ML20106E928
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Catawba Nuclear Station UFSAR Appendix 10A. Tables Appendix 10A. Tables
Catawba Nuclear Station UFSAR Table 10-1 (Page 1 of 1)
(22 OCT 2001)
Table 10-1. Design and Performance Characteristics of the Major Equipment and Tanks Name Number Capacity/Design Condenser 3
One-third capacity shells Condenser Hotwell 1
170,000 gallons Hotwell Pumps 3
One-half system requirement Condensate Booster Pumps 3
One-half system requirement Feedwater Pumps 2
One-half system requirement Condensate Polishing Demineralizer 5
One-fourth system requirement Condensate Feedwater Heaters G
3 One-third system requirement F
3 One-third system requirement E
2 One-half system requirement D
2 One-half system requirement C
2 One-half system requirement B
2 One-half system requirement A
2 One-half system requirement Steam Generators 4
One-fourth system requirement 3,963,000 lb/hr design flow Turbine-Generator 1
Tandem compound - six flow turbine with a 1,450,000 KVA generator and moisture separator reheater units Upper Surge Tanks 2
85,000 gallons total Condensate Storage Tank 1
30,000 gallons
Catawba Nuclear Station UFSAR Table 10-2 (Page 1 of 1)
(22 OCT 2001)
Table 10-2. Turbine Speed Control System Protection Devices Component Function Design Operating Speed in % of Rated Speed Primary speed control processor control 0 - 110%
Backup speed control processor control 0 - 110%
Mechanical overspeed trip trip 110%
Backup "electrical" overspeed trip trip 111.5% (Primary Processor) 111.5% (Backup Processor)
Catawba Nuclear Station UFSAR Table 10-3 (Page 1 of 1)
(22 OCT 2001)
Table 10-3. Turbine Speed Control System Valve Closure Time Valve Closure Time (Seconds)
Main stop 0.12 Main control 0.19 Intermediate stop 0.20 Intercept 0.17 Extraction check 2 (maximum)
Catawba Nuclear Station UFSAR Table 10-4 (Page 1 of 1)
(22 OCT 2001)
Table 10-4. Turbine Speed Control System Component Failure Analysis Component Malfunction Overspeed Prevented By Main control valve Fail to close Closure of stop valves Main stop valve Fail to close Closure of control valves Intercept valve Fail to close Closure of intermediate stop valve Intermediate stop valve Fail to close Closure of intercept valve Primary speed control processor Fails Backup speed control processor Mechanical overspeed trip Fails Backup "electrical" overspeed trip 24 volt "electrical" trip solenoid valve (dual solenoids)
Fails 125 volt "mechanical" trip solenoid valve A mechanical trip Fails An electrical trip Fast acting solenoid valves Fail Emergency Trip Fluid System
Catawba Nuclear Station UFSAR Table 10-5 (Page 1 of 1)
(22 OCT 2001)
Table 10-5. Branch Steam Paths Active After Postulated Accident of Break in Safety Grade Portion of Main Steam Line and a Single Non-closable Main Steam Isolation Valve Branch Line System Equipment Supplied Or Use Of Steam Maximum Flow Type Isolation Valve1 Size Closure Time Actuation2 Main Steam to Auxiliary Steam Header Auxiliary Steam Auxiliary Steam 291,000 lb/hr Gate 12 in 60 sec E
Main Steam to Steam Seal Header Main And FWP Turbine Steam Seal Sealing Steam 36,000 lb/hr Gate 4 in 30 sec E
Turbine Bypass Header Main Steam Bypass To Condenser Low Point Drain Trap And Orifices 6,430 lb/hr Gate 24 in M
Two Main Steam Equalization Header Low Point Drains Main Steam Drain Traps 680 lb/hr Gate3 1 in M
Four Main Steam Line Low Point Drains Main Steam Drain Orifices 280 lb/hr Gate3 1 in M
FWP Turbine Supply Header Steam Supply To FWP Turbine Drain Orifice And Traps 155 lb/hr Gate 6 in M
Notes:
- 1. All valves are Duke Class G.
- 2. E - Electric motor operator with manual controls in control room. M - Manual handwheel.
- 3. One valve per drain.
Catawba Nuclear Station UFSAR Table 10-6 (Page 1 of 2)
(22 OCT 2001)
Table 10-6. Main Condenser Design Parameters Manufacturer Foster Wheeler Type 3 shell - 3 pressure - Double Flow Duty 7.9 x 109 BTU/HR Heat Transfer Surface 969,213 Sq. Ft. (3 shells)
Hotwell Capacity 7,670 Cu. Ft. (per shell)
Circulating Water Design Inlet Temp.
89°F Circulating Water Flow 658,334 GPM Circulating Water Temp. Rise 24°F (8°F/shell)
Total Pressure Drop 34 Ft. (includes crossovers)
Backpressure - HP 3.73 In. Hg.
IP 2.94 In. Hg.
LP 2.40 In. Hg.
Tube Gauge 22 BWG Tube Material 304 SS Tube Diameter 1.25 In.
Effective Tube Length 42 Ft.
Tube Velocity 8.0 FPS Number of Tubes 23, 506 (per shell)
Cleanliness Factor 0.95 Shell Material A-285 Grade C CS Support Plate Material A-285 Grade C CS Tube Sheet Material A-516 Grade 70 CS Waterbox Material SA-516 Grade 70 CS Overall Length 104' - 5" Overall Width 64' - 8 3/4" Overall Height 59' - 5" Free Oxygen In Condensate 0.005cc/liter Normal Steam Flow 10,082,000 lb/hr Maximum Steam Flow 10,519,000 lb/hr Normal CCW Inlet Temperature 79°F Maximum CCW Inlet Temperature 91°F Normal Turbine Exhaust Steam Temperature Without Bypass Flow 112.2°F
Catawba Nuclear Station UFSAR Table 10-6 (Page 2 of 2)
(22 OCT 2001)
Maximum Turbine Exhaust Steam Temperature Without Bypass Flow 123.1°F Normal Turbine Exhaust Steam Temperature With Bypass Flow 133.6°F Maximum Turbine Exhaust Steam Temperature With Bypass Flow 144.1°F
Catawba Nuclear Station UFSAR Table 10-7 (Page 1 of 1)
(22 OCT 2001)
Table 10-7. Main Condenser Evacuation System Component Design Parameters CONDENSER STEAM AIR EJECTORS Manufacturer Foster Wheeler Type Steam Jet Number 3 per unit Design flow rate 20 SCFM air 90 LB/HR Associated water vapor 198 LB/HR Total air vapor mixture 288 LB/HR Design pressure 1.0 IN. HB. ABS.
Design temperature 71.5°F MAIN VACUUM PUMPS Manufacturer Nash Model CL-3002 Type Liquid Ring Number 2 per station Design flow rate 3050 ACFM Design pressure 20.0 IN. HG. VAC.
Design temperature 80°F Speed 530 RPM Design brake horsepower 180 HP
Catawba Nuclear Station UFSAR Table 10-8 (Page 1 of 1)
(22 OCT 2001)
Table 10-8. Turbine Bypass System Failure Mode And Effects Analysis Malfunction Effect Partial or complete loss of steam dump capability Overpressure protection provided by main steam safety/relief valves.
Reactor and subsequent turbine trip may occur on load reduction.
Stuck open dump valve Flow less than 970,000 lbm/hr through valve.
Turbine and reactor operation not affected.
Large break in bypass system piping Main steam isolation with subsequent reactor and turbine trip.
Catawba Nuclear Station UFSAR Table 10-9 (Page 1 of 1)
(27 MAR 2003)
Table 10-9. Condenser Circulating Water System Component Design Parameters CONDENSER CIRCULATING WATER PUMPS Manufacturer Allis-Chalmers Quantity 4 per unit Type Francis Wheel Model 84 x 72 SSCV Number of Stages 1
Design Flow 172,500 GPM Design Head 110 Ft.
Speed 293 RPM Design Brake Horsepower 5320 HP COOLING TOWERS Manufacturer Marley Quantity 3 per unit Type Round Mechanical Draft Model 700 Design Flow per Unit 630,000 GPM1 Design Wet Bulb Temperature 76°F Design Approach 12.6°F Design Range 22.9°F Note:
- 1. Measured flow per tower is 210,000 GPM with three CCW pumps operating and 245,000 GPM per tower with four CCW pumps operating.
Catawba Nuclear Station UFSAR Table 10-10 (Page 1 of 2)
(22 OCT 2001)
Table 10-10. Condensate Cleanup System Component Design Parameters CONDENSATE POLISHING DEMINERALIZERS Manufacturer DeLaval Quantity 5 per unit Type powdered resin Design flow 5450 GPM Design pressure 380 PSIG Design temperature 180°F Maximum pressure drop 41 PSI CONDENSATE POLISHING DEMINERALIZER BACKWASH TANK Quantity one per unit Design capacity 20,000 Gal Design temperature 180°F Design external pressure 0 PSIG Design internal pressure 0 PSIG CONDENSATE POLISHING DEMINERALIZER BACKWASH TANK PUMP Manufacturer Ingersoll-Rand Quantity two per unit Type Vertical In-line Model 4 x 3 x 8 VOC Number of stages 1
Design flow 400 GPM Design head 180 FT Speed 3550 RPM Design Brake horsepower 26.7 HP CONDENSATE POLISHING DEMINERALIZER HOLDING PUMPS Manufacturer Goulds Quantity 5 per unit Type centrifugal Model 3196 Number of stages 1
Design flow 750 GPM Design head 35 FT
Catawba Nuclear Station UFSAR Table 10-10 (Page 2 of 2)
(22 OCT 2001)
Speed 1200 RPM Design brake horsepower 10 HP CONDENSATE POLISHING DEMINERALIZER PRECOAT PUMP Manufacturer Goulds Quantity one per unit Type centrifugal Model 3196 Number of stages 1
Design flow 2250 GPM Design head 40 FT Speed 1200 RPM Design brake horsepower 30 HP CONDENSATE POLISHING DEMINERALIZER RESIN FEED TANK Quantity One per unit Design capacity 900 Gal Design external pressure 0 PSIG Design internal pressure 0 PSIG CONDENSATE POLISHING DEMINERALIZER RECIRCULATION TANK Quantity one per unit Design capacity 2250 Gal Design external pressure 0 PSIG Design internal pressure 0 PSIG
Catawba Nuclear Station UFSAR Table 10-11 (Page 1 of 4)
(22 OCT 2001)
Table 10-11. Condensate and Feedwater System Component Design Parameters HOTWELL PUMP STRAINERS Manufacturer Zurn Quantity 3 per unit Type Simplex Model 36" 514 VBB Design flow 12,720 GPM Design pressure 0 PSIA and 50 PSIA Design temperature 200°F Strainer medium 60 x 60 mesh Maximum pressure drop 0.2 PSI HOTWELL PUMPS Manufacturer Ingersoll-Rand Quantity 3 per unit Type Vertical Can Model 36 - APKD - 4 Number of stages 4
Design flow 12,720 GPM Design head 585 FT Speed 1180 RPM Design brake horsepower 2265 HP Minimum continuous flow 2400 GPM G FEEDWATER HEATERS Manufacturer SWECO Quantity 3 per unit Type Horizontal - Straight Tube Feedwater terminal temperature difference 3°F Drain cooler approach temperature 8°F Tube side design pressure 380 PSIG Tube side design temperature 300°F Shell side design pressure 50 PSIG & Full Vacuum Shell side design temperature 300°F F FEEDWATER HEATERS
Catawba Nuclear Station UFSAR Table 10-11 (Page 2 of 4)
(22 OCT 2001)
Manufacturer SWECO Quantity 3 per unit Type Horizontal - Straight Tube Feedwater terminal temperature difference 2°F Drain cooler approach temperature 8°F Tube side design pressure 380 PSIG Tube side design temperature 300°F Shell side design pressure 50 PSIG & Full Vacuum Shell side design temperature 300°F CONDENSATE BOOSTER PUMPS Manufacturer Bingham Quantity 3 per unit Type Horizontal Centrifugal Model 14 x 14 x 16 1/2 HSB Number of stages 1
Design flow 12,720 GPM Design head 750 Ft.
Speed 3600 RPM Design brake horsepower 2689 H.P.
Minimum continuous flow 1600 GPM E FEEDWATER HEATERS Manufacturer SWECO Quantity 2 per unit Type Horizontal - U Tube Feedwater terminal temperature difference 3°F Drain cooler approach temperature 8°F Tube side design pressure 865 PSIG Tube side design temperature 310°F Shell side design pressure 65 PSIG & Full Vacuum Shell side design temperature 310°F D FEEDWATER HEATERS Manufacturer SWECO Quantity 2 per unit
Catawba Nuclear Station UFSAR Table 10-11 (Page 3 of 4)
(22 OCT 2001)
Type Horizontal - U Tube Feedwater terminal temperature difference 4°F Drain cooler approach temperature 8°F Tube side design pressure 865 PSIG Tube side design temperature 350°F Shell side design pressure 110 PSIG & Full Vacuum Shell side design temperature 450°F C FEEDWATER HEATERS Manufacturer SWECO Quantity 2 per unit Type Horizontal - U Tube Feedwater terminal temperature difference 5°F Drain cooler approach temperature NA Tube side design pressure 856 PSIG Tube side design temperature 390°F Shell side design pressure 200 PSIG & Full Vacuum Shell side design temperature 390°F STEAM GENERATOR FEEDWATER PUMPS Manufacturer Bingham Quantity 2 per unit Type Centrifugal Model 16 x 18 x 17 CD Number of stages 1
Design flow 18,040 GPM Design head 2,040 FT Design speed 5200 RPM Design brake horsepower 9250 HP Minimum continuous flow 4000 GPM B FEEDWATER HEATERS Manufacturer SWECO Quantity 2 per unit Type Horizontal - U Tube Feedwater terminal temperature difference 5°F
Catawba Nuclear Station UFSAR Table 10-11 (Page 4 of 4)
(22 OCT 2001)
Drain cooler approach temperature 8°F Tube side design pressure 1385 PSIG Tube side design temperature 500°F Shell side design pressure 325 PSIG & Full Vacuum Shell side design temperature 480°F A FEEDWATER HEATERS Manufacturer SWECO Quantity 2 per unit Type Horizontal - U Tube Feedwater terminal temperature difference 3°F Drain cooler approach temperature 8°F Tube side design pressure 1385 PSIG Tube side design temperature 500°F Shell side design pressure 500 PSIG & Full Vacuum Shell side design temperature 570°F
Catawba Nuclear Station UFSAR Table 10-12 (Page 1 of 1)
(18 APR 2009)
Table 10-12. Deleted Per 2009 Update
Catawba Nuclear Station UFSAR Table 10-13 (Page 1 of 3)
(22 OCT 2001)
Table 10-13. Steam Generator Blowdown System Component Design Parameters STEAM GENERATOR BLOWDOWN PUMPS Number Per Unit 2
Type Vertical Inline Design Pressure, PSIG 635 Design Temperature, °F 400 Head at Design Flow, Ft 500 Temperature of Pumped Fluid, °F 110-365 Capacity at Design Head, GPM 360 STEAM GENERATOR BLOWDOWN TANK Number per Unit 1
Volume, Gallons (approx.)
3000 Normal Operating Pressure, PSIA 1.3-160 Design Pressure, PSIG 205 Design Temperature, °F 390 Construction Material Carbon Steel STEAM GENERATOR BLOWDOWN RECOVERY HEAT EXCHANGERS Number per Unit 2
Manufacturer Joseph Oat Corp.
Type CGU Tube Side:
Design Pressure, PSIG 485 Design Temperature, °F 430 Design Flow, lbm/hr 203,000 Inlet Temperature, °F 365 Outlet Temperature, °F 130 Fouling Factor
.001 Pressure Drop at Design Flow, PSI 8.1 Material Stainless steel Shell Side:
Design Pressure, PSIG 380
Catawba Nuclear Station UFSAR Table 10-13 (Page 2 of 3)
(22 OCT 2001)
Design Temperature, °F 180 Design Flow, lbm/hr 1,985,000 Inlet Temperature, °F 110 Outlet temperature, °F 134.4 Fouling Factor 0005 Pressure drop at design flow, PSI 8.8 Material Carbon steel STEAM GENERATOR BLOWDOWN DEMINERALIZER PREFILTER Number per Unit 2
Manufacturer Pall Trinity Type Cartridge Design Pressure, PSIG 485 Design Temperature, °F 430 Design Flow, GPM 500 Retention Size, Microns 2-10 Clean Pressure Drop at Design Flow, PSI 2
Cartridge Structural Design Max.
Pressure Drop, PSI 75 Material of Construction Carbon Steel STEAM GENERATOR DEMINERALIZER Number per Unit 2
Manufacturer Graver Type Mixed-bed, non-regenerative Design Pressure, PSIG 485 Design Temperature, °F 430 Operating Temperature, °F 130 Design Flow, GPM 500 Clean Pressure Drop at Design Flow, PSI 5
Flow Loading at Design Flow, GPM/ft2 17.7
Catawba Nuclear Station UFSAR Table 10-13 (Page 3 of 3)
(22 OCT 2001)
Total Resin Volume, Ft3 85 Anion to Cation Ratio
~ 1:1 Resin Bed Depth, in.
36 Material of Construction Stainless Steel STEAM GENERATOR BLOWDOWN DEMINERALIZER RESIN TRAP Number per Unit 2
Manufacturer Mueller Type Y-strainer Design Pressure, PSIG 485 Design Temperature, °F 430 Design Flow, GPM 500 Clean Pressure Drop at Design Flow, PSI 1
Retention Size, Mesh 100 Material of Construction Carbon Steel
Catawba Nuclear Station UFSAR Table 10-14 (Page 1 of 2)
(22 OCT 2001)
Table 10-14. Failure Analysis, Steam Generator Blowdown System Failure Consequences Action (1)
Rupture of blowdown line between steam generator and isolation valve inside containment.
Hot water under pressure partially flashes to steam. Pressure in lower compartment increases, and vapor passes through ice beds.
Water level in affected steam generator increases. Radioactivity present in steam generator remains inside containment.
Same action taken for small steam break.
(2)
Rupture of blowdown line from outside containment to flash tank.
Hot water under pressure escaped into Doghouse or Turbine Building and partially flashes to steam. Some of the radioactive material in blowdown is carried out with building ventilation exhaust.
When the leak is discovered, the operator closes blowdown isolation valves.
(3)
Rupture of blowdown line down stream of flash tank.
Water or steam under pressure escapes into Turbine Building and water is collected by floor drains.
When the leak is discovered, the operator closes all blowdown isolation valves.
Catawba Nuclear Station UFSAR Table 10-14 (Page 2 of 2)
(22 OCT 2001)
Failure Consequences Action (4)
Loss of instrument air The following valves will fail as listed below:
BB65 Fail Close BB69 Fail Close BB24 Fail Close BB73 Fail Close BB39 Fail Open BB86 Fail Open BB27 Fail Close BB48 Fail Close BB175 Fail Open BB178 Fail Open BB188 Fail Close BB250 Fail Open No activity will be released to the atmosphere if a primary to secondary leak is present.
No action is required from the operator.
Blowdown will be reestablished once instrument air is obtained.
(5)
One blowdown pump is inoperable.
Second blowdown pump can be used.
Second blowdown pump is aligned for operation.
Catawba Nuclear Station UFSAR Table 10-15 (Page 1 of 1)
(22 OCT 2001)
Table 10-15. Auxiliary Feedwater System Motor Driven Pump Design Data Quantity per Unit 2
Type Centrifugal, Horizontal Fluid Water Design temperature, °F 160 Design flow rate, GPM 500 Design head, ft. H2O 3210 NPSH required, at design flow, ft.
15 Rated RPM 3600 Driver:
Type Direct coupled, electric motor Rated BHP 600 Rated RPM 3600 Service Factor 1.25 Power Requirements 4000 VAC, 3 Phase, 60 Hz
Catawba Nuclear Station UFSAR Table 10-16 (Page 1 of 1)
(22 OCT 2001)
Table 10-16. Auxiliary Feedwater System Turbine Driven Pump Design Data Quantity per Unit 1
Type Centrifugal, Horizontal Fluid Water Design temperature, °F 160 Design flow rate, GPM 1000 Design head, ft. H2O 3217 NPSH required, at design flow, ft.
15 Rated Set RPM Up to 3800 Driver:
Type Direct coupled, Single stage turbine Rated BHP 1160 Rated Set RPM Up to 3800 Steam inlet pressure, max/min, psig 1210 - 110 Back pressure, psig 3
The auxiliary feedwater pump turbine is qualified to Seismic Category I.
Catawba Nuclear Station UFSAR Table 10-17 (Page 1 of 1)
(22 OCT 2001)
Table 10-17. Auxiliary Feedwater System Component Failure Analysis Component Malfunction Comment Condensate supplies Failure of all normal con-densate supplies Water can be supplied automatically from the Nuclear Service Water System or the Condenser Circulating Water System Motor Driven Auxiliary Feedwater Pump Either pump failure Use the turbine driven auxiliary feedwater pump or the redundant motor driven auxiliary feedwater pump Turbine Driven Auxiliary Feedwater Pump Fail Use motor driven auxiliary feedwater pumps Control Room No access to control room The system can be monitored and controlled from the auxiliary shutdown control panels.
Electrical Power Failure of normal auxiliary and offsite A.C. power All necessary components will automatically switch to operation from power supplied by the emergency diesel generators Failure of power supply to components associated with one of the motor driven pumps Components associated with the redundant motor driven pump are supplied power from physically separated switchgear and cabling Failure of all normal and emergency A.C. power The turbine driven auxiliary feedwater pump will operate with all necessary electrical components operating from a battery-backed D.C. power source
Catawba Nuclear Station UFSAR Table 10-18 (Page 1 of 3)
(22 OCT 2001)
Table 10-18. Auxiliary Feedwater System Instrumentation and Control Indicators Control Room Local Steam generator A,B,C,D levels (wide range)
X X
Steam generator A,B,C,D pressures (wide range)
X X
Turbine driven pump suction and discharge pressures X
X Motor driven pump A suction and discharge pressures X
X Motor driven pump B suction and discharge pressures X
X Turbine steam inlet pressure X
X Turbine speed X
X Auxiliary feedwater isolation motor operated valves CA38A, CA42B, CA46B, CA50A, CA54B, CA58A, CA62A, CA66B open/close position X
X Auxiliary feedwater turbine stop valve and main steam supply valves open/close position X
X Upper surge tank supply valve CA4 open/close position X
X Condenser hotwell supply valve CA2 open/close position X
X Auxiliary feedwater condensate storage tank supply valve CA6 open/close position X
X Main feedwater bypass to AFW nozzle isolation valves open/close position X
Condensate sources low level indicating lights X
X Local/remote control indicating lights X
Loss of condensate source indicating lights X
Auxiliary feedwater pump loss of condensate source indicating lights X
Auxiliary feedwater pump suction valves CA7A, CA9B, CA11A, CA15A, CA18B, CA85B, CA116A open/close position X
X Nuclear service water supply valves RN250A, RN310B open/close position X
X Auxiliary feedwater flows to A,B,C,D steam generators X
X Individual auxiliary feedwater pump discharge flows X
Main feedwater pressure X
Upper surge tank level X
X Auxiliary feedwater condensate storage tank level X
X Hotwell level X
X Condensate storage tank level X
Nuclear service water pond level X
Auxiliary feedwater pumps running lights X
X
Catawba Nuclear Station UFSAR Table 10-18 (Page 2 of 3)
(22 OCT 2001)
Indicators Control Room Local Auxiliary feedwater pumps automatic start defeat indicating lights X
Auxiliary feedwater pumps recirculation flow indicating lights X
Check valves CA37, CA41, CA45, CA49, CA53, CA57, CA61, CA65 upstream temperature X
Auxiliary feedwater nozzle piping temperature X
Motor driven pump A stop/start X
X Motor driven pump B stop/start X
X Turbine driven pump stop/start X
X Individual valve position controls for pump discharge flow control valves CA36, CA40, CA44, CA48, CA52, CA56, CA60, CA64 X
X Individual auxiliary feedwater motor operated isolation valves CA38A, CA42B, CA46B, CA50A, CA54B, CA58A, CA62A, CA66B open/close X
X Local/remote control transfer switch X
Auxiliary feedwater condensate storage tank supply valve CA6 open/close/auto X
X Upper surge tank supply valve CA4 open/close X
X Condenser hotwell supply valve CA2 open/close X
X Auxiliary feedwater pump suction valves CA7A, CA9B, CA11A open/close X
X Nuclear service water supply valves RN250A, RN310B, open/close/auto X
X Turbine trip and reset control X
X Auxiliary feedwater turbine main steam supply valves open/close X
X Main feedwater bypass to auxiliary feedwater nozzle isolation valves open/close X
Auxiliary feedwater pump suction valves CA15A, CA18B, CA85B, CA116A open/close/auto X
X Auto start defeat switch (motor driven pumps only)
X Auxiliary Feedwater Pump trip on low suction pressure defeat switch X
Specific control room alarms for the Auxiliary Feedwater System:
Low hotwell level Low upper surge tank level Low-low auxiliary feedwater condensate storage tank level Aux. Feedwater System Loss of Condensate source Turbine stop valves not open
Catawba Nuclear Station UFSAR Table 10-18 (Page 3 of 3)
(22 OCT 2001)
Indicators Control Room Local Control room control overridden by local panel control Any auxiliary feedwater pump discharge motor operated isolation valve not open Any nuclear service water supply valve not closed (RN250A, RN310B, CA15A, CA18B, CA85B, CA116A)
High temperature alarms for pump and driver bearings and motors Any auxiliary feedwater pump suction valve CA7A, CA9B, CA11A not open Low auxiliary feedwater condensate storage tank level Low auxiliary feedwater condensate storage tank level coincident with low upper surge tank level Less than recommended inventory in upper surge tanks Loss of condensate source Low temperature differential between CA nozzle piping and corresponding Loop main steam temperature High temperature upstream of check valves CA37, CA41, CA45, CA49, CA53, CA57, CA61, CA65 indicating backleakage
Catawba Nuclear Station UFSAR Table 10-19 (Page 1 of 1)
(22 OCT 2001)
Table 10-19. Moisture Separator/Reheater and Feedwater Heater Drains System C Feedwater Heater Drain Tank Pump Design Data Quantity per unit 2
Type Centrifugal, Vertical Fluid Condensate Hydrotest pressure, discharge, psig 1500 Design temperature, °F 370 Design flow rate, GPM @ 370°F 6220 Design head, ft. H2O @ 370°F 1150 NPSH required, at design flow, ft. H2O @ 370°F 18 Minimum NPSH available, at design flow, ft. H2O @ 370°F 25 Rated RPM 1800 Driver:
Type Direct coupled, electric motor Rated BHP 2250 Rated RPM 1800 Service Factor 1.25 Power Requirements 6600 VAC, 3 Phase, 60 Hz