ML18024A309

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

ML18024A309
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Site:	Browns Ferry
Issue date:	10/05/2017
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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BFN-16Table 13.5-1 CONTROL 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* All Scram 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 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 CMain Steam Isolation Valves (One Valve)CACMain Steam Isolation Valves (All Valves)

CTurbine-Generator Stop Valve Fast Close BATurbine-Generator Contorl Valve

Fast Close AAARecirculation 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-16Table 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 RegulatorCCCCFeedwater System SetpointCACAACACCCABFeedwater System Drop

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

OPEN50% Flow Line 75% Flow Line 100% Flow Line Power1 .%VESSHEAT15-3530-5040-6015-3537-5750-7065-8527-4755-7570-9095-10040-6020%Flow2.%ORUP4870104NC4870102NC4870100NC105%TEST CONDITION (See Figure 13.5-2)COLD TEST1322A5A544A7A766A81Chemical & RadiochemicalXXXXXX2Radiation MeasurementsXXXXX3Fuel Loading X4Full Core Shutdown Margin X5Control Rod Drive SystemXXXXX6SRM Performance & Control Rod SequenceXXX XX7Not Applicable8Not Applicable9Not Applicable10IRM CalibrationXXX11LPRM Calibration XXXX12APRM CalibrationXXXXXX13Process ComputerXXXX14RCIC SystemXM15HPCI System XM16Reactor Vessel Temperature XXXX17System ExpansionXXX18Core Power Distribution XXXXX19Core PerformanceXXXXXXXXXXXXX20Elec. Output & Heat Rate X21Flux Response to RodsMMMMMMMXMMMX22Press. Reg.: Setpoint ChangesMMMMMMMXMMMX

Backup Regulator MMMM23FW System: FW Pump Trip MM  : Water Level Stpt. Chg.MAMMAMMMMAXMAMAMAX

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

XM,SPM,SPM,SP  : Full Iso.

M,SE26Relief ValvesXMM,SEM27Turbine : Stop Valve Trip M,SE  : Control Valve Trip M,SPM,SEA,SE29Flow ControlLMAMAMAMAMAMAMAMAMA30Recirc. System: One Pump Trip MM  : Two Pump Trip MMM  : Flow Calibration XXXXXX31Loss of T-G & Offsite Power M,SELSE32Recirc. Loop ControlXXXX35Recirc. And Jet Pump Calibration X36Equalizer Open MM39Water Level verification in Reactor VesselXXX70Reactor Water Cleanup System X71Residual Heat Removal System**72Drywell Atmosphere Cooling System XX73Cooling Water Systems XX90Vibration**XXXXXX92Steam Separator and DryerXXXSPXXSPX*,XXSP93Not Applicable 1Power is in percent of rated power, 3293Mwt.

M=Master Manual Control Mode SP=Scram Possibility 2Flow is in percent of rated flow, 102.5x10 5 lbs/hrA=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)

OPEN50% Flow Control Line 75% Flow Control Line 100% Flow Control Line Power, %1 VESSEL15-3530-5040-60255337-5750-7065-853755-7570-9095-1005095-100Flow, %2ORHEAT4770104NC1164870102NC4870100NC109TEST CONDITION (See Figure 2)

COLDTESTUP12D2E2A2F3C3D3E3A4C4D4E4A4F1Chemical & RadiochemicalXXXXXX2Radiation MeasurementsXXXXXX3Fuel Loading X4Full Core Shutdown Margin X5CRDXXXXX6SRM Perf. & Control Rod Seq.XXX9Water Level Measurement XXX10IRM CalibrationXXX11LPRM Calibration XXXX12APRM Calibration XXXXX13Process ComputerXXX6X14RCICXM15HPCIXXX16Selected Process Temperatures XXXX17System ExpansionXXX18Core Power Distribution XXXX19Core PerformanceXXXXXXXXXXXXXX20Steam Production X21Flux Response to Rods MMMM22Press. Reg.: Setpoint Changes MMMMMM  : Backup Regulator MMMM23FW System: FW Pump Trip M  : Water Level Stpt. Chg.

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

X9M,SPM,SP  : Full Iso.

M,SE26Relief Valve: Capacity M  : Actuation 3X9MM27Turbine Trip and M,SE5 Generator Load Rejection M,SPM,SF529Flow ControlAAAAAAAAM,AM,A30Recirc. System : Trip One Pump M7,M8M7,M7M7,M7 Trip Both Pumps MM7M Sys. PerformanceXXXXXXXX Non-Cavit. Verif.

X1231Loss of T-G & Offsite Power M,SE532Recirc. MG Set Speed ControlL,MMMMMMMMMM33Turbine Stop Valve Surv. Test MMMM,SP1134Vibration Measurements 4 X13XXXXXXXXXXXXX35Recirc. System Flow CalibrationXXX70Reactor Water Cleanup System X71Residual Heat Removal System**

X72Drywell Atmosphere Cooling System 10XX73Cooling Water Systems 10XX74Offgas System*

XXXX1Percent of rated power, 3293 Mwt 7Included only to meet Test 34 RequirementsL= Local Manual Flow Control mode 2Percent of rated flow, 102.5 x 10 6 lb/hr8Trip the Generator Field BreakerM= Master Manual Flow Control Mode 3Also obtain data with Tests 25, Full Iso & Test 27 9Heat up tests of MSIVs & Relief Valves areA= Automatic flow Control Mode 4Obtain data with test 30 to check operation onlyX=Test Independent of Flow Control Mode 5Perform Test 5, timing of 4 slowest control rods 10Unit II only (cf. Page 36)SP= Scram Possibility in conjunction with these scrams 11Determine Maximum power without scramSE= Scram Expected 6Perform the Dynamic System Test Case 12From Test Condition 2E to 5NC= Natural Circulation 13Not 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 VESSEL15-3530-5040-602537-5750-7065-853755-7570-9095-10050Flow, %2ORHEAT4770104NC4870102NC4870100NCTEST CONDITION (See Figure 2)

COLDTESTUP12D2E2A3C3D3E3A4C4D4E4A1Chemical & RadiochemicalXXXXXX2Radiation MeasurementXXXXXX3Fuel Loading X4Full Core Shutdown Margin X5CRDXXX10X6SRM Perf. & Control Rod Seq.XXX9Water Level MeasurementXXX10IRM PerformanceXXX11LPRM Calibration XXXX12APRM CalibrationXXXXX13Process ComputerXXX6X14RCICXX15HPCIXX16Selected Process Temperature XX17System ExpansionXXX18Core Power Distribution XXXX19Core PerformanceXXXXXXXXXXX20Steam Production X21Flux Response to Rods XXXX22Press. Reg.: Setpoint Changes XXXXXX  : Backup Regulator XXXX23FW System: FW Pump Trip X  : Water Level Stpt. Chg.

XXXXXX24Bypass Valves XXXXXXXX25Main Steam Iso. Valves: Each Vlv.

X9X,SPX,SP  : Full Iso.

X,SP26Relief Valve: Capacity X  : Actuations 3X9XX27Turbine Trip and X,SE5 Generator Load Rejection X,SPX,SE530Recirc. System : Trip One Pump X7,X8X7,X7X7,X7 Trip Both Pumps XXX Sys. PerformanceXXXXX Non-Cavit. Verif.

X1231Loss of T-G & Offsite Power X,SE532Recirc. MG Set Speed ControlL,ML,ML,ML,ML,ML,ML,ML,ML,M33Turbine Stop Valve Surv. Test XXXX,SP1134Vibration Measurements 4X13XXXXXXXXXX35Recirc. System Flow Calibration XXX70Reactor Water Cleanup System X71Residual Heat Removal System X72Drywell Atmospheric Cooling System XX73Cooling Water Systems XX74Offgas System XXXX75Reactor Shutdown From Outside Control RoomX141Percent of rated power, 3293 MWt 7Included only to meet Test 34 RequirementsL= Local Manual Flow Control Mode 2Percent of rated flow, 102.5 x 10 6 lb/hr8Trip the Generator Field BreakerM= Master Manual Flow Control Mode 3Also obtain data with Tests 25, Full Iso & Test 27 9Heat up tests of MSIVs & Relief Valves areA= Automatic Flow Control Mode 4Obtain data with Test 30 to check operation onlyx=Test Indepentent of Flow Control Mode 5Perform Test 5, timing of 4 slowest control rods 10RSCS cleared ( 40%)SP= Scram Possibility in conjunction with these scrams 11Determine maximum power without scram SE= Scram Expected 6Perform the Dynamic System Test Case 12From Test Condition 2E to 5NC= Natural Circulation 13Not required if 50% power testing will be

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