NL-15-169, ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9

ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9

ML15282A182
Person / Time
Site:	Browns Ferry
Issue date:	08/31/2015
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
Shared Package
ML15282A154	List: CNL-15-169, Electric Power Research Institute Affidavit ML15282A152 ML15282A166 ML15282A167 ML15282A168 ML15282A169 ML15282A178 ML15282A179 ML15282A180 ML15282A181 ML15282A182 ML15282A184 ML15282A185 ML15282A187 ML15282A188 ML15282A189 ML15282A190 ML15282A191 ML15282A192 ML15282A193 ML15282A194 ML15282A221 ML15282A222 ML15282A223 ML15282A224 ML15282A225 ML15282A235 ML15282A236 ML15282A237 ML15282A238 ML15282A239 ML15282A240 ML15282A241 ML15282A258 ML15282A259 ML15282A260 ML15282A261 NL-15-169, ANP-2637, Revision 6, Boiling Water Reactor Licensing Methodology Compendium. NL-15-169, ANP-2860NP Revision 2, Supplement 2, Browns Ferry Unit 1 - Summary of Responses to Request for Additional Information, Extension for Use of Atrium 10XM Fuel for Extended Power Uprate. NL-15-169, ANP-3342NP, Revision 1, Browns Ferry EPU (120% OLTP) Equilibrium Fuel Cycle Design. NL-15-169, ANP-3343NP, Revision 0, Nuclear Fuel Design Report Browns Ferry EPU (120% OLTP) Equilibrium Cycle Atrium 10XM Fuel. NL-15-169, ANP-3372NP, Revision 1, Browns Ferry Unit 3 Cycle 19 EPU (120% OLTP) LAR Reference Fuel Cycle Design. NL-15-169, ANP-3377NP, Browns Ferry Units 1, 2 and 3 LOCA Break Spectrum Analysis Atrium 10XM Fuel (Epu). NL-15-169, ANP-3378NP, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for Atrium 10XM Fuel (Epu). NL-15-169, ANP-3384NP, Revision 3, Browns Ferry Units 1, 2 and 3, LOCA-ECCS Analysis MAPLHGR Limits for ATRIUM-10 Fuel (Epu). NL-15-169, ANP-3385NP, Revision 1, Mechanical Design Report for Browns Ferry Units 1, 2, and 3 Extended Power Uprate (EPU) ATRIUM-10 Fuel Assemblies, Licensing Report. NL-15-169, ANP-3386NP, Revision 1, Mechanical Design Report for Browns Ferry Units 1, 2 and 3 Extended Power Uprate (EPU) Atrium 10XM Fuel Assemblies, Licensing Report. NL-15-169, ANP-3388NP, Revision 0, Fuel Rod Thermal-Mechanical Evaluation for Browns Ferry Extended Power Uprate, Licensing Report. NL-15-169, ANP-3403NP, Revision 2, Fuel Uprate Safety Analysis Report for Browns Ferry Units 1, 2, and 3, Attachment 9 NL-15-169, ANP-3404NP, Revision 2, Browns Ferry Unit 3 Cycle 19 Representative Reload Analysis at Extended Power Uprate ... further results
References
CNL-15-169 ANP-3403NP, Rev 2
Download: ML15282A182 (181)

Text

MSIVC ATWS Overpressurization Event at 100P/99F - Key Paramete rs MSIVC ATWS Overpressurization Event at 100P/99F - Sensed Water Level MSIVC ATWS Overpressurization Event at 100P/99F - Vessel Pressures MSIVC ATWS Overpressurization Event at 100P/99F - Safety/Relief Valve Flow Rates PRFO ATWS Overpressurization Event at 100P/99F - Key Parameters PRFO ATWS Overpressurization Event at 100P/99F - Sensed Water Level PRFO ATWS Overpressurization Event at 100P/99F - Vessel Pressures PRFO ATWS Overpressurization Event at 100P/99F - Safety/Relief Valve Flow Rates

Input Variable EPU 87.5% of EPU RTP CLTP* Reactor power (MWt) 3952 3458 3458 Reactor dome pressure (psia) 1050 1039.8 1050 Each MSRV capacity at 103% of 1090 psig (lbm/hr) 870,000 870,000 870,000 High pressure ATWS

-RPT setpoint (psig) 1177 1177 1177 Number of MSRVs 13 13 13 Number of MSRVs OOS 1 1 1 Acceptance Criteria EPU 87.5% o f EPU RTP CLTP* Peak vessel bottom pressure (psig) f 1469 1375 1404 Item Event Event Time (sec) 1 MSIV Isolation Initiated 0.00 2 MSIVs Fully Closed 4.00 3 Peak Neutron Flux 4.50 4 High Pressure ATWS Setpoint 4.97 5 Opening of the First Relief Valve 5.42 6 Recirculation Pumps Trip 5.47 7 Peak Heat Flux 5.92 8 Peak Vessel Pressure 11.21 Item Event Event Time (sec) 1 TCVs and Bypass Valves Start Open 0.00 2 MSIV Closure Initiated by Low Steam Line Pressure 6.02 3 MSIVs Fully Closed 10.02 4 High Pressure ATWS Setpoint 13.39 5 Opening of the First Relief Valve 13.79 6 Peak Neutron Flux 13.87 7 Recirculation Pumps Trip 13.89 8 Peak Heat Flux 14.29 9 Peak Vessel Pressure 19.70

MSIVC ATWS Overpressurization Event at 100P/99F - Vessel Pressures

• MSIVC ATWS Overpressurization Event at 100P/99F - Safety/Relief Valve Flow Rates

PRFO ATWS Overpressurization Event at 100P/99F - Key Parameters PRFO ATWS Overpressurization Event at 100P/99F - Sensed Water Level

PRFO ATWS Overpressurization Event at 100P/99F - Vessel Pressures

• PRFO ATWS Overpressurization Event at 100P/99F - Safety/Relief Valve Flow Rates

MSIVC ATWS Overpressurization Event at 100P/99F - Key Paramete rs MSIVC ATWS Overpressurization Event at 100P/99F - Sensed Water Level MSIVC ATWS Overpressurization Event at 100P/99F - Vessel Pressures MSIVC ATWS Overpressurization Event at 100P/99F - Safety/Relief Valve Flow Rates PRFO ATWS Overpressurization Event at 100P/99F - Key Parameters PRFO ATWS Overpressurization Event at 100P/99F - Sensed Water Level PRFO ATWS Overpressurization Event at 100P/99F - Vessel Pressures PRFO ATWS Overpressurization Event at 100P/99F - Safety/Relief Valve Flow Rates

Input Variable EPU 87.5% of EPU RTP CLTP* Reactor power (MWt) 3952 3458 3458 Reactor dome pressure (psia) 1050 1039.8 1050 Each MSRV capacity at 103% of 1090 psig (lbm/hr) 870,000 870,000 870,000 High pressure ATWS

-RPT setpoint (psig) 1177 1177 1177 Number of MSRVs 13 13 13 Number of MSRVs OOS 1 1 1 Acceptance Criteria EPU 87.5% o f EPU RTP CLTP* Peak vessel bottom pressure (psig) f 1469 1375 1404 Item Event Event Time (sec) 1 MSIV Isolation Initiated 0.00 2 MSIVs Fully Closed 4.00 3 Peak Neutron Flux 4.50 4 High Pressure ATWS Setpoint 4.97 5 Opening of the First Relief Valve 5.42 6 Recirculation Pumps Trip 5.47 7 Peak Heat Flux 5.92 8 Peak Vessel Pressure 11.21 Item Event Event Time (sec) 1 TCVs and Bypass Valves Start Open 0.00 2 MSIV Closure Initiated by Low Steam Line Pressure 6.02 3 MSIVs Fully Closed 10.02 4 High Pressure ATWS Setpoint 13.39 5 Opening of the First Relief Valve 13.79 6 Peak Neutron Flux 13.87 7 Recirculation Pumps Trip 13.89 8 Peak Heat Flux 14.29 9 Peak Vessel Pressure 19.70

MSIVC ATWS Overpressurization Event at 100P/99F - Vessel Pressures

• MSIVC ATWS Overpressurization Event at 100P/99F - Safety/Relief Valve Flow Rates

PRFO ATWS Overpressurization Event at 100P/99F - Key Parameters PRFO ATWS Overpressurization Event at 100P/99F - Sensed Water Level

PRFO ATWS Overpressurization Event at 100P/99F - Vessel Pressures

• PRFO ATWS Overpressurization Event at 100P/99F - Safety/Relief Valve Flow Rates