ML18024A309

Browns Ferry Nuclear Plant Updated Final Safety Analysis Report (Ufsar), Amendment 27, 13.5 Table - Startup and Power Test Program

ML18024A309
Person / Time
Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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BFN-16Table 13.5-1CONTROL ROD DRIVE SYSTEM TESTS(Unit 1) Reactor Pressure,psig Preop (With Core Loaded)Test Description Tests 0 600 800 1000Position IndicationAllAllNormal Insert/Withdraw TimesAllAll 4*CouplingAllAllFrictionAll 4*Scram Times (Normal Accumulated Pressure)AllAll 4* 4* AllScram Times (Minimum Accumulator Pressure) 4*Scram Times (Zero Accumulator Pressure) 4*Scram Times (Scram Discharge Volume High Level)AllScram Times, Rated Power (Normal Accumulator Pressure) 4** *Value refers to the four slowest drives as determined from the normal accumulator pressure scram test at ambient reactorpressure which are compatible with the Rod Worth Minimizer and withdrawal sequence requirements.**Scram times of the four slowest rods will be determined at 25, 50, and 100 percent of rated power during planned reactorscrams at these power levels.Table 13.5-2MAJOR PLANT TRANSIENTS TEST CONDITION Nominal Power, Percent of Rated 2550 7580 100 Nominal Core Flow, Percent of Rated TEST TITLE 36 100 100 70 100Feedwater Pump Trip ACMain Steam Isolation Valves (One Valve)CACMain Steam Isolation Valves (All Valves) CTurbine-Generator Stop Valve Fast CloseBATurbine-Generator Contorl Valve Fast Close AAARecirculation Pump Trip (One Pump) CB CRecirculation Pump Trip (Two Pumps)CC CLoss of Generator and Offsite Power CA - Unit 1 B - Units 2, 3 C - Units 1, 2, 3 BFN-16Table 13.5-3STABILITY TESTS TEST CONDITION Nominal Power, Percent of Rated 254050 254760753765801005097 Nominal Core Flow, Percent of RatedTEST TITLE47 70 100 NC 48 70 100 NC 48 70 100 NC 109Flux Response to RodsCACAACAAACAPressure Regulator SetpointCACAACACCCAPressure REgulator Backup RegulatorCCCCFeedwater System SetpointCACAACACCCABFeedwater System Drop HeaterABypass ValveCAC BAACACCCCBFlow ControlCCC CCCCCCNC= Natural Circulation A - unit 1 B - units 2, 3 C - units 1, 2, 3 BFN-16TABLE 13.5-4STARTUP TEST PROGRAM (UNIT 1)OPEN50% Flow Line75% Flow Line100% Flow LinePower1 .%VESSHEAT15-3530-5040-6015-3537-5750-7065-8527-4755-7570-9095-10040-6020%Flow2.%ORUP4870104NC4870102NC4870100NC105%TEST CONDITION (See Figure 13.5-2)COLDTEST1322A5A544A7A766A81Chemical & RadiochemicalXXXXXX2Radiation MeasurementsXXXXX3Fuel LoadingX4Full Core Shutdown MarginX5Control Rod Drive SystemXXXXX6SRM Performance & Control Rod SequenceXXXXX7Not Applicable8Not Applicable9Not Applicable10IRM CalibrationXXX11LPRM CalibrationXXXX12APRM CalibrationXXXXXX13Process ComputerXXXX14RCIC SystemXM15HPCI SystemXM16Reactor Vessel TemperatureXXXX17System ExpansionXXX18Core Power DistributionXXXXX19Core PerformanceXXXXXXXXXXXXX20Elec. Output & Heat RateX21Flux Response to RodsMMMMMMMXMMMX22Press. Reg.: Setpoint ChangesMMMMMMMXMMMX  : Backup RegulatorMMMM23FW System: FW Pump TripMM  : Water Level Stpt. Chg.MAMMAMMMMAXMAMAMAX  : Heater LossM*24Bypass ValvesMAMAMAMMAMAMAXMAMAMAX25Main Steam Iso. Valves: Each Vlv.XM,SPM,SPM,SP  : Full Iso.M,SE26Relief ValvesXMM,SEM27Turbine : Stop Valve TripM,SE  : Control Valve TripM,SPM,SEA,SE29Flow ControlLMAMAMAMAMAMAMAMAMA30Recirc. System: One Pump TripMM  : Two Pump TripMMM  : Flow CalibrationXXXXXX31Loss of T-G & Offsite PowerM,SELSE32Recirc. Loop ControlXXXX35Recirc. And Jet Pump CalibrationX36Equalizer OpenMM39Water Level verification in ReactorVesselXXX70Reactor Water Cleanup SystemX71Residual Heat Removal System**72Drywell Atmosphere Cooling SystemXX73Cooling Water SystemsXX90Vibration**XXXXXX92Steam Separator and DryerXXXSPXXSPX*,XXSP93Not Applicable1Power is in percent of rated power, 3293Mwt.M=Master Manual Control ModeSP=Scram Possibility2Flow is in percent of rated flow, 102.5x105 lbs/hrA=Automatic Control ModeNC=Natural Circulation* = 90% rated powerL=Local Manual Control ModeSE=Scram Expected** = Actual test condition to be determinedX=Test independent of flow control mode.

BFN-16TABLE 13.5-5STARTUP TEST PROGRAM (UNIT 2)OPEN50% Flow Control Line75% Flow Control Line100% Flow Control LinePower, %1VESSEL15-3530-5040-60255337-5750-7065-853755-7570-9095-1005095-100Flow, %2ORHEAT4770104NC1164870102NC4870100NC109TEST CONDITION (See Figure 2)COLDTESTUP12D2E2A2F3C3D3E3A4C4D4E4A4F1Chemical & RadiochemicalXXXXXX2Radiation MeasurementsXXXXXX3Fuel LoadingX4Full Core Shutdown MarginX5CRDXXXXX6SRM Perf. & Control Rod Seq.XXX9Water Level MeasurementXXX10IRM CalibrationXXX11LPRM CalibrationXXXX12APRM CalibrationXXXXX13Process ComputerXXX6X14RCICXM15HPCIXXX16Selected Process TemperaturesXXXX17System ExpansionXXX18Core Power DistributionXXXX19Core PerformanceXXXXXXXXXXXXXX20Steam ProductionX21Flux Response to RodsMMMM22Press. Reg.: Setpoint ChangesMMMMMM  : Backup RegulatorMMMM23FW System: FW Pump TripM  : Water Level Stpt. Chg.M,AM,AM,AM,AM,AM,AM24Bypass ValvesM,AM,AXM,AMA,M,AM,AMM25Main Steam Iso. Valves: Each Vlv. X9M,SPM,SP  : Full Iso.M,SE26Relief Valve: CapacityM  : Actuation3X9MM27Turbine Trip andM,SE5 Generator Load RejectionM,SPM,SF529Flow ControlAAAAAAAAM,AM,A30Recirc. System : Trip One PumpM7,M8M7,M7M7,M7 Trip Both PumpsMM7M Sys. PerformanceXXXXXXXX Non-Cavit. Verif.X1231Loss of T-G & Offsite PowerM,SE532Recirc. MG Set Speed ControlL,MMMMMMMMMM33Turbine Stop Valve Surv. TestMMMM,SP1134Vibration Measurements 4X13XXXXXXXXXXXXX35Recirc. System Flow CalibrationXXX70Reactor Water Cleanup SystemX71Residual Heat Removal System**X72Drywell Atmosphere Cooling System10XX73Cooling Water Systems10XX74Offgas System*XXXX1Percent of rated power, 3293 Mwt7Included only to meet Test 34 RequirementsL= Local Manual Flow Control mode2Percent of rated flow, 102.5 x 106 lb/hr8Trip the Generator Field BreakerM= Master Manual Flow Control Mode3Also obtain data with Tests 25, Full Iso & Test 279Heat up tests of MSIVs & Relief Valves areA= Automatic flow Control Mode4Obtain data with test 30 to check operation onlyX=Test Independent of Flow Control Mode5Perform Test 5, timing of 4 slowest control rods10Unit II only (cf. Page 36)SP= Scram Possibility in conjunction with these scrams11Determine Maximum power without scramSE= Scram Expected6Perform the Dynamic System Test Case12From Test Condition 2E to 5NC= Natural Circulation13Not required if 50% power testing will be done within about 2 months*Applies to unit 3 and, subsequent to equipment installation, to unit 2.

BFN-16TABLE 13.5-6STARTUP TEST PROGRAM (UNIT 3)OPEN50% Flow Control Line75% Flow Control Line100% Flow Control LinePower, %1VESSEL15-3530-5040-602537-5750-7065-853755-7570-9095-10050Flow, %2ORHEAT4770104NC4870102NC4870100NCTEST CONDITION (See Figure 2)COLDTESTUP12D2E2A3C3D3E3A4C4D4E4A1Chemical & RadiochemicalXXXXXX2Radiation MeasurementXXXXXX3Fuel LoadingX4Full Core Shutdown MarginX5CRDXXX10X6SRM Perf. & Control Rod Seq.XXX9Water Level MeasurementXXX10IRM PerformanceXXX11LPRM CalibrationXXXX12APRM CalibrationXXXXX13Process ComputerXXX6X14RCICXX15HPCIXX16Selected Process TemperatureXX17System ExpansionXXX18Core Power DistributionXXXX19Core PerformanceXXXXXXXXXXX20Steam ProductionX21Flux Response to RodsXXXX22Press. Reg.: Setpoint ChangesXXXXXX  : Backup RegulatorXXXX23FW System: FW Pump TripX  : Water Level Stpt. Chg.XXXXXX24Bypass ValvesXXXXXXXX25Main Steam Iso. Valves: Each Vlv.X9X,SPX,SP  : Full Iso.X,SP26Relief Valve: CapacityX  : Actuations3X9XX27Turbine Trip andX,SE5 Generator Load RejectionX,SPX,SE530Recirc. System : Trip One PumpX7,X8X7,X7X7,X7 Trip Both PumpsXXX Sys. PerformanceXXXXX Non-Cavit. Verif.X1231Loss of T-G & Offsite PowerX,SE532Recirc. MG Set Speed ControlL,ML,ML,ML,ML,ML,ML,ML,ML,M33Turbine Stop Valve Surv. TestXXXX,SP1134Vibration Measurements 4X13XXXXXXXXXX35Recirc. System Flow CalibrationXXX70Reactor Water Cleanup SystemX71Residual Heat Removal SystemX72Drywell Atmospheric Cooling SystemXX73Cooling Water SystemsXX74Offgas SystemXXXX75Reactor Shutdown From Outside ControlRoomX141Percent of rated power, 3293 MWt7Included only to meet Test 34 RequirementsL= Local Manual Flow Control Mode2Percent of rated flow, 102.5 x 106 lb/hr8Trip the Generator Field BreakerM= Master Manual Flow Control Mode3Also obtain data with Tests 25, Full Iso & Test 279Heat up tests of MSIVs & Relief Valves areA= Automatic Flow Control Mode4Obtain data with Test 30 to check operation onlyx=Test Indepentent of Flow Control Mode5Perform Test 5, timing of 4 slowest control rods10RSCS cleared ( 40%)SP= Scram Possibility in conjunction with these scrams11Determine maximum power without scram SE= Scram Expected6Perform the Dynamic System Test Case12From Test Condition 2E to 5NC= Natural Circulation13Not required if 50% power testing will be done in about 2 months14At greater than 10% generator output