ML18018A792

Updated Final Safety Analysis Report (Ufsar), Amendment 27, 1.7 Table - Comparison of Principal Design Characteristics

ML18018A792
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-17 TABLE 1.7-1 (Sheet 1)

COMPARISON OF NUCLEAR SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

(Parameters are related to Rated Power Output for a single plant unless otherwise noted)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD THERMAL AND HYDRAULIC DESIGN UNITS 1/2/3 HATCH UNIT 1 YANKEE STATION ENERGY CENTER Rated Power, MWt 3293 2436 1593 2381 1593 Design Power, MWt 3440 2537 1665 2500 1670 Steam Flow Rate, lb/hr 13.37 x 106 10.03 x 106 6.43 x 106 9.81 x 106 6.847 x 106 Core Coolant Flow Rate, lb/hr 102.5 x 106 75.5 x 106 48.5 x 106 74.5 x 106 48.5 x 106 Feedwater Flow Rate, lb/hr 13.315 x 106 10.445 x 106 6.43 x 106 9.81 x 106 6.77 x 106 Feedwater Temperature, °F 378.4 387.4 372 367 420 System Pressure, Nominal in Steam Dome, psia 1020 1020 1020 1020 1020 Average Power Density, kW/liter 49.69/49.46/ 51.2 50.8 51.2 50.9 49.2 Maximum Thermal Output, kW/ft 18.5 (7x7)/13.4 18.3 18.37 18.5 18.5 (8x8)

Average Thermal Output, kW/ft 7.050 (7x7)/ 7.114 7.1 7.079 7.079 5.59 (8x8)

Average Heat Flux, Btu/hr-ft2 148937/142007/ 164,734 163,900 164,500 163,933 143635 Maximum UO2 Temperature, °F 4430 4430 4430 4430 4430 Average Volumetric Fuel Temperature, °F 1210 1210 1210 1210 1210 Average Fuel Rod Surface Temperature, °F 560 560 560 560 560 Minimum Critical Power Ratio (MCPR)(1) >1.07 >1.9 >1.9 >1.9 >1.9 Coolant Enthalpy at Core Inlet, Btu/lb 521.3 526.2 522.9 520.1 525.6 Core Maximum Exit Voids Within Assemblies 79 79 79 79 79 Core Average Exit Quality, % Steam 13.2 13.9 13.6 13.2 14.3

BFN-17 TABLE 1.7-1 (Sheet 2)

COMPARISON OF NUCLEAR SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

(Parameters are related to Rated Power Output for a single plant unless otherwise noted)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD THERMAL AND HYDRAULIC DESIGN (Cont-d) UNITS 1/2/3 HATCH UNIT 1 YANKEE STATION ENERGY CENTER Design Power Peaking Factors Transverse Peaking Factor 1.4 1.4 1.4 1.4 1.405 Local Peaking Factor 1.24 1.24 1.24 1.24 1.24 Axial Peaking Factor 1.5 1.5 1.5 1.5 1.5 Total Peaking Factor 2.63 2.6 2.6 2.6 2.6 NUCLEAR DESIGN (First Core)

Water/UO2 Volume Ratio (Cold) 2.43 Type I 2.41 2.41 2.41 2.41 2.53 Type II & III Reactivity with Strongest Control Rod <0.99 <0.99 <0.99 <0.99 <0.99 Out, keff Moderator Temperature Coefficient At 68°F, k/k - °F Water -3.5 x 10-5 -3.5 x 10-5 -5.0 x 10-5 -3.5 x 10-5 -3.5 x 10-5 Hot, no voids, k/k - °F Water -11.6 x 10-5 -11.6 x 10-5 -17.0 x 10-5 -11.6 x 10-5 -11.6 x 10-5 Moderator Void Coefficient Hot, no voids, k/k - % Void -8.7 x 10-4 -8.7 x 10-4 -1.0 x 10-3 -8.7 x 10-4 -8.7 x 10-4 At Rated Output, k/k - % Void -1.05 x 10-3 -1.05 x 10-3 -1.5 x 10-3 -1.05 x 10-3 -1.05 x 10-3 Fuel Temperature Doppler Coefficient At 68°F, k/k - °F Fuel -0.9 x 10-5 -1.3 x 10-5 -1.3 x 10-5 -1.3 x 10-5 -1.3 x 10-5 Hot, No Void, k/k - °F Fuel -1.0 x 10-5 -1.2 x 10-5 -1.2 x 10-5 -1.2 x 10-5 -1.2 x 10-5 At Rated Output, k/k - °F Fuel -0.9 x 10-5 -1.3 x 10-5 -1.3 x 10-5 -1.3 x 10-5 -1.3 x 10-5 Initial Average U-235 Enrichment, W/O 2.19% 2.30% 2.50% 2.15% 2.25%

Fuel Average Discharge Exposure, MWD/Ton 19,000 19,000 19,000 19,000 18,350 (6)

Nuclear Design (Reload Core) See applicable Nuclear Design Reports.

BFN-17 TABLE 1.7-1 (Sheet 3)

COMPARISON OF NUCLEAR SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

(Parameters are related to Rated Power Output for a single plant unless otherwise noted)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD CORE MECHANICAL DESIGN UNITS 1/2/3 HATCH UNIT 1 YANKEE STATION ENERGY CENTER Fuel Assembly Number of Fuel Assemblies 764 560 368 548 368 Fuel Rod Array 7 x 7 or 8 x 8 7x7 7x7 7x7 7x7 Overall Dimensions, inches 175.98 175.98 175.98 175.98 175.98 Weight of UO2 per Assembly, pounds See applicable Undished - Undished - 487.4 Undished -

Nuclear Design 490.35 487.4 490.35 (6) Reports Dished - Dished -

483.42 483.42 Weight of Fuel Assembly, pounds 681 Undished - Undished - 682 Undished -

681.48 682 681.48 Dished - Dished -

674.55 674.55 Fuel Rods Number per Fuel Assembly 49 or 64* 49 49 49 49 (mixed cores) 1.483 Outside Diameter, inch 0.563 0.563 0.563 0.563 0.563 Clad Thickness, inch 0.032 0.032 0.032 0.032 0.032 Gap - Pellet to Clad, inch 0.006/0.009 0.006 0.006 0.006 0.006 Length of Gas Plenum, inches 16/9.48 16 16 16 16 Clad Material Zircaloy-2 Zircaloy-2 Zircaloy-2 Zircaloy-2 Zircaloy-2 Cladding Process Free standing Free standing Free Standing Free Standing Free Standing loaded tubes loaded tubes loaded tubes loaded tubes loaded tubes

• Two different 8 x 8 fuel bundle arrangements are used. One uses 63 fuel rods and 1 water rod; the other uses 62 fuel rods and 2 water rods.

BFN-17 TABLE 1.7-1 (Sheet 4)

COMPARISON OF NUCLEAR SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

(Parameters are related to Rated Power Output for a single plant unless otherwise noted)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD CORE MECHANICAL DESIGN (Cont'd) UNITS 1/2/3 HATCH UNIT 1 YANKEE STATION ENERGY CENTER Fuel Pellets Material Uranium Dioxide Uranium Dioxide Uranium Dioxide Uranium Dioxide Uranium Dioxide Density, % of theoretical 94% 93% 93% 93% 93%

Diameter, inch 0.410 0.487 0.487 0.487 0.487 Length, inch 0.410 0.75 0.75 0.75 0.75 Fuel Channel Overall Dimension, inches (length) 166.906 166.906 166.906 166.096 166.906 Thickness, inch 0.080 0.080 0.080 0.080 0.080 Cross-Section Dimensions, inches 5.438 x 5.438 5.438 x 5.438 5.438 x 5.438 5.438 x 5.438 5.438 x 5.438 Material Zircaloy-4 Zircaloy-4 Zircaloy-4 Zircaloy-4 Zircaloy-4 Core Assembly Fuel Weight as UO2, pounds 361,837 272,849 179,370 267,095 179,298 Zirconium Weight, pounds 140,397 96,370 63,300 94,305 63,300 (Zr.2 + Zr.4 Spacers)

Core Diameter (equivalent), inches 187.1 160.2 129.9 158.5 129.9 Core Height (Active Fuel), inches 144 - 150 144 144 144 144 Reactor Control System Method of Variation of Reactor Power Movable Control Movable Control Movable Control Movable Control Movable Control Rods and Variable Rods and Variable Rods and Variable Rods and Variable Rods and Variable Coolant Pumping Coolant Pumping Coolant Pumping Coolant Pumping Coolant Pumping Number of Movable Control Rods 185 137 89 137 89 Shape of Movable Control Rods Cruciform Cruciform Cruciform Cruciform Cruciform Pitch of Movable Control Rods 12.0 12.0 12.0 12.0 12.0

BFN-17 TABLE 1.7-1 (Sheet 5)

COMPARISON OF NUCLEAR SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

(Parameters are related to Rated Power Output for a single plant unless otherwise noted)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD CORE MECHANICAL DESIGN (Cont'd) UNITS 1/2/3 HATCH UNIT 1 YANKEE STATION ENERGY CENTER Reactor Control System (Cont'd)

Control Material in Movable Rods B4C granules B4C granules B4C granules B4C granules B4C granules Compacted Compacted Compacted Compacted Compacted in SS Tubes in SS Tubes in SS Tubes in SS Tubes in SS Tubes Type of Control Rod Drives Bottom Entry, Bottom Entry, Bottom Entry, Bottom Entry, Bottom Entry, Locking Piston Locking Piston Locking Piston Locking Piston Locking Piston Supplementary Reactivity Control Grandolinia 156 Burnable Poison Flat, boron-stainless steel control curtains In-Core Neutron Instrumentation Number of In-Core Neutron Detectors (Fixed) 172 124 80 124 80 Number of In-Core Detector Assemblies 43 31 20 31 20 Number of Detectors Per Assembly 4 4 4 4 4 Number of Flux Mapping Neutron Detectors 5 4 3 4 3 Range (and Number) of Detectors Source Range Monitor Source to Source to Source to Source to Source to 0.001% power 0.001% power 0.001% power 0.001% power 0.001% power (4) (4) (4) (4) (4)

Intermediate Range Monitor 0.0001% to 10% 0.0001% to 10% 0.0001% to 10% 0.0001% to 10% 0.0001% to 10%

power (8) power (8) power (8) power (8) power (8)

Local Power Range Monitor 5% to 125% 5% to 125% 5% to 125% 5% to 125% 5% to 125%

power (172) power (124) power (80) power (124) power (80)

Average Power Range Monitor 2.5% to 125% 2.5% to 125% 2.5% to 125% 2.5% to 125% 2.5% to 125%

power (U1-6; U2-4; power (6) power (6) power (6) power (6)

U3-6)

BFN-17 TABLE 1.7-1 (Sheet 6)

COMPARISON OF NUCLEAR SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

(Parameters are related to Rated Power Output for a single plant unless otherwise noted)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD REACTOR VESSEL DESIGN UNITS 1/2/3 HATCH UNIT 1 YANKEE STATION ENERGY CENTER Material Carbon Steel/Clad Stainless Steel (ASME SA-336 & SA-302B)

Design pressure, psia 1265 1265 1265 1265 1265 Design Temperature, °F 575 575 575 575 575 Inside Diameter ft-in. 20 - 11 18 - 2 17 - 2 18 - 2 15 - 3 Inside Height, ft-in. 73 1/2 69 - 4 63 - 1.5 69 - 4 66 - 4 Side Thickness (including clad) 6.313 5.531 5.187 5.531 5.625 Minimum Clad Thickness, inches 1/8 1/8 1/8 1/8 1/8 REACTOR COOLANT RECIRCULATION DESIGN Number of Recirculation Loops 2 2 2 2 2 Design Pressure Inlet Leg. psig 1148 1148 1175 1148 1148 Outlet Leg. psig 1326 1274 1274 1274 1268 CORE MECHANICAL DESIGN Design Temperature, °F 562 562 562 562 562 Pipe Diameter Max. inches 28 28 28 28 22 Pipe Material 304/316 304/316 304/316 304/316 304/316 Recirculation Pump flow Rate, GPM 45,200 45,200 32,500 45,200 27,100 Number of Jet Pumps in Reactor 20 20 20 20 16 MAIN STEAM LINES Number of Steam Lines 4 4 4 4 4 Design Pressure, psig 1146 1146 1146 1146 1146 Design Temperature, °F 563 563 563 563 563 Pipe Diameter, inches 26 24 20 24 20 Pipe Material Carbon Steel (ASTM A155 KC70 or ASTM A106 Grade B)

BFN-17 TABLE 1.7-1 (Sheet 7)

COMPARISON OF NUCLEAR SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

(Parameters are related to Rated Power Output for a single plant unless otherwise noted)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD CORE STANDBY COOLING SYSTEMS UNITS 1/2/3 HATCH UNIT 1 YANKEE STATION ENERGY CENTER (These systems are sized on design power)

Core Spray System Number of Loops 2 2 2 2 2 Flow Rate (gpm) 6250 at 4625 at 3000 at 4500 at 3020 at 105 psid 120 psid 136 psid 115 psid 127 psid High Pressure Coolant Injection system (No.) 1 1 1 1 1 Number of Loops 1 1 1 1 1 Flow Rate (gpm) 5000 4250 4250 4220 2980 Automatic Depressurization system (No.) 1 1 1 1 1 Low Pressure Coolant Injection (No.) 1 1 1 1 1 Number of Pumps 4 4 4 4 4 Flow Rate (gpm/pump) 10,800 gpm 7700 at 4800 at 7000 at 4800 at (1 pump per loop) 20 psid 20 psid 20 psid 20 psid 20,000 gpm (2 pumps per loop)

AUXILIARY SYSTEMS Residual Heat Removal System Reactor Shutdown Cooling (number of pumps) 4 4 4 4 4 Flow Rate (gpm/pump)(2) 10,000 7,700 7,000 7,700 4,800 Capacity (Btu/hr/heat exchanger)(3) 70 x 106 32 x 106 57.5 x 106 70 x 106 35 x 106 Number of heat exchangers 4 2 2 2 2 Primary Containment Cooling Flow rate (gpm)(4) 32,000 30,800 28,000 30,800 19,200

BFN-17 TABLE 1.7-1 (Sheet 8)

COMPARISON OF NUCLEAR SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

(Parameters are related to Rated Power Output for a single plant unless otherwise noted)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD AUXILIARY SYSTEMS (Cont'd) UNITS 1/2/3 HATCH UNIT 1 YANKEE STATION ENERGY CENTER RHR Service Water System Flow Rate (gpm/pump) 4,500 8,000 2,700 8,000 2,500 Number of pumps 12(5) 4 4 4 4 Reactor Core Isolation Cooling System Flow Rate (gpm) 616 at 400 at 400 416 at 416 1120 psid 1120 psid 1120 psid Fuel Pool Cooling and Cleanup system 6 6 6 6 6 Capacity (BTU/hr) 8.8 x 10 3.3 x 10 2.37 x 10 3.4 x 10 2.37 x 10 (1) The operating MCPR limits are subject to change from one cycle to the next and also from one part of the current cycle to the next. The appropriate value for MCPR may be obtained by consulting the applicable current Reload Licensing Amendment.

(2) Capacity during reactor flooding mode with three of four pumps running.

(3) Capacity during post-accident cooling mode with 165°F shell side inlet temperature, maximum service water temperature, and 1 RHR pump and 1 RHR service water pump in operation.

(4) The existing design requires 16,000 gpm (2 pumps, 1 loop) to ensure torus water temperature is maintained within acceptable limits for following all postulated events.

(5) For all three units.

(6) See Appendix N

BFN-17 TABLE 1.7-2 COMPARISON OF POWER CONVERSION SYSTEMS DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

Browns Ferry Duane Arnold TURBINE GENERATOR Each Unit Hatch Unit 1 Vermont Yankee Cooper Station Energy Center Design Power, MWt 3440 2537 1665 2487 1670 Design Power, MWe 1152 849 564 836 597 Generator Speed, rpm 1800 1800 1800 1800 1800 6 6 6 6 6 Design Steam Flow, lb/hr 14.035 x 10 10.48 x 10 6.423 x 10 10.049 x 10 6.696 x 10 Turbine Inlet Pressure, psia 965 970 950 970 950 TURBINE BYPASS SYSTEM Capacity, percent of turbine design steam flow 25 25 100 25 25 MAIN CONDENSER 6 6 6 6 6 Heat removal capacity, Btu/hr 7,770 x 10 5,800 x 10 3,500 x 10 5,367 x 10 3,681 x 10 CIRCULATING WATER SYSTEM Number of Pumps 3 3 3 4 2 or more Flow Rate gpm/pump 220,000 185,000 117,000 162,500 130,000 or less CONDENSATE AND FEEDWATER SYSTEMS 6 6 6 6 6 Design Flow Rate, lb/hr 13.845 x 10 10.096 x 10 6.4 x 10 9.773 x 10 7.146 x 10 Number Condensate Pumps 3 3 2 3 2 Number Condensate Booster Pumps 3 - ---

Number Feedwater Pumps 3 2 2 2 2 Condensate Pump Drive AC power AC power AC power AC power AC power Condensate Booster Pump Drive AC power - - - -

Feedwater Pump Drive Turbine Turbine AC power Turbine AC power

BFN-17 TABLE 1.7-3 COMPARISON OF ELECTRICAL POWER SYSTEM DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD TRANSMISSION SYSTEM NUCLEAR PLANT HATCH UNIT 1 YANKEE STATION ENERGY CENTER Outgoing lines (number-rating) 7-500kV 2-230kV 2-345kV 4-345kV 2-345kV NORMAL AUXILIARY AC POWER Incoming lines (number-rating) 2-161kV 2-230kV 2-345kV 1-115kV 2-345kV 1-230kV 1-69kV 3-161kV 1-115kV 1-4160kV Auxiliary transformers 3 1 1 1 2 Startup transformers 2 2 1 2 1 STANDBY AC POWER SUPPLY Number diesel generators 8 3 2 4 2 Number of 4160V Shutdown buses 8 3 2 2 2 Number of 480V Shutdown buses 6 4-660V 3 3 3 DC POWER SUPPLY Number of 125V or 250V batteries* 6 2 2 2 2 Number of 125V or 250V buses* 6 4 4 4 2

• 3 of the 6 250V systems are qualified

BFN-17 TABLE 1.7-4 Sheet 1 COMPARISON OF CONTAINMENT DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

BROWNS FERRY VERMONT COOPER Duane Arnold PRIMARY CONTAINMENT* EACH UNIT HATCH UNIT 1 YANKEE STATION Energy Center Type Pressure Pressure Pressure Pressure Pressure Suppression Suppression Suppression Suppression Suppression Construction Drywell Light bulb Light bulb Light bulb Light bulb Light bulb shape; steel shape; steel shape; steel shape; steel shape; steel vessel vessel vessel vessel vessel Pressure Suppression Chamber Torus; steel Torus; steel Torus; steel Torus; steel Torus; steel vessel vessel vessel vessel vessel Pressure Suppression Chamber 56 56 56 56 56 Internal Design Pressure (psig)

Pressure Suppression chamber - 2 2 2 2 2 External Design Pressure (psig)

Drywell-Internal Design Pressure (psig) 56 56 56 56 56 Drywell-External Design Pressure (psig) 2 2 2 2 2 Drywell Free Volume (ft3) 159,000 146,400 134,000 145,430 130,930 Pressure Suppression chamber 119,000 101,410 99,000 109,810 94,630 Free Volume (ft3), minimum Pressure Suppression Pool Water 128,700 86,660 78,000 87,660 61,500 Volume (ft3), maximum Submergence of Vent Pipe Below 4 4 4 4 4 Pressure Pool Surface (ft), nominal Design Temperature of Drywell (°F) 281 281 281 281 281 Design Temperature of Pressure 281 281 281 281 281 Suppression Chamber (°F)

• Where applicable, containment parameters are based on design power.

BFN-17 TABLE 1.7-4 (Cont'd)

Sheet 2 COMPARISON OF CONTAINMENT DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD PRIMARY CONTAINMENT* EACH UNIT HATCH UNIT 1 YANKEE STATION ENERGY CENTER Downcomer Vent Pressure Loss Factor 4.1 6.21 6.21 6.21 6.21 Break Area/total Vent Area 0.017 0.019 0.019 0.019 0.019 Calculated Maximum Pressure After Blow- 49.6 45 35 46 45 down Drywell (psig)

Pressure Suppression chamber (psig) 27 28 22 28 29 Initial Pressure Suppression Pool 40 50 35 50 50 Temperature Rise (°F)

Leakage Rate (% Free Volume/Day 0.5 0.5 0.5 0.5 0.5 at 56 psig and 281°F SECONDARY CONTAINMENT Type Controlled Leakage, Controlled Leakage, Controlled Leakage, Controlled Leakage, Controlled Leakage, Elevated Release Elevated Release Elevated Release Elevated Release Elevated Release Construction Reinforced Reinforced Reinforced Reinforced Reinforced Concrete Concrete Concrete Concrete Concrete Upper Levels Steel Super- Steel Super- Steel Super- Steel Super- Steel Super-structure and structure and structure and structure and structure and Siding Siding Siding Siding Siding Roof Steel Decking Steel Steel Steel Steel with Builtup Sheeting Sheeting Sheeting Sheeting Composition Roof Internal Design Pressure (psig) +7 to -5 in. H2O 0.25 0.25 0.25 0.25 Design Inleakage Rate (% Free 100 100 100 100 100 Volume/Day at 0.25 inches H2O)

• Where applicable, containment parameters are based on design power.

BFN-17 TABLE 1.7-4 (Cont'd)

Sheet 3 COMPARISON OF CONTAINMENT DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

BROWNS FERRY VERMONT COOPER Duane Arnold SECONDARY CONTAINMENT* EACH UNIT HATCH UNIT 1 YANKEE STATION Energy Center ELEVATED RELEASE POINT Type Stack Stack Stack Stack Stack Construction Reinforced Steel Steel Steel Steel Concrete Height (above ground) 600 feet 150 meters 318 feet 100 meters 100 meters

• Where applicable, containment parameters are based on design power.

BFN-17 TABLE 1.7-5 COMPARISON OF CONTAINMENT DESIGN CHARACTERISTICS (Data in this table has not been updated to reflect the power uprate at Browns Ferry)

BROWNS FERRY VERMONT COOPER DUANE ARNOLD SEISMIC DESIGN NUCLEAR PLANT HATCH UNIT 1 YANKEE STATION ENERGY CENTER Operating Basis Earthquake (horizontal g) 0.10 0.08 0.07 0.10 0.06 Design Basis Earthquake (horizontal g) 0.20 0.15 0.14 0.20 0.12 WIND DESIGN Maximum sustained (mph) 100 105 80 100 105 Tornadoes (mph) 300 300 300 300 300