ML18024A309

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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Text

BFN-16 Table 13.5-1 CONTROL ROD DRIVE SYSTEM TESTS (Unit 1) Reactor Pressure,psig Preop (With Core Loaded)

Test Description Tests 0 600 800 1000 Position IndicationAllAll Normal Insert/Withdraw TimesAllAll 4*

CouplingAllAll Friction All 4*

Scram Times (Normal Accumulated Pressure)AllAll 4* 4* All Scram Times (Minimum Accumulator Pressure) 4*

Scram Times (Zero Accumulator Pressure) 4*

Scram Times (Scram Discharge Volume

High Level)

All Scram 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 reactor pressure 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 reactor scrams at these power levels.

Table 13.5-2 MAJOR PLANT TRANSIENTS

TEST CONDITION Nominal Power, Percent of Rated 2550 7580 100 Nominal Core Flow, Percent of Rated TEST TITLE 36 100 100 70 100 Feedwater Pump Trip A C Main Steam Isolation Valves (One Valve)CAC Main Steam Isolation Valves (All Valves)

C Turbine-Generator Stop Valve Fast Close B ATurbine-Generator Contorl Valve

Fast Close AAA Recirculation Pump Trip (One Pump) CB C Recirculation Pump Trip (Two Pumps)CC C Loss of Generator and Offsite Power CA - Unit 1 B - Units 2, 3 C - Units 1, 2, 3 BFN-16 Table 13.5-3 STABILITY TESTS TEST CONDITION Nominal Power, Percent of Rated 254050 254760753765801005097 Nominal Core Flow, Percent of Rated TEST TITLE47 70 100 NC 48 70 100 NC 48 70 100 NC 109 Flux Response to RodsCACAACAAACAPressure Regulator SetpointCACAACA CCCAPressure REgulator Backup RegulatorCC C CFeedwater System SetpointCACAACACCCAB Feedwater System Drop

Heater A Bypass ValveCAC BAACA CCCCB Flow ControlCCC CCCCCC NC= Natural Circulation A - unit 1 B - units 2, 3 C - units 1, 2, 3 BFN-16 TABLE 13.5-4 STARTUP TEST PROGRAM (UNIT 1)

OPEN 50% Flow Line 75% Flow Line 100% Flow Line Power 1 .%VESSHEAT15-3530-5040-6015-3537-5750-7065-8527-4755-7570-9095-10040-60 20%Flow 2.%ORUP 48 70 104NC4870 102 NC 48 70100NC105%TEST CONDITION (See Figure 13.5-2)COLD TEST1322A5A544A7A766A81Chemical & RadiochemicalXXX X X X2Radiation MeasurementsXXX X X3Fuel Loading X4Full Core Shutdown Margin X5Control Rod Drive SystemXXX X X6SRM Performance & Control Rod SequenceXXX X X7Not Applicable8Not Applicable9Not Applicable10IRM CalibrationXXX11LPRM Calibration X X X X12APRM CalibrationXX X X X X13Process ComputerXXX X14RCIC SystemXM15HPCI System X M16Reactor Vessel Temperature X X X X17System ExpansionXXX18Core Power Distribution X X X X X19Core PerformanceXXXXXXXXXXXXX20Elec. Output & Heat Rate X21Flux Response to RodsMMMMMMMXMMMX22Press. Reg.: Setpoint ChangesMMMMMMMXMMMX

Backup Regulator M M M M23FW System: FW Pump Trip MM  : Water Level Stpt. Chg.MAMMAMMMMAXMAMAMAX

Heater Loss M*24Bypass ValvesMAMAMAMMAMAMAXMAMAMAX25Main Steam Iso. Valves: Each Vlv.

X M,SP M,SP M,SP  : Full Iso.

M,SE26Relief ValvesXM M,SE M27Turbine : Stop Valve Trip M,SE  : Control Valve Trip M,SP M,SE A,SE29Flow ControlLMAMAMAMAMAMAMAMAMA30Recirc. System: One Pump Trip M M  : Two Pump Trip M M M  : Flow Calibration XXX X X X31Loss of T-G & Offsite Power M,SE LSE32Recirc. Loop ControlXXXX35Recirc. And Jet Pump Calibration X36Equalizer Open MM39Water Level verification in Reactor Vessel XX X70Reactor Water Cleanup System X71Residual Heat Removal System**72Drywell Atmosphere Cooling System X X73Cooling Water Systems X X90Vibration**XXX X X X92Steam Separator and DryerXXXSPX XSP X*,X XSP93Not Applicable 1 Power is in percent of rated power, 3293Mwt.

M=Master Manual Control Mode SP=Scram Possibility 2 Flow is in percent of rated flow, 102.5x10 5 lbs/hr A=Automatic Control Mode NC=Natural Circulation

• = 90% rated power L=Local Manual Control Mode SE=Scram Expected

• • = Actual test condition to be determined X=Test independent of flow control mode.

BFN-16TABLE 13.5-5 STARTUP TEST PROGRAM (UNIT 2)

OPEN 50% Flow Control Line 75% Flow Control Line 100% Flow Control Line Power, %1 VESSEL15-3530-5040-60 25 5337-5750-7065-853755-7570-9095-100 50 95-100 Flow, %2ORHEAT 47 70 104 NC 116 48 70 102 NC 48 70 100 NC 109 TEST CONDITION (See Figure 2)

COLD TESTUP12D2E2A2F3C3D3E3A4C4D4E4A4F1Chemical & RadiochemicalXX X X X X2Radiation MeasurementsXX X X X X3Fuel Loading X4Full Core Shutdown Margin X5CRDXX X X X6SRM Perf. & Control Rod Seq.XX X9Water Level Measurement X X X10IRM CalibrationXX X11LPRM Calibration X X X X12APRM Calibration X X X X X13Process ComputerXX X6 X14RCIC X M15HPCI XXX16Selected Process Temperatures X X X X17System ExpansionXX X18Core Power Distribution X X X X19Core PerformanceXXXXXXXXXXXXXX20Steam Production X21Flux Response to Rods M M M M22Press. Reg.: Setpoint Changes M M MMM M  : Backup Regulator M M M M23FW System: FW Pump Trip M  : Water Level Stpt. Chg.

M,A M,A M,AM,AM,AM,A M24Bypass Valves M,AM,AX M,AMA,M,AM,AMM25Main Steam Iso. Valves: Each Vlv.

X 9 M,SP M,SP  : Full Iso.

M,SE26Relief Valve: Capacity M  : Actuation 3 X 9 M M27Turbine Trip and M,SE 5 Generator Load Rejection M,SP M,SF 529Flow ControlAAAAAAAAM,AM,A30Recirc. System : Trip One Pump M 7 ,M 8 M 7 ,M 7 M 7 ,M 7 Trip Both Pumps MM 7 M Sys. PerformanceXXXXXXXX Non-Cavit. Verif.

X 1231Loss of T-G & Offsite Power M,SE 532Recirc. MG Set Speed ControlL,MMMMMMMMM M33Turbine Stop Valve Surv. Test M M M M,SP 1134Vibration Measurements 4 X 13XXXXXXXXXXXXX35Recirc. System Flow CalibrationXXX70Reactor Water Cleanup System X71Residual Heat Removal System**

X72Drywell Atmosphere Cooling System 10 X X73Cooling Water Systems 10 X X74Offgas System*

X X X X 1Percent of rated power, 3293 Mwt 7 Included only to meet Test 34 RequirementsL= Local Manual Flow Control mode 2 Percent of rated flow, 102.5 x 10 6 lb/hr 8 Trip the Generator Field BreakerM= Master Manual Flow Control Mode 3Also obtain data with Tests 25, Full Iso & Test 27 9 Heat up tests of MSIVs & Relief Valves areA= Automatic flow Control Mode 4 Obtain data with test 30 to check operation onlyX=Test Independent of Flow Control Mode 5 Perform Test 5, timing of 4 slowest control rods 10 Unit II only (cf. Page 36)SP= Scram Possibility in conjunction with these scrams 11 Determine Maximum power without scramSE= Scram Expected 6 Perform the Dynamic System Test Case 12 From Test Condition 2E to 5NC= Natural Circulation 13 Not 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 13.5-6 STARTUP TEST PROGRAM (UNIT 3)

OPEN50% Flow Control Line75% Flow Control Line 100% Flow Control Line Power, %1 VESSEL15-3530-5040-60 2537-5750-7065-853755-7570-9095-100 50 Flow, %2ORHEAT 47 70 104 NC 48 70 102 NC 48 70 100 NC TEST CONDITION (See Figure 2)

COLD TESTUP12D2E2A3C3D3E3A4C4D4E4A1Chemical & RadiochemicalXXX X X X2Radiation MeasurementXXX X X X3Fuel Loading X4Full Core Shutdown Margin X5CRDXXX 10 X6SRM Perf. & Control Rod Seq.XXX9Water Level MeasurementXX X10IRM PerformanceXXX11LPRM Calibration X X X X12APRM CalibrationXX X X X13Process ComputerXX X 6 X14RCICXX15HPCI X X16Selected Process Temperature X X17System ExpansionXXX18Core Power Distribution X X X X19Core PerformanceXXXXXXXXXXX20Steam Production X21Flux Response to Rods X X X X22Press. Reg.: Setpoint Changes X X XXXX  : Backup Regulator X X X X23FW System: FW Pump Trip X  : Water Level Stpt. Chg.

X X XXXX24Bypass Valves XXX XXXXX25Main Steam Iso. Valves: Each Vlv.

X 9 X,SP X,SP  : Full Iso.

X,SP26Relief Valve: Capacity X  : Actuations 3 X 9 XX27Turbine Trip and X,SE 5 Generator Load Rejection X,SP X,SE 530Recirc. System : Trip One Pump X 7 ,X 8 X 7 ,X 7 X 7 ,X 7 Trip Both Pumps X X X Sys. PerformanceXX XXX Non-Cavit. Verif.

X 1231Loss of T-G & Offsite Power X,SE 532Recirc. MG Set Speed ControlL,ML,ML,ML,ML,ML,ML,ML,ML,M33Turbine Stop Valve Surv. Test X X X X,SP 1134Vibration Measurements 4 X 13XXXXXXXXXX35Recirc. System Flow Calibration X X X70Reactor Water Cleanup System X71Residual Heat Removal System X72Drywell Atmospheric Cooling System X X73Cooling Water Systems X X74Offgas System X X X X75Reactor Shutdown From Outside Control Room X 14 1 Percent of rated power, 3293 MWt 7 Included only to meet Test 34 RequirementsL= Local Manual Flow Control Mode 2 Percent of rated flow, 102.5 x 10 6 lb/hr 8 Trip the Generator Field BreakerM= Master Manual Flow Control Mode 3Also obtain data with Tests 25, Full Iso & Test 27 9 Heat up tests of MSIVs & Relief Valves areA= Automatic Flow Control Mode 4 Obtain data with Test 30 to check operation onlyx=Test Indepentent of Flow Control Mode 5 Perform Test 5, timing of 4 slowest control rods 10 RSCS cleared ( 40%)SP= Scram Possibility in conjunction with these scrams 11 Determine maximum power without scram SE= Scram Expected 6 Perform the Dynamic System Test Case 12 From Test Condition 2E to 5NC= Natural Circulation 13Not required if 50% power testing will be

done in about 2 months 14 At greater than 10% generator output