPCS ADS,2 LPCS, 2 LPCI Systems remaining, as identified in this table for recirculation suction line breaks, are applicable to other non-EGGS line breaks. For a LOGA from an EGGS line break, the systems remaining are those listed for recirculation suction breaks, less the EGGS in which the break is assumed. t

j:

§ Analyses are performed with all six ADS valves in-service. Each LPGS means operation of two core spray pumps in a system. It is assumed that both pumps in a system must operate to take credit for core spray cooling or inventory makeup in that loop. Two LPGI pumps into one loop. Four LPGI pumps into two loops, two per loop. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 5-8 Table 5.2 Available ECCS for ECCS Line Break LOCAs ECCS Line Single Available Break Failure ECCS Battery 2 LPCI,* ADSt False LOCA signal 2 LPCI, HPCI, ADS LPCS LPCI valve 2 LPCI, 1 LPCS,' HPCI, ADS Diesel generator 2 LPCI, HPCI, ADS HPCI system 4 LPCI,§ 1 LPCS, ADS Battery 1 LPCS, ADS False LOCA signal 1 LPCS, HPCI, ADS LPCI LPCI valve 2 LPCS, HPCI, ADS Diesel generator 1 LPCS, HPCI, ADS HPCI system 2 LPCI, 2 LPCS, ADS Battery 2 LPCI, 1 LPCS, ADS False LOCA signal 2 LPCI, 1 LPCS, ADS HPCI LPCI valve 2 LPCI, 2 LPCS, ADS Diesel generator 2 LPCI, 1 LPCS, ADS HPCI system 4 LPCI, 2 LPCS, ADS Two LPCI pumps into one loop. t Analyses are performed with all six ADS valves in-service. Each LPCS means operation of two core spray pumps in a system. It is assumed that both pumps in a system must operate to take credit for core spray cooling or inventory makeup in that loop. § Four LPCI pumps into two loops. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOGA Break Spectrum Analysis Table 5.2 Available ECCS for ECCS Line Break LOCAs ECCS Line Single Available Break Failure ECCS Battery 2 LPCI,* ADSt False LOCA signal 2 LPCI, HPCI, ADS LPCS LPCI valve 2 LPCI, 1 LPCS,:t: HPCI, ADS Diesel generator 2 LPCI, HPCI, ADS HPCI system 4 LPCI,§ 1 LPCS, ADS Battery 1 LPCS, ADS False LOCA signal 1 LPCS, HPCI, ADS LPCI LPCI valve 2 LPCS, HPCI, ADS Diesel generator 1 LPCS, HPCI, ADS HPCI system 2 LPCI, 2 LPCS, ADS Battery 2 LPCI, 1 LPCS, ADS False LOCA signal 2 LPCI, 1 LPCS, ADS HPCI LPCI valve 2 LPCI, 2 LPCS, ADS Diesel generator 2 LPCI, 1 LPCS, ADS HPCI system 4 LPCI, 2 LPCS, ADS Two LPGI pumps into one loop. t Analyses are performed with all six ADS valves in-service. EMF-2950(NP) Revision 0 Page 5-8 Each LPGS means operation of two core spray pumps in a system. It is assumed that both pumps in a system must operate to take credit for core spray cooling or inventory makeup in that loop. § Four LPGI pumps into two loops. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 6-1 6.0 Recirculation Line Break LOCA Analyses The largest diameter recirculation system pipes are the suction line between the reactor vessel and the recirculation pump and the discharge line between the recirculation pump and the riser manifold ring. LOCA analyses are performed for breaks in both of these locations with consideration for both DEG and split break geometries. The break sizes considered included DEG breaks with discharge coefficients from 1.0 to 0.4 and split breaks with areas ranging between the full pipe area to 0.05 ft2. As discussed in Section 5.0, the single failures considered in the recirculation line break analyses are SF-BATT, SF-LOCA, SF-DGEN, SF-HPCI, and SF-LPCI. 6.1 Limiting Break Analysis Results The analyses demonstrates that the limiting (highest PCT) recirculation line break is the 0.5 ft2 split break in the pump discharge piping with an SF-BATT single failure and a mid-peaked axial power shape when operating at 102% EPU and 105% rated core flow. The PCT is 1998°F. The key results and event times for this limiting break are provided in Tables 6.1 and 6.2, respectively. Figures 6.1 - 6.26 provide plots of key parameters from the RELAX system and hot channel blowdown analyses. A plot of cladding temperature versus time in the hot assembly from the HUXY heatup analysis is provided in Figure 6.27. Tables 6.3 - 6.8 present the detailed break spectrum POT results for each of the single failures and state points considered in this LOCA analyses. Table 6.9 provides a summary of the highest PCT recirculation line break calculations for each of the single failures, state points, and axial power shapes. The results of the break analyses are discussed in the following sections. AREVA NP Inc. [ Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 6.0 Recirculation Line Break LOCA Analyses EMF-2950(NP) Revision 0 Page 6-1 The largest diameter recirculation system pipes are the suction line between the reactor vessel and the recirculation pump and the discharge line between the recirculation pump and the riser manifold ring. LOCA analyses are performed for breaks in both of these locations with consideration for both DEG and split break geometries. The break sizes considered included DEG breaks with discharge coefficients from 1.0 to 0.4 and split breaks with areas ranging between the full pipe area to 0.05 ft2. As discussed in Section 5.0, the single failures considered in the recirculation line break analyses are SF-BATT, SF-LOCA, SF-DGEN, SF-HPCI, and SF-LPCI. 1 6.1 Limiting Break Analysis Results The analyses demonstrates that the limiting (highest PCT) recirculation line break is the 0.5 ft2 split break in the pump discharge piping with an SF-BATT single failure and a mid-peaked axial power shape when operating at 102% EPU and 105% rated core flow. The PCT is 1998°F. The key results and event times for this limiting break are provided in Tables 6.1 and 6.2, respectively. Figures 6.1 - 6.26 provide plots of key parameters from the RELAX system and hot channel blowdown analyses. A plot of cladding temperature versus time in the hot assembly from the HUXY heatup analysis is provided in Figure 6.27. Tables 6.3 - 6.8 present the detailed break spectrum POT results for each of the single failures and state points considered in this LOCA analyses. Table 6.9 provides a summary of the highest PCT recirculation line break calculations for each of the single failures, state points, and axial power shapes. The results of the break analyses are discussed in the following sections. [ AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-2 6.2 Break Location Analysis Results Table 6.9 shows that the maximum PCT calculated for a recirculation line break occurs in the pump discharge piping. 6.3 Break Geometry and Size Analysis Results Recirculation line break PCT results versus break geometry (DEG or split) and size are presented in Tables 6.3 - 6.8. The maximum PCT calculated for a recirculation line break occurs for a 0.5 ft2 split break. 6.4 Limiting Single-Failure Analysis Results As mentioned in Section 5.1, SF-BATT is the limiting single failure based on available ECCS capacity. This conclusion is supported by analyses performed for SF-LOCA, SF-LPCI, SF-DGEN, and SF-HPCI 0.5 ft2 breaks as reported in Tables 6.4 - 6.6. 6.5 Axial Power Shape Analysis Results The results in Table 6.9 show that the mid-peaked axial power shape is limiting compared to the top-peaked shape analyses for the limiting break size. 6.6 State Point Analysis Table 6.9 shows that 102% EPU and 105% rated core flow was the limiting state point for the recirculation line breaks. Both [ ] and 102% CLTP were less limiting. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis ] 6.2 Break Location Analysis Results EMF-2950(NP) Revision 0 Page 6-2 Table 6.9 shows that the maximum PCT calculated for a recirculation line break occurs in the pump discharge piping. 6.3 Break Geometry and Size Analysis Results Recirculation line break PCT results versus break geometry (DEG or split) and size are presented in Tables 6.3 - 6.8. The maximum PCT calculated for a recirculation line break occurs for a 0.5 ft2 split break. 6.4 Limiting Single-Failure Analysis Results As mentioned in Section 5.1, SF-BATT is the limiting single failure based on available ECCS capacity. This conclusion is supported by analyses performed for SF-LOCA, SF-LPCI, SF-DGEN, and SF-HPCI 0.5 ff breaks as reported in Tables 6.4 - 6.6. 6.5 Axial Power Shape Analysis Results The results in Table 6.9 show that the mid-peaked axial power shape is limiting compared to the top-peaked shape analyses for the limiting break size. 6.6 State Point Analysis Table 6.9 shows that 102% EPU and 105% rated core flow was the limiting state point for the recirculation line breaks. Both [ ] and 102% CL TP were less limiting. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-3 Table 6.1 Results for Limiting TLO Recirculation Line Break 0.5 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial 102% EPU 105% Flow PCT 19980F Maximum local MWR 1.83% Maximum planar average MWR 0.839% AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. Table 6.1 Results for Limiting TLO Recirculation Line Break 0.5 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial 102% EPU 105% Flow peT Maximum local MWR 1.83% Maximum planar average MWR 0.839% EMF-2950(NP) Revision 0 Page 6-3

Browns Ferry Units 1,2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 6-4 Table 6.2 Event Times for Limiting TLO Recirculation Line Break 0.5 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial 102% EPU 105% Flow Time Event (sec) Initiate break 0.0 Initiate scram 0.5 Low-low liquid level, L2 (448 in) 16.4 Low-low-low liquid level, Li (372.5 in) 26.7 Jet pump uncovers 35.5 Recirculation suction uncovers 57.2 Lower plenum flashes 71.3 LPCS high-pressure cutoff 201.4 LPCS valve pressure permissive 193.1 LPCS valve starts to open 195.1 LPCS valve fully open 228.1 LPCS permissive for ADS timer 55.7 LPCS pump at rated speed 58.7 LPCS flow starts 201.4 RDIV pressure permissive 222.0 RDIV starts to close 224.0 RDIV fully closed 260.0 Rated LPCS flow 277.2 ADS valves open 175.7 Blowdown ends 277.2 Bypass reflood 421.4 Core reflood 358.3 PCT 358.3 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. Table 6.2 Event Times for Limiting TLO Recirculation Line Break 0.5 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial 102% EPU 105% Flow Time Event (sec) Initiate break 0.0 Initiate scram 0.5 Low-low liquid level, L2 (448 in) 16.4 Low-low-low liquid level, L 1 (372.5 in) 26.7 Jet pump uncovers 35.5 Recirculation suction uncovers 57.2 Lower plenum flashes 71.3 LPCS high-pressure cutoff 201.4 LPCS valve pressure permissive 193.1 LPCS valve starts to open 195.1 LPCS valve fully open 228.1 LPCS permissive for ADS timer 55.7 LPCS pump at rated speed 58.7 LPCS flow starts 201.4 RDIV pressure permissive 222.0 RDIV starts to close 224.0 RDIV fully closed 260.0 Rated LPCS flow 277.2 ADS valves open 175.7 Blowdown ends 277.2 Bypass reflood 421.4 Core reflood 358.3 PCT 358.3 EMF-2950(NP) Revision 0 Page 6-4

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-5 Table 6.3 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-BATT I I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [

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] AREVA NP Inc. Table 6.3 TlO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-BATT EMF-2950(NP) Revision 0 Page 6-5 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-6 Table 6.4 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-LOCA/DGEN II I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Table 6.4 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-LOCAlOGEN EMF-2950(NP) Revision 0 Page 6-6 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-7 Table 6.5 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-HPCI I I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Table 6.5 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF*HPCI EMF-2950(NP) Revision 0 Page 6-7 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-8 Table 6.6 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-LPCI I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Table 6.6 TLO Recirculation Line Break Spectrum Results for 102% EPU 105% Flow SF-LPCI EMF-2950(NP) Revision 0 Page 6-8 1

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-9 Table 6.7 TLO Recirculation Line Break Spectrum Results for 102% EPU [ ] SF-BATT I I I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Table 6.7 TLO Recirculation Line Break Spectrum Results for 102% EPU [ ] SF-BATT [

• [

] AREVA NP Inc. EMF-2950(NP) Revision 0 Page 6-9 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-10 Table 6.8 TLO Recirculation Line Break Spectrum Results for 102% CLTP 105% Flow SF-BATT I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Table 6.8 TLO Recirculation Line Break Spectrum Results for 102% CLTP 105% Flow SF-BATT EMF-2950(NP) Revision 0 Page 6-10 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-11 Table 6.9 Summary of TLO Recirculation Line Break Results Highest PCT Cases [ I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Table 6.9 Summary of TlO Recirculation Line Break Results Highest PCT Cases EMF-2950(NP) Revision 0 Page 6-11 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-12 I Figure 6.1 Limiting TLO Recirculation Line Break Upper Plenum Pressure I I Figure 6.2 Limiting TLO Recirculation Line Break Total Break Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 6.1 Limiting TLO Recirculation Line Break Upper Plenum Pressure Figure 6.2 Limiting TLO Recirculation Line Break Total Break Flow Rate EMF-2950(NP). ] ] Revision 0 Page 6-12

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-13 I Figure 6.3 Limiting TLO Recirculation Line Break Core Inlet Flow Rate I I Figure 6.4 Limiting TLO Recirculation Line Break Core Outlet Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 6.3 Limiting TLO Recirculation Line Break Core Inlet Flow Rate Figure 6.4 Limiting TLO Recirculation Line Break Core Outlet Flow Rate EMF-2950(NP) Revision 0 Page 6-13 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-14 I Figure 6.5 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate [ I Figure 6.6 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Suction Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 6.5 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate Figure 6.6 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Suction Flow Rate EMF-2950(NP) Revision 0 Page 6-14 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-15 I I Figure 6.7 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Exit Flow Rate I I Figure 6.8 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 6.7 Limiting TLO Recirculation Line Break Intact Loop Jet Pump Exit Flow Rate Figure 6.8 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate EMF-2950(NP) Revision 0 Page 6-15 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-16 [ I Figure 6.9 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate [ I Figure 6.10 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 6.9 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate Figure 6.10 Limiting TLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate EMF-2950(NP) Revision 0 Page 6-16 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-17 "I I I I 7 -1 Mo mo _2.0O 00 10O0 200 300 400 500 600 700 TIME (SEC) Figure 6.11 Limiting TLO Recirculation Line Bn ADS Flow Rate BROWNS FERRY 0.5 FT2/PD MID SF-BATT 102P/105F EPU 800 eak uD LO V) Cq w LCo C-, 10 100 200 300 Figure 6.12 Limiting I I I I 400 TIME (SEC) 500 600 700 800 HPK TLO Recirculation Line Break 1 Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 0.-~B~R~O~W~NS~F~ERrR~Y_O~,~S~FrT~2~P~D-TMI~D~S~F_-B~ArT~T~10~2~P/~1~0~S~F~ETP~U __ ~ lil AREVA NP Inc, u w V1 " CDo --,0 ~.., g 00 u w V1 " CD 2-0 ?i o LL -I u 0.. I I 100 200 300 400 500 600 700 TIME (SEC) Figure 6.11 Limiting TLO Recirculation Line Break ADS Flow Rate BROWNS FERRY 0,5 FT2/PD MID SF -BA TT 1 02P /1 OSF EPU 800 ..,~--~----~----~----~----~--~----~----~ 10 100 200 300 400 500 600 700 TIME (SEC) Figure 6.12 Limiting TLO Recirculation Line Break H PCI Flow Rate 800 EMF-2950(NP) Revision 0 Page 6-17

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-18 O Lfl .0 U, M0 C0 100 200 300 400 500 600 700 800 TIME (SEC) Figure 6.13 Limiting TLO Recirculation Line Break LPCS Flow Rate BROWNS FERRY 0.5 FT2/PD MID SF-BATT 102P/105F EPU 1L-r) 0 0 U) o-1 C-, -j 10 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 6.14 Limiting TLO Recirculation Line Break Intact Loop LPCl Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. o BROWNS FERRY o.s FT2 PO MID SF -BA TT 102P 10SF EPU ~ g Ill~ III

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o ....J '-'-0 Ul!ii' () 0.. ....J 0() 'O-w Ul "- 00 ....J ~o ?i o ....J UI 0.. ....J d N I 70 100 200 300 4{)0 500 600 700 TIME (SEC) Figure 6.13 Limiting TLO Recirculation Line Break LPCS Flow Rate BROWNS FERRY 0.5 FT2/PD MID SF -BA TT 1 02P / 1 OSF EPU 100 200 300 4{)0 500 600 700 TIME (SEC) Figure 6.14 Limiting TLO Recirculation Line Break Intact Loop LPCI Flow Rate 800 800 EMF-2950(NP) Revision 0 Page 6-18

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-19 BROWNS FERRY 0.5 FT2/PD MID SF-BATT 102P/105F EPU n 0~ UT MN I I I I I I I I I I I 10 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 6.15 Limiting TLO Recirculation Line Break Broken Loop LPCl Flow Rate oe.. -J 0 l-- -J -J z 00 (if 0d Z) 0O 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 6.16 Limiting TLO Recirculation Line Break Upper Downcomer Mixture Level AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis u-w (J) "- CD c- .0 ~ o t... ~I CD N I BROWNS FERRY 0.5 FT2/PD MID SF -BA TT 1 02P /1 05F EPU ~L-__ ~ ____ -L ____ -L ____ ~ ____ L-__ ~ ____ -L ____ ~ AREVA NP Inc. 10 100 200 300 400 500 600 700 BOO ..J ~'" w -' x ~ 0::<0 W o u z ~.. o 0:: w

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Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-20 UD -j X U-00 z 0 j L 0 00 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 6.17 Limiting TLO Recirculation Line Break Lower Downcomer Mixture Level 0 8 BROWNS FERRY 0.5 FT2/PD MID SF-N m8 -'o 0 Oo 00 zo 00 00 zo ý-V CO 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 6.18 Limiting TLO Recirculation Line Break Lower Downcomer Liquid Mass AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis' AREVA NP Inc. .3 w'" >~ W x :< o::~ W

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Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-21 mo -/1 <0M0 _o I0 La -i 00 100 200 300 400 500 600 700 TIME (SEC) Figure 6.19 Limiting TLO Recirculation Line Break Intact Loop Discharge Line Liquid Mass 800 88 BROWNS FERRY 0.5 FT2/PD MID SF 00 Do zoo 0-co 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 6.20 Limiting TLO Recirculation Line Break Upper Plenum Liquid Mass AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. ~ BROWNS FERRY 0.5 FT2 PD MID SF -BA TT 102P 105F EPU 0() 0 0 0 0 '"

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Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-22 0 no .Zowo 05 w* Ld 0 00 100 200 300 400 500 600 700 800 TIME (SEC) Figure 6.21 Limiting TLO Recirculation Line Break Lower Plenum Liquid Mass BROWNS FERRY 0.5 FT2/PD MID SF-BATT 102P/105F EPU 0 -LJ -j z 00 1H I I I I I 50 100 15 200 TIME (SEC) 250 300 350 400 Figure 6.22 Limiting TLO Recirculation Line Break Hot Channel Inlet Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 8 BROWNS FERRY 0.5 FT2 PD MID SF -BA TT 102P 105F EPU g g o~ ~ ~ ~ ~ ~ ~ ~ ~ AREVA NP Inc. 3i o Ro o 1-0< W ~~ z < I U I-00 I 100 200 300 400 500 600 700 TIME (SEC) Figure 6.21 Limiting TLO Recirculation Line Break Lower Plenum Liquid Mass BROWNS FERRY 0.5 FT2 PD MID SF -BA TT 102P 105F EPU BOO o~ ~ ~ ~ ~ ~ ~ ~ ~ IB 5B lBB 15B 200 250 300 350 TIME (SEC) Figure 6.22 Limiting TLO Recirculation Line Break Hot Channel Inlet Flow Rate 400 EMF-2950(NP) Revision 0 Page 6-22

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-23 Oo 0 -j U-2 zz 10 400 Figure 6.23 Limiting TLO Recirculation Line Break Hot Channel Outlet Flow Rate I Figure 6.24 Limiting TLO Recirculation Line Break Hot Channel Coolant Temperature at the Limiting Node AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. BROWNS FERRY o.s FT2/PD MID SF -BA TT 1 02P /1 OSF EPU oo~~~~~=r~~~~~F-~~~~=+~~~--~ ~., ~ o ro..... U W U1 m --l ~o 70L-------'-SO-----,LOO-----"SO-----2LOO------'2S-0 ----3.LOO----.....13S-0-------'400 TIME (SEC) Figure 6.23 Limiting TLO Recirculation Line Break Hot Channel Outlet Flow Rate Figure 6.24 Limiting TLO Recirculation Line Break Hot Channel Coolant Temperature at the Limiting Node EMF-2950(NP) Revision 0 Page 6-23 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-24 I Figure 6.25 Limiting TLO Recirculation Line Break Hot Channel Quality at the Limiting Node I I Figure 6.26 Limiting TLO Recirculation Line Break Hot Channel Heat Transfer Coef. at the Limiting Node AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 6.25 Limiting TLO Recirculation Line Break Hot Channel Quality at the Limiting Node Figure 6.26 Limiting TLO Recirculation Line Break Hot Channel Heat Transfer Coef. at the Limiting Node EMF-2950(NP) Revision 0 Page 6-24 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 6-25 2500 2000 1500 0 CIL E F-- on 1000 0 500 50 100 150 200 250 300 350 400 Time (sec) Figure 6.27 Limiting TLO Recirculation Line Break Cladding Temperatures AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 2500 o---a PCT Rod (Rod 11) 0----0 Water Channel IJr-------{>. Fuel Channel 2000 g Q) L

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L Q) a. E Q) l-e> 1000 c '6 -0 0 (3 500 a 50 100 150 200 250 300 350 Time (sec) Figure 6.27 Limiting TLO Recirculation Line Break Cladding Temperatures AREVA NP Inc. 400 EMF-2950(NP) Revision 0 Page 6-25

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 7-1 7.0 Non-Recirculation Line LOCA Analysis LOCA analyses are performed for breaks in the LPCS line only. Breaks in other non-recirculation lines are less limiting for the reasons discussed in Section 5.3. Note that for LPCS line break cases with no core spray available, the HUXY heatup analysis is performed with the core spray heat transfer coefficients equal to 0.0. 7.1 Limiting ECCS Line Break Results The results of this analysis indicate that the limiting ECCS line break is the 0.4 ft2 DEG break in the LPCS line with battery power failure and a top-peaked axial power shape. The initial operating conditions for the limiting case are 102% rated core power and 105% rated core flow. The PCT for the limiting ECCS line break is 1604'F and maximum local cladding oxidation is 0.26%. The key event times for the limiting break are provided in Table 7.1. Table 7.2 presents initial condition flow independent PCT results for the ECCS line breaks. [ ] The 1604'F maximum PCT for ECCS line breaks is lower than the maximum PCT for recirculation line breaks of 1998°F. Therefore, ECCS line breaks are nonlimiting. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 7.0 Non-Recirculation Line LOCA Analysis EMF-2950(NP) Revision 0 Page 7-1 LOCA analyses are performed for breaks in the LPCS line only. Breaks in other non-recirculation lines are less limiting for the reasons discussed in Section 5.3. Note that for LPCS line break cases with no core spray available, the HUXY heatup analysis is performed with the core spray heattransfer coefficients equal to 0.0. 7.1 Limiting ECCS Line Break Results The results of this analysis indicate that the limiting ECCS line break is the 0.4 if DEG break in the LPCS line with battery power failure and a top-peaked axial power shape. The initial operating conditions for the limiting case are 102% rated core power and 105% rated core flow. The PCT for the limiting ECCS line break is 1604°F and maximum local cladding oxidation is 0.26%. The key event times for the limiting break are provided in Table 7.1. Table 7.2 presents initial condition flow independent PCT results for the ECCS line breaks. [ ] The 1604 of maximum PCT for ECCS line breaks is lower than the maximum PCT for recirculation line breaks of 1998°F. Therefore, ECCS line breaks are nonlimiting. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 7-2 Table 7.1 Event Times for Limiting ECCS Line Break 0.4 ft2 Double-Ended Guillotine SF-BATT Top-Peaked Axial 102% EPU 105% Flow Time Event (sec) Initiate break 0.0 Initiate scram 0.5 Low-low liquid level, L2 (448 in) 27.3 Low-low-low liquid level, LI (372.5 in) 77.9 Jet pump uncovers 82.7 Recirculation suction uncovers 0.0 Lower plenum flashes 55.9 LPCI high-pressure cutoff 205.2 LPCI valve pressure permissive 191.7 LPCI valve starts to open 193.7 LPCI valve fully open 233.7 LPCS permissive for ADS timer 106.9 LPCI pump at rated speed 110.9 LPCI flow starts 208.7 RDIV pressure permissive 264.0 RDIV starts to close 266.0 RDIV fully closed 302.0 Rated LPCS pressure 320.8 ADS valves open 226.9 Blowdown ends 320.8 Bypass reflood NA Core reflood 347.4 PCT 347.4 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Table 7.1 Event Times for Limiting ECCS Line Break 0.4 ftl Double-Ended Guillotine SF-BATT Top-Peaked Axial 102% EPU 105% Flow Time Event (sec) Initiate break 0.0 Initiate scram 0.5 Low-low liquid level, L2 (448 in) 27.3 Low-low-low liquid level, L 1 (372.5 in) 77.9 Jet pump uncovers 82.7 Recirculation suction uncovers 0.0 Lower plenum flashes 55.9 LPCI high-pressure cutoff 205.2 LPCI valve pressure permissive 191.7 LPCI valve starts to open 193.7 LPCI valve fully open 233.7 LPCS permissive for ADS timer 106.9 LPCI pump at rated speed 110.9 LPCI flow starts 208.7 RDIV pressure permissive 264.0 RDIV starts to close 266.0 RDIV fully closed 302.0 Rated LPCS pressure 320.8 ADS valves open 226.9 Blowdown ends 320.8 Bypass reflood NA Core reflood 347.4 PCT 347.4 AREVA NP Inc. EMF-2950(NP) Revision 0 Page 7-2

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 7-3 Table 7.2 Non-Recirculation Line Break Spectrum Results for 102% EPU I I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. Table 7.2 Non-Recirculation Line Break Spectrum Results for 102% EPU ] EMF-2950(NP) Revision 0 Page 7-3

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 8-1 8.0 Single-Loop Operation LOCA Analysis During SLO the pump in one recirculation loop is not operating. A break may occur in either loop, but results from a break in the inactive loop would be similar to those from a two-loop operation break. If a break occurs in the inactive loop during SLO, the intact active loop flow to the reactor vessel would continue during the recirculation pump coastdown period and would provide core cooling similar to that which would occur in breaks during two-loop operation. System response would be similar to that resulting from an equal-sized break during two-loop operation. A break in the active loop during SLO results in a more rapid loss of core flow and earlier degraded core conditions relative to those from a break in the inactive loop. Therefore, only breaks in the active recirculation loop are analyzed. A break in the active recirculation loop during SLO will result in an earlier loss of core heat transfer relative to a similar break occurring during two-loop operation. This occurs because there will be an immediate loss of jet pump drive flow. Therefore, fuel rod surface temperatures will increase faster in an SLO LOCA relative to a normal operation LOCA. Also, the early loss of core heat transfer will result in higher stored energy in the fuel rods at the start of the heatup. The increased severity of an SLO LOCA can be reduced by applying an SLO multiplier to the two-loop MAPLHGR limits. [ ] 8.1 SLO Analysis Modeling Methodology AREVA NP Inc. [ Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 8.0 Single-Loop Operation LOCA Analysis EMF-2950(NP) Revision 0 Page 8-1 During SLO the pump in one recirculation loop is not operating. A break may occur in either loop, but results from a break in the inactive loop would be similar to those from a two-loop operation break. If a break occurs in the inactive loop during SLO, the intact active loop flow to the reactor vessel would continue during the recirculation pump coastdown period and would provide core cooling similar to that which would occur in breaks during two-loop operation. System response would be similar to that resulting from an equal-sized break during two-loop operation. A break in the active loop during SLO results in a more rapid loss of core flow and earlier degraded core conditions relative to those from a break in the inactive loop. Therefore, only breaks in the active recirculation loop are analyzed. A break in the active recirculation loop during SLO will result in an earlier loss of core heat transfer relative to a similar break occurring during two-loop operation. This occurs because there will be an immediate loss of jet pump drive flow. Therefore, fuel rod surface temperatures will increase faster in an SLO LOCA relative to a normal operation LOCA. Also, the early loss of core heat transfer will result in higher stored energy in the fuel rods at the start of the heatup. The increased severity of an SLO LOCA can be reduced by applying an SLO multiplier to the two-loop MAPLHGR limits. [ ] 8.1 SLO Analysis Modeling Methodology ] AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-2 I 8.2 SLO Analysis Results [I The SLO analyses are performed with a 0.85 multiplier applied to the two-loop MAPLHGR limit resulting in an SLO MAPLHGR limit of 10.625 kW/ft. The analyses are performed at BOL ATRIUM-10 fuel conditions. The limiting SLO LOCA is the 0.6 ft2 split pump discharge line break with SF-BATT and a mid-peaked axial power shape. The PCT for this case is 1818'F. Other key results and event times for the limiting SLO LOCA are provided in Tables 7.1 and 7.2, respectively. Figures 7.1 - 7.26 show important RELAX system blowdown and hot channel results from the SLO limiting LOCA analysis. Figure 7.27 shows the cladding surface temperature for the limiting rod as calculated by HUXY. Table 7.3 shows the spectrum of SLO analyses and the PCT for each case. A comparison of the limiting SLO and the limiting two-loop results is provided in Table 7.4. The results in Table 7.4 show that the limiting two-loop LOCA results bound the limiting SLO results when a 0.85 multiplier is applied to the two-loop MAPLHGR limit. AREVA NP Inc. [ [ Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 8.2 SLO Analysis Results ] ] EMF-2950(NP) Revision 0 Page 8-2 The SLO analyses are performed with a 0.85 multiplier applied to the two-loop MAPLHGR limit resulting in an SLO MAPLHGR limit of 10.625 kW/ft. The analyses are performed at BOL ATRIUM-10 fuel conditions. The limiting SLO LOCA is the 0.6 ft2 split pump discharge line break with SF-BATT and a mid-peaked axial power shape. The PCT for this case is 1818°F. Other key results and event times for the limiting SLO LOCA are provided in Tables 7.1 and 7.2, respectively. Figures 7.1 - 7.26 show important RELAX system blowdown and hot channel results from the SLO limiting LOCA analysis. Figure 7.27 shows the cladding surface temperature for the limiting rod as calculated by HUXY. Table 7.3 shows the spectrum of SLO analyses and the PCT for each case. A comparison of the limiting SLO and the limiting two-loop results is provided in Table 7.4. The results in Table 7.4 show that the limiting two-loop LOCA results bound the limiting SLO results when a 0.85 multiplier is applied to the two-Io'op MAPLHGR limit. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-3 Table 8.1 Results for Limiting SLO Recirculation Line Break 0.6 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial [ I PCT 1818OF Maximum local MWR 0.91% AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. Table 8.1 Results for Limiting SLO Recirculation Line Break 0.6 tt2 Split Pump Discharge SF-BATT Mid-Peaked Axial [ peT Maximum local MWR 0.91% ] EMF-2950(NP) Revision 0 Page 8-3

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 8-4 Table 8.2 Event Times for Limiting SLO Recirculation Line Break 0.6 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial [ ] Time Event (sec) Initiate break 0.0 Initiate scram 0.5 Low-low liquid level, L2 (448 in) 14.6 Low-low-low liquid level, Li (372.5 in) 22.4 Jet pump uncovers 30.4 Recirculation suction uncovers 47.0 Lower plenum flashes 60.5 LPCS high-pressure cutoff 185.9 LPCS valve pressure permissive 177.8 LPCS valve starts to open 179.8 LPCS valve fully open 212.8 LPCS permissive for ADS timer 51.4 LPCS pump at rated speed 54.4 LPCS flow starts 185.9 RDIV pressure permissive 205.3 RDIV starts to close 207.3 RDIV fully closed 243.3 Rated LPCS flow 255.0 ADS valves open 171.4 Blowdown ends 255.0 Bypass reflood 389.9 Core reflood 335.0 PCT 335.0 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. Table 8.2 Event Times for Limiting SLO Recirculation Line Break 0.6 ft2 Split Pump Discharge SF-BATT Mid-Peaked Axial [ ] Time Event (sec) Initiate break 0.0 Initiate scram 0.5 Low-low liquid level, L2 (448 in) 14.6 Low-low-low liquid level, L 1 (372.5 in) 22.4 Jet pump uncovers 30.4 Recirculation suction uncovers 47.0 Lower plenum flashes 60.5 LPCS high-pressure cutoff 185.9 LPCS valve pressure permissive 177.8 LPCS valve starts to open 179.8 LPCS valve fully open 212.8 LPCS permissive for ADS timer 51.4 LPCS pump at rated speed 54.4 LPCS flow starts 185.9 RDIV pressure permissive 205.3 RDIV starts to close 207.3 RDIV fully closed 243.3 Rated LPCS flow 255.0 ADS valves open 171.4 Blowdown ends 255.0 Bypass reflood 389.9 Core reflood 335.0 PCT 335.0 EMF-2950(NP) Revision 0 Page 8-4

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-5 Table 8.3 SLO Recirculation Line Break Spectrum Results I I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [

• [

] AREVA NP Inc. Table 8.3 SLO Recirculation Line Break Spectrum Results EMF-2950(NP) Revision 0 Page 8-5 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-6 Table 8.4 Single-and Two-Loop Operation PCT Summary Limiting PCT Operation Case (OF) Single-loop 0.6 ft2 split pump discharge 1818 mid-peaked SF-BATT Two-loop 0.5 ft2 split pump discharge 1998 mid-peaked SF-BATT AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Operation Single-loop Two-loop AREVA NP Inc. Table 8.4 Single-and Two-Loop Operation PCT Summary Limiting Case 0.6 ft2 split pump discharge mid'"peaked SF-BATT 0.5 ft2 split pump discharge mid-peaked SF-BATT PCT (OF) 1818 1998 EMF-2950(NP) Revision 0 Page 8-6

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-7 I Figure 8.1 Limiting SLO Recirculation Line Break Upper Plenum Pressure I Figure 8.2 Limiting SLO Recirculation Line Break Total Break Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 8.1 Limiting SLO Recirculation Line Break Upper Plenum Pressure Figure 8.2 Limiting SLO Recirculation Line Break Total Break Flow Rate EMF~2950(NP) Revision a Page 8~7 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-8 I Figure 8.3 Limiting SLO Recirculation Line Break Core Inlet Flow Rate I Figure 8.4 Limiting SLO Recirculation Line Break Core Outlet Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 8.3 Limiting SLO Recirculation Line Break Core Inlet Flow Rate Figure 8.4 Limiting SLO Recirculation Line Break Core Outlet Flow Rate EMF-2950(NP) Revision 0 Page 8-8 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-9 I Figure 8.5 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate I I Figure 8.6 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Suction Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 8.5 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Drive Flow Rate Figure 8.6 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Suction Flow Rate EMF-2950(NP) Revision 0 Page 8-9 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-10 I Figure 8.7 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Exit Flow Rate I I Figure 8.8 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 8.7 Limiting SLO Recirculation Line Break Intact Loop Jet Pump Exit Flow Rate Figure 8.8 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Drive Flow Rate EMF-2950(NP) Revision 0 Page 8-10 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-11 I Figure 8.9 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate [ I Figure 8.10 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 8.9 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Suction Flow Rate Figure 8.10 Limiting SLO Recirculation Line Break Broken Loop Jet Pump Exit Flow Rate EMF-2950(NP) Revision 0 Page 8-11 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-12 o C-,F mo C0C', II I I 0O 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 8.11 Limiting SLO Recirculation Line Break ADS Flow Rate BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P/105F SLO EPU I I I I I I I U') Li 0 C3) 10 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 8.12 Limiting SLO Recirculation Line Break HPCI Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis ~ r-----,B=.R.:..:;O...:..:W.:..:.NS=---.cF-=.ER:.;:R.:..:Y--=.;0.c.=.6 --,F,..:.T-=.2 <....:P-=D~MI:.=.D --,S:..:.F_-=.cBATCTc.:.T--'-C1 0:..::2::"PL.:..:.1 O:..::S.:..:.F -=S:;:L-=O-=E:::..P-=U~ AREVA NP Inc. u w (I) mo ....10 ?Ii o ....I "-0 o (I)'" o << g 0() u w (I) m do ?Ii o ....I "--I u a.

c 100 200 300 400 500 600 700 TIME (SEC)

Figure 8.11 Limiting SLO Recirculation Line Break ADS Flow Rate BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P/10SF SLO EPU BOO ",L-__ ~ ____ -L ____ -L ____ ~ ____ L-__ ~ ____ -L ____ ~ 10 100 200 300 400 500 600 700 BOO TIME (SEC) Figure 8.12 Limiting SLO Recirculation Line Break HPCI Flow Rate EMF-2950(NP) Revision 0 Page 8-12

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-13 t bIUWNS L.NKY U.b V I Z/ FU MIU Z>V-bA II I1UZI'~/ IU:I-bLU LI-LO g 0-j 0 00 100 200 300 400 500 600 700 TIME (SEC) Figure 8.13 Limiting SLO Recirculation Line Break LPCS Flow Rate BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P/105F SLO EPU Boo IAI I 0 EL

• 0 100 200 300 Figure 8.14 Limiting I

I I I 400 TIME (SEC) 500 600 700 800 Intact Loc SLO Recirculation Line Break

• p LPCI Flow Rate AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. o BROWNS FERRY 0.6 FT2 PD MID SF -BA TT 1 02P /1 05F SLO EPU ~ o o U')~ U') ~ 0() I 100 200 300 400 500 600 700 TIME (SEC) Figure 8.13 Limiting SLO Recirculation Line Break LPCS Flow Rate BROWNS FERRY 0.6 FT2/PD MID SF -SA TT 1 02P /1 05F SLO EPU '70 100 200 300 400 500 600 700 TIME (SEC) Figure 8.14 Limiting SLO Recirculation Line Break Intact Loop LPCI Flow Rate BOO BOO EMF~2950(NP) Revision 0 Page 8-13

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-14 BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P/105F SLO EPU LOn "I) 0 -j 5-10 100 200 300 400 TIME (SEC) 500 600 700 Boo Figure 8.15 Limiting SLO Recirculation Line Break Broken Loop LPCI Flow Rate -J U-U- -S w of LL w Q:2= -IJ 00 0 aaN- -0 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 8.16 Limiting SLO Recirculation Line Break Upper Downcomer Mixture Level AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis u~ w (f) '- (D .0 3: o ...J u... o~

0. 1

...J ...J (D N 1 BROWNS FERRY 0.6 FT2/PD MID SF -BA TT 1 02P /1 05F SLO EPU ~L-__ ~ ____ -L ____ -L ____ ~ ____ L-__ ~ ____ -L ____ ~ AREVA NP Inc. 10 100 200 300 400 500 600 700 BOO ....i ~'" W ...J X ~ a::'" w o o z ~"' o a:: w

0. g,N TIME (SEC)

Figure 8.15 Limiting SLO Recirculation Line Break Broken Loop LPCI Flow Rate BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P/105F SLO EPU cO 100 200 300 400 500 600 700 TIME (SEC) Figure 8.16 Limiting SLO Recirculation Line Break Upper Downcomer Mixture Level BOO EMF-2950(NP) Revision 0 Page 8-14

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-15 X (0 3-J x bw 0 0 00 100 200 300 400 500 600 700 TIME (SEC) Figure 8.17 Limiting SLO Recirculation Line Break Lower Downcomer Mixture Level 800 8 BROWNS FERRY 0.6 FT2/P0 MID SF-m8 cf)l --J 0 a 00 U-1 0 300 0N -j o 100 200 300 400 TIME (SEC) 500 600 700 800 Figure 8.18 Limiting SLO Recirculation Line Break Lower Downcomer Liquid Mass AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. BROWNS FERRY 0.6 FT2/PD MID SF -BA TT 1 02P /1 05F SLO EPU c() 100 200 300 400 500 600 700 TIME (SEC) Figure 8.17 Limiting SLO Recirculation Line Break Lower Downcomer Mixture Level o g BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P/105F SLO EPU <0-o g o [jJ- -=-*0 ~g >... <<~ -, o So Qg -'0 e:: w

00 uo

~§ o o f5§

';0 0'"

\\~~--------------------- c() 100 200 300 400 500 TIME (SEC) 600 700 Figure 8.18 Limiting SLO Recirculation Line Break Lower Downcomer Liquid Mass BOO BOO EMF-2950(NP) Revision 0 Page 8-15

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-16 BROWNS FERRY 0.6 FT2/PD MID SF-rr) V,) 0~ T we 000 00 100 200 300 400 TIME (SEC) Figure 8.19 Limiting SLO Reci Intact Loop Discharge Lii BROWNS FERRY 0.6 FT2/PD MID SF 0 0 0 (11 Do -- 0 0"' 00 100 200 300 400 TIME (SEC) 500 600 700 B00 rculation Line Break ne Liquid Mass 500 600 700 800 Figure 8.20 Limiting SLO Recirculation Line Break Upper Plenum Liquid Mass AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. ~ BROWNS FERRY 0.6 FT2 PD MID SF -BA TT 102P 105F SLO EPU vi VJ ~g o o~ 5 a ~g ct:'" I () VJ 08 ",,!;j! 00 0 0 0 0 '"

=0 0 0 0.,

m -'0 ~o 0 vi!;j! VJ 08 58 an

Jo zo W o

-,1<: 0.. ct: ~g 0..0

J~

100 200 300 400 500 600 700 TIME (SEC) Figure 8.19 Limiting SLO Recirculation Line Break Intact Loop Discharge Line Liquid Mass BROWNS FERRY 0.6 FT2/PD MID SF-BATT 102P/105F SLO EPU

• r 00 100 200 300 400 500 600 700 TIME (SEC)

Figure 8.20 Limiting SLO Recirculation Line Break Upper Plenum Liquid Mass 800 800 EMF-2950(NP) Revision 0 Page 8-16

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-17 Q~- 0 -o _j EL -j 400 TIME (SEC) Figure 8.21 Limiting SLO Recirculation Line Break Lower Plenum Liquid Mass I I Figure 8.22 Limiting SLO Recirculation Line Break Hot Channel Inlet Flow Rate AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis g g BROWNS FERRY 0.6 FT2 PD MID SF -BA TT 102P 105F SLO EPU / [ AREVA NP Inc. 100 200 300 400 500 600 700 TIME (SEC) Figure 8.21 Limiting SLO Recirculation Line Break Lower Plenum Liquid Mass Figure 8.22 Limiting SLO Recirculation Line Break Hot Channel Inlet Flow Rate BOO EMF-2950(NP) Revision 0 Page 8-17 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-18 I Figure 8.23 Limiting SLO Recirculation Line Break Hot Channel Outlet Flow Rate I Figure 8.24 Limiting SLO Recirculation Line Break Hot Channel Coolant Temperature at the Limiting Node AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 8.23 Limiting SLO Recirculation Line Break Hot Channel Outlet Flow Rate Figure 8.24 Limiting SLO Recirculation Line Break Hot Channel Coolant Temperature at the Limiting Node EMF-2950(NP) Revision 0 Page 8-18 ] ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-19 I: I Figure 8.25 Limiting SLO Recirculation Line Break Hot Channel Quality at the Limiting Node [ I Figure 8.26 Limiting SLO Recirculation Line Break Hot Channel Heat Transfer Coef. at the Limiting Node AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ AREVA NP Inc. Figure 8.25 Limiting SLO Recirculation Line Break Hot Channel Quality at the Limiting Node Figure 8.26 Limiting SLO Recirculation Line Break Hot Channel Heat Transfer Coef. at the Limiting Node EMF-2950(NP) Revision 0 Page 8-19 1 1

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page 8-20 2500 2000 1500 0uE I-- o 1000 C) 500 0 50 100 150 200 250 300 350 400 Time (sec) Figure 8.27 Limiting SLO Recirculation Line Break Cladding Temperatures AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 2500 o----a PCT Rod (Rod 0----0 Water Channel I!r------i>. Fuel Channel 2000 ~ Cl>....

J

-+-' 0 1500 Cl> a. E Cl> I-0> 1000 c '6 "0 0 U 500 o 50 100 11 ) \\ " 150 200 250 300 350 Time (sec) Figure 8.27 Limiting SLO Recirculation Line Break Cladding Temperatures AREVA NP Inc. 400 EMF-2950(NP) Revision 0 Page 8-20

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 9-1 9.0 Long-Term Coolability Long-term coolability addresses the issue of reflooding the core and maintaining a water level adequate to cool the core and remove decay heat for an extended time period following a LOCA. For non-recirculation line breaks, the core can be reflooded to the top of the active fuel and be adequately cooled indefinitely. For recirculation line breaks, the core will initially remain covered following reflood due to the static head provided by the water filling the jet pumps to a level of approximately two-thirds core height. Eventually, the heat flux in the core will not be adequate to maintain a two-phase water level over the entire length of the core. Beyond this time, the upper third of the core will remain wetted and adequately cooled by core spray. Maintaining water level at two-thirds core height with one core spray system operating is sufficient to maintain long-term coolability as demonstrated by the NSSS vendor (Reference 8). AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 9.0 Long-Term Coolability EMF-2950(NP) Revision 0 Page 9-1 Long-term coolability addresses the issue of reflooding the core and maintaining a water level adequate to cool the core and remove decay heat for an extended time period following a LOCA. For non-recirculation line breaks, the core can be reflooded to the top of the active fuel and be adequately cooled indefinitely. For recirculation line breaks, the core will initially remain covered following reflood due to the static head provided by the water filling the jet pumps to a level of approximately two-thirds core height. Eventually, the heat flux in the core will not be adequate to maintain a two-phase water level over the entire length of the core. Beyond this time, the upper third of the core will remain wetted and adequately cooled by core spray. Maintaining water level at two-thirds core height with one core spray system operating is sufficient to maintain long-term coolability as demonstrated by the NSSS vendor (Reference 8). AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 10-1 10.0 Conclusions The major conclusions of this LOCA break spectrum analysis are: The limiting recirculation line break is a 0.5 ft2 split break in the pump discharge piping with single failure SF-BATT and a mid-peaked axial shape at 102% EPU and 105% rated core flow for two-loop operation. The limiting break analysis identified above satisfies all acceptance criteria specified in 10 CFR 50.46. The analysis is performed in accordance with 10 CFR 50.46 Appendix K requirements. Peak PCT < 2200'F (1998°F). Local cladding oxidation thickness < 0.17 (0.0183). Total hydrogen generation < 0.01 (the break spectrum analysis had a maximum planar average MWR of less than 0.01, it is concluded that core-wide metal-water reaction (CMWR) would be less than 0.01). Coolable geometry, satisfied by meeting peak PCT, local cladding oxidation, and total hydrogen generation criteria. Core long-term cooling, satisfied by concluding core flooded to top of active fuel or core flooded to the jet pump suction elevation with one core spray operating. Breaks in the non-recirculation lines are less limiting than the most severe break in the recirculation line. The MAPLHGR limit multiplier for SLO is 0.85 for ATRIUM-1 0 fuel. This multiplier ensures that a LOCA from SLO is less limiting than a LOCA from two-loop operation. The limiting break characteristics determined in this report can be referenced and used in future Browns Ferry Units 1, 2, and 3 LOCA analyses to establish the MAPLHGR limit versus exposure for ATRIUM-10 fuel. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate EMF-2950(NP) Revision 0 Page 10-1 LOCA Break Spectrum Analysis 10.0 Conclusions The major conclusions of this LOCA break spectrum analysis are: The limiting recirculation line break is a 0.5 ft2 split break in the pump discharge piping with single failure SF-BATT and a mid-peaked axial shape at 102% EPU and 105% rated core flow for two-loop operation. The limiting break analysis identified above satisfies all acceptance criteria specified in 10 CFR 50.46. The analysis is performed in accordance with 10 CFR 50.46 Appendix K requirements. Peak PCT < 2200°F (1998°F). Local cladding oxiqation thickness < 0.17 (0.0183). Total hydrogen generation < 0.01 (the break spectrum analysis had a maximum planar average MWR of less than 0.01, it is concluded that core-wide metal-water reaction (CMWR) would be less than 0.01). Coolable geometry, satisfied by meeting.peak PCT, local cladding oxidation, and total hydrogen generation criteria. Core long-term cooling, satisfied by concluding core flooded to top of active fuel or core flooded to the jet pump suction elevation with one core spray operating. Breaks in the non-recirculation lines are less limiting than the most severe break in the recirculation line. The MAPLHGR limit multiplier for SLO is 0.85 for ATRIUM-10 fuel. This multiplier ensures that a LOCA from SLO is less limiting than a LOCA from two-loop operation. The limiting break characteristics determined in this report can be referenced and used in future Browns Ferry Units 1, 2, and 3 LOCA analyses to establish the MAPLHGR limit versus exposure for ATRIUM-10 fuel. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page 11-1 11.0 References

1.

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

2.

XN-CC-33(P)(A) Revision 1, HUXY: A Generalized Multirod Heatup Code with 10 CFR 50 Appendix K Heatup Option Users Manual, Exxon Nuclear Company, November 1975.

3.

XN-NF-82-07(P)(A) Revision 1, Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model, Exxon Nuclear Company, November 1982.

4.

XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

5.

EMF-2292(P)(A) Revision 0, ATRIUM TM-1O: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000.

6.

EMF-2925(P) Revision 2, Browns Ferry Units 1, 2, and 3 Extended Power Uprate Plant Parameters Document, Framatome ANP, December 2003.

7.

Browns Ferry Nuclear Plant FSAR, Amendment 19.06, Tennessee Valley Authority.

8.

NEDO-20566A, Analytical Model for Loss-of-Coolant Analysis in Accordance with 10 CFR Appendix K, General Electric Company, September 19.86. AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis 11.0 References EMF-2950(NP) Revision 0 Page 11-1

1.

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

2.

XN-CC-33(P)(A) Revision 1, HUXY: A Generalized MultirodHeatup Code with 10 CFR 50 Appendix K Heatup Option Users Manual, Exxon Nuclear Company, November 1975.

3.

XN-NF-82-07(P)(A) Revision 1, Exxon Nuclear Company ECCS Cladding Swelling and Rupture Model, Exxon Nuclear Company, November 1982.

4.

XN-NF-81-58(P)(A) Revision 2 and Supplements 1 and 2, RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model, Exxon Nuclear Company, March 1984.

5.

EMF-2292(P)(A) Revision 0, ATRIUMTM-10: Appendix K Spray Heat Transfer Coefficients, Siemens Power Corporation, September 2000..

6.

EMF-2925(P) Revision 2, Browns Ferry Units 1, 2, and 3 Extended Power Uprate Plant Parameters Document, Framatome ANP, December 2003.

7.

Browns Ferry Nuclear Plant FSAR, Amendment 19.06, Tennessee Valley Authority.

8.

NEDO-20566A, Analytical Model for Loss-of-Coolant Analysis in Accordance with 10 CFR Appendix K, General Electric Company, September 19.86. AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 EMF-2950(NP) Extended Power Uprate Revision 0 LOCA Break Spectrum Analysis Page A-1 Appendix A Supplemental Information The tables and figures presented in this appendix provide additional information requested by TVA for review. The supplemental information provided is: Major computer codes used Table A. 1 Supplemental limiting break data Tables A. 2-A. 4, Figures A. 1-A. 3 Limiting recirculation line pump discharge large break (DEG) data Tables A.5-A. 7, Figures A.4-A.33 Limiting recirculation line pump suction large break (DEG) data. Tables A.8-A. 10, Figures A.34-A.63 CLTP 0.5 ft2 split break data Tables A. 11-A. 13, Figures A.64-A.93 AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis Appendix A Supplemental Information EMF-2950(NP) Revision 0 Page A-1 The tables and figures presented in this appendix provide additional information requested by TVA for review. The supplemental information provided is: Major computer codes used Table A1 Supplemental limiting break data Tables A 2-A 4, Figures A1-A3 Limiting recirculation line pump discharge large break (OEG) data Tables A5-A 7, Figures A4-A33 Limiting recirculation line pump suction large break (OEG) data. Tables A8-A10, Figures A34-A63 CL TP 0.5 ft2 split break data Tables A11-A13, Figures A64-A93 AREVA NP Inc.

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-2 [ I I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ [ t AREVA NP Inc. ] EMF-2950(NP) Revision 0 Page A-2 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-3 [ I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP l(le. EMF-2950(NP) Revision 0 Page A-3 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-4 II I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. EMF-2950(NP) Revision 0 Page A-4 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-5 I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. EMF-2950(NP) Revision 0 Page A-5 1

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-6 [ AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. EMF-2950(NP) Revision 0 Page A-6 1

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-7 [ I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. EMF-2950(NP) Revision 0 Page A-7 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-8 I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. EMF-2950(NP) Revision 0 Page A-8 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-9 I I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. EMF-2950(NP) Revision 0 Page A-9 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-10 I I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. EMF-2950(NP) Revision 0 Page A-10 ]

Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis EMF-2950(NP) Revision 0 Page A-11 I AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis [ AREVA NP Inc. EMF-2950(NP) Revision 0 Page A~11 ]

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Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Soectrum Analysis EMF-2950(NP) Revision 0 Distribution Controlled Distribution Richland DJ ME CE AB RR Braun Garrett Hendrix Meginnis Schnepp E-Mail Notification DB McBurney MS Stricker SA Tylinski AREVA NP Inc. Browns Ferry Units 1, 2, and 3 Extended Power Uprate LOCA Break Spectrum Analysis AREVA NP Inc. Distribution Controlled Distribution Richland OJ Braun ME Garrett CE Hendrix AB Meginnis RR Schnepp E-Mail Notification OB McBurney MS Stricker SA Tylinski EMF-2950(NP) Revision 0}}