ML21286A542

Amendment 29 to Updated Final Safety Analysis Report, Chapter 14, Table 14.5, Analyses of Abnormal Operational Transients

ML21286A542
Person / Time
Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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Download: ML21286A542 (2)

Text

BFN-28 Table 14.5-1 (Deleted by Amendment 28)

BFN-29 Table 14.5-2 TRANSIENT ANALYSES INITIAL CONDITIONS Parameter AREVA Reload Analysis Thermal Power, MWt 3952 (100%) / 4031 (102%)

Core Flow, Mlb/hr 102.5 Core Flow Range

(% of current rated) 85 - 105 Vessel Steam Flow and FW flow, Mlb/hr 16.44 Analysis Dome Pressure, psia 1050 Analysis Turbine Pressure, psia 988 Feedwater Temperature, F 394.8 Turbine Bypass Capacity 21.3% of rated vessel steam flow Number of MSRVs 13 MSRV type Target Rock Opening response of relief functions 0.15 s Opening delay of relief functions 0.45 s MSRV Capacity per valve, lbm/hr 870,000 (Based on 1090 psig setpoint) (12 valves)

MSRV Setpoint, 4 @ 1174ii (number of valves @ psig) 4 @ 1184

(+3% setpoint tolerance included) 4 @ 1194 MCPR Safety Limit Cycle Specific Recirculation Flow Control VFD Flow Control Core Average Gap Conductance (Btu/s-sq. ft -Deg F) Case Dependent High Neutron Flux Scram Setpoint 125.4% of rated power High Pressure Scram Setpoint, psig 1101 High Pressure ATWS-RPT setpoint, psig 1177 iii Reactor L8 Water Level, in avz 588 Reactor L3 Water Level, in avziii 518 iii Reactor L2 Water Level, in avz 448 iii Reactor L1 Water Level, in avz 372.5 i (deleted) ii Considered only 3 out of 4 due to 1 MSRV-OOS iii Above vessel zero