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| number = ML18024A309
| number = ML18024A309
| issue date = 10/05/2017
| issue date = 10/05/2017
| title = Browns Ferry Nuclear Plant Updated Final Safety Analysis Report (Ufsar), Amendment 27, 13.5 Table - Startup and Power Test Program
| title = Updated Final Safety Analysis Report (Ufsar), Amendment 27, 13.5 Table - Startup and Power Test Program
| author name =  
| author name =  
| author affiliation = Tennessee Valley Authority
| author affiliation = Tennessee Valley Authority
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=Text=
=Text=
{{#Wiki_filter:BFN-16 Table 13.5-1 CONTROL ROD DRIVE SYSTEM TESTS (Unit 1)                     Reactor Pressure,psig         Preop (With Core Loaded)
{{#Wiki_filter:BFN-16 Table 13.5-1 CONTROL ROD DRIVE SYSTEM TESTS (Unit 1)
Test Description         Tests          0                  600             800 1000 Position IndicationAllAll Normal Insert/Withdraw TimesAllAll        4*
Reactor Pressure,psig Preop                   (With Core Loaded)
CouplingAllAll Friction All           4*
Test Description                                               Tests       0           600         800       1000 Position Indication                                            All        All Normal Insert/Withdraw Times                                    All        All                                4*
Scram Times (Normal Accumulated Pressure)AllAll  4* 4*       All Scram Times (Minimum Accumulator Pressure)         4*
Coupling                                                        All        All Friction                                                                   All                                 4*
Scram Times (Zero Accumulator Pressure)           4*
Scram Times (Normal Accumulated Pressure)                       All        All          4*           4*       All Scram Times (Minimum Accumulator Pressure)                                                                 4*
Scram Times (Scram Discharge Volume
Scram Times (Zero Accumulator Pressure)                                                                         4*
 
Scram Times (Scram Discharge Volume High Level)                                                   All Scram Times, Rated Power (Normal Accumulator Pressure)                                                                                         4**
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.
  *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.
**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
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


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)
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    A    A  A  C  A Pressure Regulator Setpoint       C      A  C          A    A      C    A    C  C  C  A Pressure REgulator Backup Regulator                        C         C                      C                C Feedwater System Setpoint          C      A C         A    A      C    A    C  C  C  A  B Feedwater System Drop Heater                                                                                A Bypass Valve                       C      A  C   B    A    A      C    A    C  C  C  C  B Flow Control                      C      C  C          C    C      C          C  C  C NC= Natural Circulation A - unit 1 B - units 2, 3 C - units 1, 2, 3
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
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     3      2      2A    5A      5      4      4A    7A      7       6    6A    8 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        X      X      X    X        X      X     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                                                                          M                              M
: 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                                                      M                                                          M 39  Water Level verification in Reactor            X                  X                                                          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.


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)
BFN-16 TABLE 13.5-5 STARTUP TEST PROGRAM (UNIT 2)
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
OPEN                   50% Flow Control Line                         75% Flow Control Line                 100% Flow Control Line Power, %1                     VESSEL      15-35    30-50      40-60       25       53      37-57  50-70    65-85      37  55-75        70-90        95-100     50 95-100 Flow, %2                      OR    HEAT 47       70       104       NC       116     48     70     102       NC 48         70         100       NC   109 COLD  UP  1        2D        2E          2A        2F      3C      3D      3E        3A  4C          4D          4E          4A  4F TEST CONDITION (See Figure 2)                               TEST 1    Chemical & Radiochemical                                    X      X    X                    X                                               X                                       X 2    Radiation Measurements                                      X     X   X                   X                                              X                                        X 3    Fuel Loading                                                 X 4    Full Core Shutdown Margin                                   X 5    CRD                                                          X     X    X                    X                                                                                        X 6    SRM Perf. & Control Rod Seq.                                 X      X    X 9    Water Level Measurement                                             X   X                                                                                                             X 10    IRM Calibration                                              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   M 15    HPCI                                                                X                        X          X 16    Selected Process Temperatures                                       X                                    X                                             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            X          X    X 20    Steam Production                                                                                                                                                                       X 21    Flux Response to Rods                                                   M                   M                                               M                                       M 22    Press. Reg.: Setpoint Changes                                           M                   M                                               M             M            M            M
                  :  Backup Regulator M M M M23FW System:  FW Pump Trip MM                  :  Water Level Stpt. Chg.MAMMAMMMMAXMAMAMAX
: Backup Regulator                                           M                    M                                               M                                       M 23    FW System: FW Pump Trip                                                                                                                                                               M
                  :  Heater Loss M*24Bypass ValvesMAMAMAMMAMAMAXMAMAMAX25Main Steam Iso. Valves:  Each Vlv.
: Water Level Stpt. Chg.                                     M,A                 M,A                                             M,A            M,A          M,A          M,A             M 24    Bypass Valves                                                           M,A                  M,A        X                                  M,A            MA,         M,A          M,A        M    M 9
X M,SP M,SP M,SP                                      :  Full Iso.
25    Main Steam Iso. Valves: Each Vlv.                                   X                         M,SP                                                                       M,SP
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.
: Full Iso.                                                                                                                                                   M,SE 26    Relief Valve: Capacity                                                   M 3                                            9
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
: Actuation                                             X   M                                                                    M 5
* = 90% rated power L=Local Manual Control Mode SE=Scram Expected
27    Turbine Trip and                                                                                                                                                                       M,SE 5
** = Actual test condition to be determined X=Test independent of flow control mode.
Generator Load Rejection                                             M,SP                                                                                                         M,SF 29    Flow Control                                                            A        A          A                    A        A      A        A              A            M,A          M,A 7 8                                              7 7                                    7 7 30    Recirc. System : Trip One Pump                                                               M ,M                                           M ,M                                     M ,M 7
BFN-16TABLE 13.5-5 STARTUP TEST PROGRAM (UNIT 2)
Trip Both Pumps                                                             M                                              M                                        M Sys. Performance                                                          X          X        X                        X          X                            X          X    X 12 Non-Cavit. Verif.                                                           X 5
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)
31    Loss of T-G & Offsite Power                                             M,SE 32    Recirc. MG Set Speed Control                                            L,M      M          M                    M        M      M        M              M            M            M 11 33    Turbine Stop Valve Surv. Test                                           M                   M                                               M                                       M,SP 13 34    Vibration Measurements 4                                                 X         X          X          X        X        X      X        X          X  X            X            X          X    X 35    Recirc. System Flow Calibration                                                              X                                              X                                        X 70    Reactor Water Cleanup System                                       X 71    Residual Heat Removal System**                                           X 72    Drywell Atmosphere Cooling System 10                               X                                                                                                                 X 73    Cooling Water Systems 10                                           X                                                                                                                 X 74    Offgas System*                                                           X                   X                                               X                                       X 1                                                                                        7 2 Percent  of rated power, 3293 Mwt 6                                                    8Included only to meet Test 34 Requirements                                  L  = Local Manual Flow Control mode 3Percent of rated flow, 102.5 x 10 lb/hr                                                 9Trip the Generator Field Breaker                                            M  = Master Manual Flow Control Mode 4Also obtain data with Tests 25, Full Iso & Test 27                                         Heat up tests of MSIVs & Relief Valves are                                A  = Automatic flow Control Mode 5Obtain data with test 30                                                                 10 to check operation only                                                  X  =Test Independent of Flow Control Mode Perform Test 5, timing of 4 slowest control rods                                       11Unit II only (cf. Page 36)                                               SP   = Scram Possibility 6      in conjunction with these scrams                                                 12Determine Maximum power without scram                                    SE  = Scram Expected Perform the Dynamic System Test Case                                                   13From Test Condition 2E to 5                                              NC  = Natural Circulation Not required if 50% power testing will be done within about 2 months
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.
*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}}
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        2D        2E      2A      3C        3D    3E    3A    4C        4D        4E        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                          X9    X                                                  X 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      X        X        X      X        X    X          X        X          X        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 Room 1Percent of rated power, 3293 MWt                                  7 Included only to meet Test 34 Requirements              L = Local Manual Flow Control Mode 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 11 Determine maximum power without scram in conjunction with these scrams                                                                                          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 done in about 2 months 14 At greater than 10% generator output}}

Latest revision as of 02:12, 22 October 2019

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 13.5 Table - Startup and Power Test Program
ML18024A309
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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 A A A C A Pressure Regulator Setpoint C A C A A C A C C C A Pressure REgulator Backup Regulator C C C C Feedwater System Setpoint C A C A A C A C C C A B Feedwater System Drop Heater A Bypass Valve C A C B A A C A C C C C B Flow Control C C C C C C C C C 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 3 2 2A 5A 5 4 4A 7A 7 6 6A 8 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 X X X X X X 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 M M
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 M M 39 Water Level verification in Reactor X X 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 13.5-5 STARTUP TEST PROGRAM (UNIT 2)

OPEN 50% Flow Control Line 75% Flow Control Line 100% Flow Control Line Power, %1 VESSEL 15-35 30-50 40-60 25 53 37-57 50-70 65-85 37 55-75 70-90 95-100 50 95-100 Flow, %2 OR HEAT 47 70 104 NC 116 48 70 102 NC 48 70 100 NC 109 COLD UP 1 2D 2E 2A 2F 3C 3D 3E 3A 4C 4D 4E 4A 4F TEST CONDITION (See Figure 2) TEST 1 Chemical & Radiochemical X X X X X X 2 Radiation Measurements X X X X X X 3 Fuel Loading X 4 Full Core Shutdown Margin X 5 CRD X X X X X 6 SRM Perf. & Control Rod Seq. X X X 9 Water Level Measurement X X X 10 IRM Calibration 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 M 15 HPCI X X X 16 Selected Process Temperatures X X 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 X X X 20 Steam Production X 21 Flux Response to Rods M M M M 22 Press. Reg.: Setpoint Changes M M M M M M

Backup Regulator M M M M 23 FW System: FW Pump Trip M
Water Level Stpt. Chg. M,A M,A M,A M,A M,A M,A M 24 Bypass Valves M,A M,A X M,A MA, M,A M,A M M 9

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

Full Iso. M,SE 26 Relief Valve: Capacity M 3 9
Actuation X M M 5

27 Turbine Trip and M,SE 5

Generator Load Rejection M,SP M,SF 29 Flow Control A A A A A A A A M,A M,A 7 8 7 7 7 7 30 Recirc. System : Trip One Pump M ,M M ,M M ,M 7

Trip Both Pumps M M M Sys. Performance X X X X X X X X 12 Non-Cavit. Verif. X 5

31 Loss of T-G & Offsite Power M,SE 32 Recirc. MG Set Speed Control L,M M M M M M M M M M 11 33 Turbine Stop Valve Surv. Test M M M M,SP 13 34 Vibration Measurements 4 X X X X X X X X X X X X X X 35 Recirc. System Flow Calibration X X X 70 Reactor Water Cleanup System X 71 Residual Heat Removal System** X 72 Drywell Atmosphere Cooling System 10 X X 73 Cooling Water Systems 10 X X 74 Offgas System* X X X X 1 7 2 Percent of rated power, 3293 Mwt 6 8Included only to meet Test 34 Requirements L = Local Manual Flow Control mode 3Percent of rated flow, 102.5 x 10 lb/hr 9Trip the Generator Field Breaker M = Master Manual Flow Control Mode 4Also obtain data with Tests 25, Full Iso & Test 27 Heat up tests of MSIVs & Relief Valves are A = Automatic flow Control Mode 5Obtain data with test 30 10 to check operation only X =Test Independent of Flow Control Mode Perform Test 5, timing of 4 slowest control rods 11Unit II only (cf. Page 36) SP = Scram Possibility 6 in conjunction with these scrams 12Determine Maximum power without scram SE = Scram Expected Perform the Dynamic System Test Case 13From Test Condition 2E to 5 NC = Natural Circulation 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-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 2D 2E 2A 3C 3D 3E 3A 4C 4D 4E 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 X9 X X 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 X X X X X X X X X 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 Room 1Percent of rated power, 3293 MWt 7 Included only to meet Test 34 Requirements L = Local Manual Flow Control Mode 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 11 Determine maximum power without scram in conjunction with these scrams 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 done in about 2 months 14 At greater than 10% generator output
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