ML20093G955
Text
McGuire Nuclear Station UFSAR Appendix 10A. Tables Appendix 10A. Tables
McGuire Nuclear Station UFSAR Table 10-1 (Page 1 of 1)
(27 MAR 2002)
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 1
17,000 GPM Condensate Feedwater Heaters G
3 One-third system requirement F
3 One-third system requirement E
3 One-third system requirement D
3 One-third system requirement C
3 One-third system requirement B
3 One-third system requirement A
3 One-third system requirement Steam Generators 4
One-fourth system requirement 3,810,000 lbm/hr feedwater 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 C Heater Drain Tanks 3
8,800 gallons/tank G Heater Drain Tanks 3
3,000 gallons/tank Auxiliary Feedwater Storage Tank 1
300,000 gallons Auxiliary Feedwater Condensate Storage Tank 2/station 42,500 gallons/tank
McGuire Nuclear Station UFSAR Table 10-2 (Page 1 of 1)
(14 OCT 2000)
Table 10-2. Main Steam Supply System Main Steam Line Safety Valves Number of main steam lines (per Unit) 4 Number of valves per main steam line 5
Total Number of safety valves (per Unit) 20 Design Data For Valves In Each Main Steam Line Valve No.
(psig)
(lb/hr) 1 1170 671,083 2
1190 682,416 3
1205 908,050 4
1220 919,220 5
1225 922,950 Total per line 4,103,719 Total capacity for four lines lb/hr = 16,414,846
McGuire Nuclear Station UFSAR Table 10-3 (Page 1 of 1)
(14 OCT 2000)
Table 10-3. Main Condenser Performance And Data Characteristics Shell A Shell B Shell C Total heat load, Btu/hr 2.5589 x 109 2.5589 x 109 2.5589 x 109 Design absolute pressure in condensing zone in. Hg (with 60°F circulating water temperature at inlet to shells) 1.46 1.46 1.46 Circulating water flow, GPM 319,867 319,867 319,867 Average velocity in tube, ft/sec 7.0 7.0 7.0 Effective surface area, ft2 245,370 245,370 245,370 Cleanliness factor, %
95 95 95 Tube outside diameter, in.
1.0 1.0 1.0 Tube BWG 22 22 22 Tube overall length, ft.
45.01 45.01 45.01 Number of Tubes:
304 Stainless Steel 20,944 20,944 20,944 Condensate stored at normal operating level, gal.
56,667 56,667 56,667
McGuire Nuclear Station UFSAR Table 10-4 (Page 1 of 1)
(06 OCT 2003)
Table 10-4. Failure Mode And Effects Analysis Of The Control Systems And Valves Of The Turbine Bypass System Component Valve Nos.
Malfunction Comment
- 1. Main Steam Power Relief Valves 1SV1, 1SV7, 1SV13, 1SV19 Fail These valves will fail closed and can be isolated for repair by electric motor operated valves.
Deleted per 2003 update.
- 2. Turbine Bypass to Condenser Valves (40% capacity) 1SB3, 1SB6, 1SB9, 1SB12, 1SB15, 1SB18, 1SB21, 1SB24, 1SB27 Fail These valves will fail closed and can be isolated for repair by manually operated valves.
- 3. Turbine Bypass Control System Fail The main steam safety valves are designed to relieve 100% of full load steam flow to assure integrity of the Steam and Power Conversion System in the event of failure of the Turbine Bypass Control System.
- 4. Main Steam Safety Valves (100%
capacity) 1SV2, 1SV3, 1SV4, 1SV5, 1SV6, 1SV8, 1SV9, 1SV10, 1SV11, 1SV12, 1SV14, 1SV15, 1SV16, 1SV17, 1SV18, 1SV20, 1SV21, 1SV22, 1SV23, 1SV24 Fail The failure on one valve would cause loss of steam to the atmosphere, but would not effect safe operation of the Steam and Power Conversion System.
McGuire Nuclear Station UFSAR Table 10-5 (Page 1 of 2)
(14 OCT 2000)
Table 10-5. Condensate And Feedwater System Feedwater Heater Data Characteristics Data Heater Identification A
B C
D E
F G
Quantity per Unit 3
3 3
3 3
3 3
Type Vert. U-Tube Vert. U-Tube Vert. U-Tube Vert. U-Tube Vert. U-Tube Horz. U-Tube Horz. U-Tube Design heat duty. Btu/hr 219.37x106 214.55x106 240.3x106 122.43x106 182.70x106 154.62x106 182.38x106 Overall heat transfer Coefficient. condensing zone/subcooling zone/ Btu/hr.
ft2 °F 817/522 803/578 788/--
747/373 710/472 642/452 566/--
Shell side:
Fluid Steam & Drains Steam & Drains Steam & Flash Vapor Steam & Drains Steam & Drains Steam & Drains Steam & Drains Design Temp. °F 570 480 390 390 310 300 300 Design operating temp.
inlet. steam/drains. °F 448.6/539.4 411.5/450.2 372.1/372.1 358.4/--
280.9/275.2 216.7/222.1 174.8/174.8 Design operating temp.
outlet. steam/drains. °F 414.5/414.5 377.3/377.3 372.1/372.1 275.2/--
222.1/222.1 179.2/179.2 174.8/174.8 Design pressure. psig 500 & full vacuum 325 & full vacuum 200 &full vacuum 75 & full vacuum 50 & full vacuum 50 & full vacuum 50 & full vacuum Design operating flow, steam/drains. lb/hr 239,698/279,044 234,327/697,551 315,032/6,308 126,743/--
178,552/126,743 145,102/328,357 193,722/40,940 Pressure Loss at design flow condensing zone/
subcooling zone. psi Nil/3.8 Nil/4.1 Nil/--
Nil/0.6 Nil/3.2 Nil/1.4 Nil/--
Design fouling factor.
condensing zone/subcooling zone. hr.
ft.2 °F/Btu
.0003
.0003
.0003
.0003
.0003
.0003 Tube side:
Fluid Feedwater Feedwater Condensate Condensate Condensate Condensate Condensate Design temp. °F 470 430 390 320 310 300 300
McGuire Nuclear Station UFSAR Table 10-5 (Page 2 of 2)
(14 OCT 2000)
Characteristics Data Design operating temp.
inlet °F 406.5 368.3 299.0 265.2 214.1 169.2 103.3 Design operating temp.
outlet °F 444.6 406.5 364.1 299.0 265.2 212.7 167.8 Design pressure. psig 1425 1425 700 700 700 269 269 Design operating flow.
lb/hr 5,283,972 5,283,972 3,536,179 3,536,179 3,536,179 3,536,179 2,831,252 Pressure loss at design flow. psi 13.6 13.6 11 11.5 12.0 14.6 15 Design fouling factor, hr ft2 °F/Btu
.000225
.000225
.000215
.00022
.00022
.00022
.00022 Shell diameter, in.
64-3/8 68 46-1/8 50-7/8 52-1/8 58-7/8 52-1/8 Tube outside diameter, in.
5/8 5/8 1
7/8 7/8 3/4 3/4 Tube BWG 20 20 20 20 20 20 20 Materials of Construction:
Shell A-515-70 A-515-70 A-515-70 A-515-70 A-515-70 A-515-70 A-515-70 Tubes A-249-304 A-249-304 A-249-304 A-249-304 A-249-304 A-249-304 A-249-304 Tubesheets A-266-II A-266-II A-516-70 A-516-70 A-516-70 A-516-70 A-516-70
McGuire Nuclear Station UFSAR Table 10-6 (Page 1 of 1)
(14 OCT 2000)
Table 10-6. Hotwell Pump Design Data Quantity per Unit 3
Type Vertical Centrifugal Fluid Condensate Design Pressure, PSIG 269 Design Temperature, °F 95.8 min - 180 max Design Flow Rate, GPM 9820 Design Heat, FT 470 NPSH Required at Design Flow, Ft.
28.5 NPSH Available Ft.
31 Rate RPM 1180 Driver:
Type Motor Rated BHP 1500 Rated RPM 1179 Service Factor 1.25
McGuire Nuclear Station UFSAR Table 10-7 (Page 1 of 1)
(14 OCT 2000)
Table 10-7. Condensate Booster Pump Design Data Quantity per Unit 3
Type Horizontal Centrifugal Fluid Condensate Design Pressure, PSIG 670 Design Temperature, °F 220 Design Flow Rate, GPM 12720 Design Head, Ft.
735 NPSH Required at Design Flow, Ft.
95 NPSH Available at Design Flow, Ft.
330 Rate RPM 3560 Driver:
Type Motor Rated BHP 3000 Rated RPM 3555 Service Factor 1.25
McGuire Nuclear Station UFSAR Table 10-8 (Page 1 of 1)
(14 OCT 2000)
Table 10-8. Steam Generator Feedwater Pump Design Data Quantity per Unit 2
Type Horizontal Centrifugal Fluid Condensate Design Pressure, PSIG 1167 Design Temperature, °F1 366.8 Design Flow Rate, GPM1 17,965 Design Head, Ft.1 2045 NPSH Required at Design Flow, Ft.
160 NPSH Available at Design Flow, Ft. 1 613 Rate RPM1 5210 Turbine Driver:
Type Single flow - Condensing Steam Inlet Pressure, Psia 166 Back Pressure, in. Hg. A 1.7 Rated BHP 12,200 Rated RPM 5510 Note:
- 1. 100 0
0 of all valves wide open
McGuire Nuclear Station UFSAR Table 10-9 (Page 1 of 1)
(22 APR 2017)
Table 10-9. Auxiliary Feedwater System Motor Driven Pump Design Data Quantity per Unit 2
Type Horizontal Centrifugal Fluid Water Design Pressure (rerated), PSIG 1900 Design Temperature (rerated), °F 160 Design Flow Rate, GPM 450 Design Head, Ft.
3200 NPSH Required at Design Flow, Ft.
14 Minimum NPSH Available at Design Flow, Ft.
(CA Storage Tank Supply) 100 Rate RPM 3560 Driver:
Type Motor Rated BHP 500 Rated RPM 3600 Service Factor 1.25
McGuire Nuclear Station UFSAR Table 10-10 (Page 1 of 1)
(22 APR 2017)
Table 10-10. Auxiliary Feedwater System Turbine Driven Pump Design Data Quantity per Unit 1
Type Horizontal Centrifugal Fluid Water Design Pressure (rerated), PSIG 2003 Design Temperature (rerated), °F 160 Design Flow Rate, GPM 900 Design Head, Ft.
3200 NPSH Required at Design Flow, Ft.
16 Minimum NPSH Available at Design Flow, Ft.
(CA Storage Tank supply) 100 Rate RPM 3600 Driver:
Type Single Stage Turbine Steam Inlet Pressure, PSIG Operating Minimum Maximum 957 - 1092 110 1205 Back Pressure, PSIG 0
McGuire Nuclear Station UFSAR Table 10-11 (Page 1 of 1)
(14 OCT 2000)
Table 10-11. Component Failure Analysis for Condensate and Feedwater System Component Malfunction Comment Condensate Hotwell Pump Any failure of pump or valves Isolate to repair and use redundant pump Condensate Cooler Plug or rupture Isolate to repair and use redundant cooler or use bypass Steam Packing Exhauster Condenser Plug or rupture Use Bypass Condensate Booster Pump Any failure of pump or valves Isolate to repair and use redundant pump Main Feedwater Pump Fail Bring plant to safe shutdown conditions if shutdown trip limits are exceeded using Auxiliary Feedwater System One Low or High Pressure Heater Train Fail Use remaining two trains to pass full feedwater flow Two Low or High Pressure Heater Trains Fail Use remaining train and bypass to pass full feedwater flow
McGuire Nuclear Station UFSAR Table 10-12 (Page 1 of 1)
(09 OCT 2015)
Table 10-12. Component Failure Analysis for Auxiliary Feedwater System Component Malfunction Comment Condensate supply Failure of normal condensate supply Water can be supplied from the Nuclear Service Water System by automatic switchover on low suction pressure.
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 panels located near the pumps.
Electrical Power Supply Failure of normal and offsite power All necessary components will automatically switch to operation from power supplied by the emergency diesel generators.
Failure of power supply of 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.
McGuire Nuclear Station UFSAR Table 10-13 (Page 1 of 3)
(09 OCT 2015)
Table 10-13. Auxiliary Feedwater System Instrumentation and Controls Control Room Local Controls Motor stop/start x
x Turbine stop/start x
x Individual auxiliary Feedwater regulators for control valves CA40, CA44, CA56, CA60, CA36, CA48, CA52, and CA64 x
x Individual auxiliary feedwater isolation valves CA42, CA46, CA58, CA62, CA38, CA50, CA54, and CA66 open/close x
x Deleted Per 2002 Update Auxiliary Feedwater Storage Tank Supply Valve CA2 open/close x
x Auxiliary Feedwater Condensate Storage Tanks Supply Valve CA6 open/close x
x Auxiliary feedwater pump suction valves CA7A, CA9B, and CA11B open/close x
x Nuclear service water supply valves RN69A, RN162B, CA15A, CA18B, CA86A, CA116B, open/close x
x Deleted Per 2002 Update Manual block of normal automatic auxiliary feedwater pump start logic x
Alarms Deleted per 2002 Update Individual low auxiliary feedwater pump suction pressure x
Low turbine stop valve steam pressure x1 Remote control of the pumps overridden by local control x
Low level in auxiliary feedwater storage tank x
Auxiliary Feedwater Condensate Storage Tanks Not Full x
Auxiliary feedwater injection line check valve upstream temperature x1 Indicators Steam generator A, B, C and D levels x
x Steam generator A, B, C and D pressure x
x Turbine driven pump suction and discharge pressure x
x Motor driven pump 1A suction and discharge pressure x
x
McGuire Nuclear Station UFSAR Table 10-13 (Page 2 of 3)
(09 OCT 2015)
Control Room Local Motor driven pump 1B suction and discharge pressure x
x Turbine steam inlet pressure x
x Turbine speed x
x Auxiliary feedwater control valves CA40, CA44, CA56, CA60 analog position x
x Indicators Auxiliary feedwater isolation valves CA42, CA46, CA58, CA62, CA50, CA54, and CA66 open/close position x
x TDCA PUMP-TO-SG control valves open/close position (CA64, 52, 48, 36) x x
Upper surge tank supply valves CS18 and CA4 open/close position x
x Auxiliary Feedwater Storage Tank Supply Valve CA2 open/close position x
x Auxiliary feedwater condensate storage tank supply valve CA6 open/close position x
x Auxiliary feedwater pump suction valves CA7A, CA9B, and CA11A open/close position x
x Nuclear service water supply valves RN69A, RN162B, CA15A, CA18B, CA86A, and CA116B open/close position x
x Individual auxiliary feedwater flows to A, B, C and D generators x
x Individual auxiliary feedwater pumps supply flows x
Main feedwater pressure x
Auxiliary Feedwater Storage Tank level x
x Deleted rows per 2002 Update x
Auxiliary Feedwater Condensate Storage Tanks level x
x Nuclear service water pond level x
Flow/No Flow indication in the Auxiliary Feedwater minimum flow lines x
x Motor running lights x
x Auxiliary feedwater check valves CA37, CA41, CA45, CA49, CA53, CA57, CA61, and CA65 upstream temperature x2
McGuire Nuclear Station UFSAR Table 10-13 (Page 3 of 3)
(09 OCT 2015)
Control Room Local Notes:
- 1. computer alarm
- 2. computer indicator
McGuire Nuclear Station UFSAR Table 10-14 (Page 1 of 1)
(05 APR 2011)
Table 10-14. Condensate Polishing Demineralizer Design Data Quantity per Unit 4
Type Powdered Resin/Filter Design Flow, GPM 17000 Design Pressure Drop, PSID 30 Design Pressure, PSIG 285 Design Temperature, °F 180 Effluent Water Quality:
Analysis Average Maximum Total Dissolved Solids 25 PPB 50 PPB Suspended Solids 20 PPB 25 PPB Soluble Silica as SiO2 5 PPB 10 PPB Iron as Fe 5 PPB Copper as Cu 2 PPB Nickel as Ni 2 PPB Chlorides as C1 5 PPB Acid Conductivity 0.2 umhos 0.5 umhos
McGuire Nuclear Station UFSAR Table 10 10-20 (Page 1 of 1)
(14 OCT 2000)
Table 10-15. Deleted Per 1992 Update Table 10-16. Deleted Per 1992 Update Table 10-17. Deleted Per 1992 Update Table 10-18. Deleted Per 1992 Update Table 10-19. Deleted Per 1992 Update Table 10-20. Deleted Per 1992 Update
McGuire Nuclear Station UFSAR Table 10-21 (Page 1 of 1)
(27 MAR 2002)
Table 10-21. Steam Generator Blowdown System Component Design Data Steam Generator Blowdown Blowoff Tank Quantity (per unit) 1 Design Temperature, °F 338 Design Pressure, PSIG 100 Design Capacity, LBM/HR @ 338°F 180,000 Material Carbon Steel Code ASME VIII Steam Generator Blowdown Blowoff Tank Pumps Quantity (per unit) 2 Design Flow, GPM 280 Design TDH, Feet of H2O 600 Design Temperature, °F 338
McGuire Nuclear Station UFSAR Table 10-22 and 10-23 (Page 1 of 1)
(14 OCT 2000)
Table 10-22. Deleted Per 1992 Update Table 10-23. Deleted Per 1999 Update
McGuire Nuclear Station UFSAR Table 10-24 (Page 1 of 1)
(14 OCT 2000)
Table 10-24. C Heater Drain Tank Pump Design Data Quantity per Unit 3
Type Centrifugal - Vertical Fluid Condensate Design Pressure, PSIG 785 Design Temperature, °F 390 Design Flow Rate, GPM 4380 Design Head, Ft.
850 NPSH Required at Design Flow, Ft.
16 Minimum NPSH Available at Design Flow, Ft.
19 Rate RPM 1780 Driver:
Type Motor Rated bhp 1250 Rated rpm 1780 Service Factor 1.25
McGuire Nuclear Station UFSAR Table 10-25 (Page 1 of 1)
(14 OCT 2000)
Table 10-25. G Heater Drain Tank Pump Design Data Quantity per Unit 3
Type Centrifugal - Horizontal Fluid Condensate Design Pressure, PSIG 269 Design Temperature, °F 300 Design Flow Rate, GPM 1600 Design Head, Ft.
390 NPSH Required at Design Flow, Ft.
18 Minimum NPSH Available at Design Flow, Ft.
20 Rate RPM 3600 Driver:
Type Motor Rated bhp 250 Rated rpm 3600