ML21286A543

Amendment 29 to Updated Final Safety Analysis Report, Chapter 13, Table 13.5, Startup and Power Test Program

ML21286A543
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Site:	Browns Ferry
Issue date:	10/04/2021
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 Indication All All Normal Insert/Withdraw Times All All 4*

Coupling All All Friction All 4*

Scram Times (Normal Accumulated Pressure) All All 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 25 50 75 80 100 Nominal Core Flow, Percent of Rated TEST TITLE 36 100 100 70 100

Feedwater Pump Trip A C Main Steam Isolation Valves (One Valve) C A C Main Steam Isolation Valves (All Valves) C Turbine-Generator Stop Valve Fast Close B A Turbine-Generator Contorl Valve Fast Close A A A Recirculation Pump Trip (One Pump) C B C Recirculation Pump Trip (Two Pumps) C C C Loss of Generator and Offsite Power C

A - 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 25 40 50 25 47 60 75 37 65 80 100 50 97 Nominal Core Flow, Percent of Rated TEST TITLE 47 70 100 NC 48 70 100 NC 48 70 100 NC 109

Flux Response to Rods C A C A A C AAACA Pressure Regulator Setpoint C A C A A C A CCCA Pressure REgulator Backup Regulator C C C C Feedwater System Setpoint C A C A A C A CCCAB Feedwater System Drop Heater A Bypass Valve C A C BAACACCCCB Flow Control CCC CCC CCC

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 Power1.% VESS HEAT 15-35 30-50 40-60 15-35 37-57 50-70 65-85 27-47 55-75 70-90 95-100 40-60 20%

Flow2.% OR UP 48 70 104 NC 48 70 102 NC 48 70 100 NC 105%

TEST CONDITION (See Figure 13.5-2) COLD 1 322A5A544A7A76 6A8 TEST 1 Chemical & Radiochemical X X X X X X 2 Radiation Measurements X X X X X 3 Fuel Loading X 4 Full Core Shutdown Margin X 5 Control Rod Drive System X X X X X 6 SRM Performance & Control Rod Sequence X X X X X 7 Not Applicable 8 Not Applicable 9 Not Applicable 10 IRM Calibration X X X 11 LPRM Calibration X X X X 12 APRM Calibration X X X X X X 13 Process Computer X X X X 14 RCIC System X M 15 HPCI System X M 16 Reactor Vessel Temperature X X X X 17 System Expansion X X X 18 Core Power Distribution X X X X X 19 Core Performance X X X X X XXXX XX X X 20 Elec. Output & Heat Rate X 21 Flux Response to Rods M M M M M M M X M M M X 22 Press. Reg.: Setpoint Changes M M M M M M M X M M M X

Backup Regulator M M M M 23 FW System: FW Pump Trip MM

Water Level Stpt. Chg. MA M MA M M M MA X MA MA MA X

Heater Loss M*

24 Bypass Valves MA MA MA M MA MA MA X MA MA MA X 25 Main Steam Iso. Valves: Each Vlv. X M,SP M,SP M,SP

Full Iso. M,SE 26 Relief Valves X M M,SE M 27 Turbine : Stop Valve Trip M,SE

Control Valve Trip M,SP M,SE A,SE 29 Flow Control LMA MA MA MA MA MA MA MA MA 30 Recirc. System: One Pump Trip M M

Two Pump Trip M M M

Flow Calibration X X X X X X 31 Loss of T-G & Offsite Power M,SE LSE 32 Recirc. Loop Control X X X X 35 Recirc. And Jet Pump Calibration X 36 Equalizer Open MM 39 Water Level verification in Reactor XX X Vessel 70 Reactor Water Cleanup System X 71 Residual Heat Removal System**

72 Drywell Atmosphere Cooling System X X 73 Cooling Water Systems X X 90 Vibration** X X X X X X 92 Steam Separator and Dryer X X XSP X XSP X*,X XSP 93 Not Applicable 1Power is in percent of rated power, 3293Mwt. M=Master Manual Control Mode SP=Scram Possibility 2Flow is in percent of rated flow, 102.5x105 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-16

TABLE 13.5-6

STARTUP TEST PROGRAM (UNIT 3)

OPEN 50% Flow Control Line 75% Flow Control Line 100% Flow Control Line Power, %1 VESSEL 15-35 30-50 40-60 25 37-57 50-70 65-85 37 55-75 70-90 95-100 50 Flow, %2 OR HEAT 47 70 104 NC 48 70 102 NC 48 70 100 NC COLD UP 1 2D2E2A3C3D3E 3A4C 4D4E 4A TEST CONDITION (See Figure 2) TEST 1 Chemical & Radiochemical X X X X X X 2 Radiation Measurement X X X X X X 3 Fuel Loading X 4 Full Core Shutdown Margin X 5 CRD X X X10 X 6 SRM Perf. & Control Rod Seq. X X X 9 Water Level Measurement X X X 10 IRM Performance X X X 11 LPRM Calibration X X X X 12 APRM Calibration X X X X X 13 Process Computer X X X6 X 14 RCIC X X 15 HPCI X X 16 Selected Process Temperature X X 17 System Expansion X X X 18 Core Power Distribution X X X X 19 Core Performance X X X X X X X X X X X 20 Steam Production X 21 Flux Response to Rods X X X X 22 Press. Reg.: Setpoint Changes X X X X X X

Backup Regulator X X X X 23 FW System: FW Pump Trip X

Water Level Stpt. Chg. X X X X X X 24 Bypass Valves X X X X X X X X 25 Main Steam Iso. Valves: Each Vlv. X9 X,SP X,SP

Full Iso. X,SP 26 Relief Valve: Capacity X

Actuations3 X9XX 27 Turbine Trip and X,SE5 Generator Load Rejection X,SP X,SE5 30 Recirc. System : Trip One Pump X7,X8 X7,X7 X7,X7 Trip Both Pumps X X X Sys. Performance X X X X X Non-Cavit. Verif. X12 31 Loss of T-G & Offsite Power X,SE5 32 Recirc. MG Set Speed Control L,M L,M L,M L,M L,M L,M L,M L,M L,M 33 Turbine Stop Valve Surv. Test X X X X,SP11 34 Vibration Measurements 4 X13 XXXXXX X XX X 35 Recirc. System Flow Calibration X X X 70 Reactor Water Cleanup System X 71 Residual Heat Removal System X 72 Drywell Atmospheric Cooling System X X 73 Cooling Water Systems X X 74 Offgas System X X X X 75 Reactor Shutdown From Outside Control X14 1Percent of rated power, 3293 MWt 7 Included only to meet Test 34 Requirements L = Local Manual Flow Control ModeRoom 2Percent of rated flow, 102.5 x 10 6 lb/hr 8 Trip the Generator Field Breaker M = Master Manual Flow Control Mode 3Also obtain data with Tests 25, Full Iso & Test 27 9 Heat up tests of MSIVs & Relief Valves are A = Automatic Flow Control Mode 4Obtain data with Test 30 to check operation only x =Test Indepentent of Flow Control Mode 5Perform 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 6Perform the Dynamic System Test Case 12 From Test Condition 2E to 5 NC = Natural Circulation 13 Not required if 50% power testing will be 14 At greater than 10% generator output done in about 2 months