ML22340A161
Text
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
1 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
12-HV-ACCP-1 CCW Pump Ventilation North Supply Fan Auxiliary Building Ventilation Auxiliary 633 633 Hallway 633 12-HV-ACCP-2 CCW Pump Ventilation Middle Supply Fan Auxiliary Building Ventilation Auxiliary 633 633 Hallway 633 12-HV-ACCP-3 CCW Pump Ventilation South Supply Fan Auxiliary Building Ventilation Auxiliary 633 633 Hallway 633 12-HV-ESW-1 Unit 2 East Essential Service Water Pump Room Supply Ventilation Fan ESW Ventilation Screenhouse 591 East ESW Pump Room 135 12-HV-ESW-2 Unit 2 East Essential Service Water Pump Room Supply Ventilation Fan ESW Ventilation Screenhouse 591 East ESW Pump Room 135 12-HV-ESW-3 Unit 2 West Essential Service Water Pump Room Supply Ventilation Fan ESW Ventilation Screenhouse 591 West ESW Pump Room 136 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
2 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
12-HV-ESW-4 Unit 2 West Essential Service Water Pump Room Supply Ventilation Fan ESW Ventilation Screenhouse 591 West ESW Pump Room 136 12-TK-47-AB Diesel Fuel Oil Storage Yard Tanks AB Diesel Fuel Oil Grounds 609 Inner Plant Grounds 244 12-TK-47-CD Diesel Fuel Oil Storage Yard Tanks CD Diesel Fuel Oil Grounds 609 Inner Plant Grounds 244 2-20-SV-1-AB Solenoid Valve to POV-1-AB Compressed Air Auxiliary 587 AB EDG Room 121 2-20-SV-1-CD Solenoid Valve to POV-1-CD Compressed Air Auxiliary 587 CD EDG Room 122 2-20-SV-2-AB Solenoid Valve to POV-2-AB Compressed Air Auxiliary 587 AB EDG Room 121 2-20-SV-2-CD Solenoid Valve to POV-2-CD Compressed Air Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
3 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-20-SV-3-AB Solenoid Valve to XRV-220 Compressed Air Auxiliary 587 AB EDG Room 121 2-20-SV-3-CD Solenoid Valve to XRV-225 Compressed Air Auxiliary 587 CD EDG Room 122 2-21A 600Vac Bus 21A 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21A11 600Vac Bus 21A Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21A2 600Vac MCC AM-A Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21A5 600Vac MCC ABD-A Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
4 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-21A6 600Vac MCCs AB-A, PS-A, TPP-A, and VCCS ABV-A, AZV-A Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21A9 600Vac MCC EZC-A Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21B 600Vac Bus 21B Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21B1 600Vac MCC ABD-B Supply Breaker (2-ELSC) 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21B11 600Vac Bus 21B Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
5 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-21B2 600Vac MCC EZC-B Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21C 600Vac Bus 21C 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21C1 600v Bus 21C Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21C10 600Vac MCC ABD-C and 2-AFW Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21C6 600Vac MCC EZC-C Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
6 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-21D 600Vac Bus 21D 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21D1 600v Bus 21D Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21D14 600Vac MCC 2-AB-D, VCC 2-ABV-D, MCC 2-PS-D Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21D5 600Vac MCC ABD-D Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-21D6 600Vac MCC EZC-D Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
7 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-21D8 600Vac MCC AM-D Supply Breaker 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-52-BYA Reactor Rod Control TR-A Reactor Trip Bypass Circuit Breaker Reactor Trip Breaker (Rod Control & Inst.)
Auxiliary 609 Control Rod Drive Equipment Room 203 2-52-BYB Reactor Rod Control Train B Reactor Trip Bypass Circuit Breaker Reactor Trip Breaker (Rod Control & Inst.)
Auxiliary 609 Control Rod Drive Equipment Room 203 2-52-RTA Reactor Rod Control Train 'A' Reactor Trip Circuit Breaker Rod Control and Instrumentation Auxiliary 609 Control Rod Drive Equipment Room 203 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
8 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-52-RTB Reactor Rod Control Train 'B' Reactor Trip Circuit Breaker Rod Control and Instrumentation Auxiliary 609 Control Rod Drive Equipment Room 203 2-AB-A 600Vac Motor Control Center AB-A 600Vac Auxiliary 587 587 Hallway 587 2-AB-D 600Vac Motor Control Center AB-D 600Vac Auxiliary 587 587 Hallway 587 2-ABD-A 600Vac Motor Control Center ABD-A 600Vac Auxiliary 587 AB EDG Room 121 2-ABD-B 600Vac Motor Control Center ABD-B 600Vac Auxiliary 587 AB EDG Room 121 2-ABD-C 600Vac Motor Control Center ABD-C 600Vac Auxiliary 587 CD EDG Room 122 2-ABD-D 600Vac Motor Control Center ABD-D 600Vac Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page:
9 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-AB-N Control Center Valve 250Vdc Control and Instrumentation Auxiliary 587 587 Hallway 587 2-ABV-A 600Vac Valve Control Center ABV-A 600Vac Auxiliary 587 587 Hallway 587 2-ABV-D 600Vac Valve Control Center ABV-D 600Vac Auxiliary 587 587 Hallway 587 2-AFW 120/208 Vac AFW Distribution Panel 120/208Vac Misc Safety Related Power Distribution Auxiliary 587 CD EDG Room 122 2-AFWX 120/208 Vac AFW Auxiliary Distribution Panel 120/208Vac Misc Safety Related Power Distribution Auxiliary 587 CD EDG Room 122 2-AM-A 600Vac Motor Control Center AM-A 600Vac Auxiliary 633 633 Hallway 633 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 10 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-AM-D 600Vac Motor Control Center AM-D 600Vac Auxiliary 633 633 Hallway 633 2-ARA-2 Reactor Protection Train 'A' Auxiliary Relay Cabinet #2 120/208Vac Misc Safety Related Power Distribution Auxiliary 633 Control Room 123 2-ARB-2 Reactor Protection Train 'B' Auxiliary Relay Cabinet #2 120/208Vac Misc Safety Related Power Distribution Auxiliary 633 Control Room 123 2-AZV-A 600Vac Valve Control Center AZV-A 600Vac Auxiliary 609 609 Hallway 609 2-BATT-AB Plant Battery AB 250Vdc Auxiliary 609 AB BATT Equip Area 200 2-BATT-AB-SH Plant Battery BATT-AB Ammeter Shunt 250Vdc Auxiliary 613 4kv Room -
Mezzanine Area 205 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 11 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-BATT-CD Plant Battery CD 250Vdc Auxiliary 626 CD BATT Equip Area 201 2-BATT-CD-SH Plant Battery BATT-CD Ammeter Shunt Cabinet 250Vdc Auxiliary 626 CD BATT Equip Area 201 2-BATT-N Train 'N' Plant Battery 250Vdc Control and Instrumentation Auxiliary 633 Plant Battery Train 'N' Auxiliary Equipment Room 263 2-BATT-N-SH Train 'N' Plant Battery Ammeter Shunt Cabinet 250Vdc Control and Instrumentation Auxiliary 633 633 Hallway 633 2-BC-A Battery Charger A for N-Train Battery 250Vdc Control and Instrumentation Auxiliary 633 633 Hallway 633 2-BC-AB1 Plant Battery BATT-AB Battery Charger #1 250Vdc Auxiliary 613 4kv Room -
Mezzanine Area 205 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 12 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-BC-AB2 Plant Battery BATT-AB Charger #2 250Vdc Auxiliary 613 4kv Room -
Mezzanine Area 205 2-BC-AB-SH Plant Battery Charger Ammeter BC-AB Shunt Cabinet 250Vdc Auxiliary 613 4kv Room -
Mezzanine Area 205 2-BC-B Battery Charger B for N-Train Battery 250Vdc Control and Instrumentation Auxiliary 633 633 Hallway 633 2-BC-CD1 Plant Battery BATT-CD Charger #1 250Vdc Auxiliary 626 CD BATT Equip Area 201 2-BC-CD2 Plant Battery BATT-CD Charger #2 250Vdc Auxiliary 626 CD BATT Equip Area 201 2-BC-CD-SH Plant Battery Charger BC-CD Shunt Cabinet 250Vdc Auxiliary 626 CD BATT Equip Area 201 2-BCTC-AB Plant Battery Chargers BC-AB1 and BC-AB2 Transfer Switch Cabinet 250Vdc Auxiliary 613 4kv Room -
Mezzanine Area 205 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 13 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-BCTC-CD Plant Battery Chargers BC-CD1 and BC-CD2 Transfer Cabinet 250Vdc Auxiliary 626 CD BATT Equip Area 201 2-BLI-110 Steam Generator OME-3-1 Wide Range Level Indicator Transmitter Main Steam Containment 612 Accumulator Tank #1 Area 68 2-BLI-120 Steam Generator OME-3-2 Wide Range Level Indicator Transmitter Main Steam Containment 612 West Containment Lower Vent Room 73 2-BLI-130 Steam Generator OME-3-3 Wide Range Level Indicator Transmitter Main Steam Containment 612 Accumulator Tank #3 Area 70 2-BLI-140 Steam Generator OME-3-4 Wide Range Level Indicator Transmitter Main Steam Containment 612 Accumulator Tank #4 Area 71 2-BLP-110 Steam Generator OME-3-1 Channel 4 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 Accumulator Tank #1 Area 68 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 14 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-BLP-111 Steam Generator OME-3-1 Channel 2 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 East Containment Lower Vent Room 72 2-BLP-112 Steam Generator OME-3-1 Channel 3 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 East Containment Lower Vent Room 72 2-BLP-120 Steam Generator OME-3-2 Channel 4 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 West Containment Lower Vent Room 73 2-BLP-121 Steam Generator OME-3-2 Channel 1 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 West Containment Lower Vent Room 73 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 15 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-BLP-122 Steam Generator OME-3-2 Channel 3 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 Accumulator Tank #2 Area 69 2-BLP-130 Steam Generator OME-3-3 Channel 4 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 West Containment Lower Vent Room 73 2-BLP-131 Steam Generator OME-3-3 Channel 1 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 West Containment Lower Vent Room 73 2-BLP-132 Steam Generator OME-3-3 Channel 3 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 West Containment Lower Vent Room 73 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 16 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-BLP-140 Steam Generator OME-3-4 Channel 4 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 East Containment Lower Vent Room 72 2-BLP-141 Steam Generator OME-3-4 Channel 2 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 East Containment Lower Vent Room 72 2-BLP-142 Steam Generator OME-3-4 Channel 3 Reactor Protection Input Narrow Range Level Transmitter Main Steam Containment 612 Accumulator Tank #4 Area 71 2-CA-711 Containment 85 PSI Control Air Ring Header #2 to Control Valve NRV-152 Check Valve Control Air Containment 625 Lower Containment, Quadrant #4 63 2-CA-713 Containment 85 PSI Control Air Ring Header to Control Valve NRV-153 Check Valve Control Air Containment 625 Lower Containment, Quadrant #4 63 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 17 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CAS Containment Auxiliaries Subpanel (Ventilation)
Containment Ventilation Auxiliary 633 633 Hallway 633 2-CCV-AB 250Vdc Train 'B' Critical Solenoid Valves Distribution Panel 250Vdc Auxiliary 633 Control Room 123 2-CCV-CD 250Vdc Train 'A' Critical Solenoid Valves Distribution Panel 250Vdc Auxiliary 633 Control Room 123 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 18 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 19 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CMO-410 East CCW Heat Exchanger HE-15E CCW Outlet Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 2-CMO-411 CCW Pumps Suction Crosstie Train 'A' Misc. Service Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 2-CMO-412 CCW Pumps Discharge Crosstie Train 'A' Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 2-CMO-413 CCW Pumps Suction Crosstie Train 'B' Misc. Service Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 2-CMO-414 CCW Pumps Discharge Crosstie Train 'B' Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 2-CMO-415 CCW to Miscellaneous Service Train 'A' Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 20 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CMO-416 CCW to Miscellaneous Service Header 'B' 16" Motor Operated Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 2-CMO-419 East RHR Heat Exchanger HE-17E CCW Outlet Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 2-CMO-420 West CCW Heat Exchanger HE-15W CCW Outlet Shutoff Valve Component Cooling Water Auxiliary 609 609 Hallway 609 2-CMO-429 West RHR Heat Exchanger HE-17W CCW Outlet Shutoff Valve Component Cooling Water Auxiliary 633 633 Hallway 633 2-CPS-312 AB Emergency Diesel Jacket Water Pump QT-130-AB1 Discharge Pressure Switch Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-CPS-314 AB Emergency Diesel Jacket Water Pump QT-130-AB2 Discharge Pressure Switch Diesel Jacket Water Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 21 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CPS-317 CD Emergency Diesel Jacket Water Pump QT-130-CD1 Discharge Pressure Switch Diesel Jacket Water Auxiliary 587 CD EDG Room 122 2-CPS-319 CD Emergency Diesel Jacket Water Pump QT-130-CD2 Discharge Pressure Switch Diesel Jacket Water Auxiliary 587 CD EDG Room 122 2-CPS-410 East Component Cooling Water Pump PP-10E Discharge Pressure Switch Component Cooling Water Auxiliary 609 609 Hallway 609 2-CPS-420 West Component Cooling Water Pump PP-10w Discharge Pressure Switch Component Cooling Water Auxiliary 609 609 Hallway 609 2-CRAB 250Vdc Control Room Distribution Panel CRAB 250Vdc Auxiliary 633 Control Room 123 2-CRCD 250Vdc Control Room Distribution Panel CRCD 250Vdc Auxiliary 633 Control Room 123 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 22 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CRID-I 120Vac Control Room Instrument Distribution Channel I Distribution Panel 120Vac Control Room Instrumentation Distr Auxiliary 633 Control Room 123 2-CRID-I-CVT 120Vac Control Room Instrument Distribution Channel I Constant Voltage Transformer 120Vac Control Room Instrumentation Distr Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-CRID-II 120Vac Control Room Instrument Distribution Channel II Distribution Panel 120Vac Control Room Instrumentation Distr Auxiliary 633 Control Room 123 2-CRID-II-CVT 120Vac Control Room Instrument Distribution Channel II Constant Voltage Transformer 120Vac Control Room Instrumentation Distr Auxiliary 609 4kv Room -
600v Switchgear Area 204 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 23 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CRID-III 120Vac Control Room Instrument Distribution Channel III Distribution Panel 120Vac Control Room Instrumentation Distr Auxiliary 633 Control Room 123 2-CRID-III-CVT 120Vac Control Room Instrument Distribution Channel III Constant Voltage Transformer 120Vac Control Room Instrumentation Distr Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-CRID-III-INV 120Vac Control Room Instrumentation Distribution System Channel III Inverter 120Vac Control Room Instrumentation Distr Auxiliary 609 Inverter Area 202 2-CRID-II-INV 120Vac Control Room Instrument Distribution System Channel II Inverter 120Vac Control Room Instrumentation Distr Auxiliary 609 Inverter Area 202 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 24 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CRID-I-INV 120Vac Control Room Instrument Distribution System Channel I Inverter 120Vac Control Room Instrumentation Distr Auxiliary 609 Inverter Area 202 2-CRID-IV 120Vac Control Room Instrument Distribution Channel IV Distribution Panel 120Vac Control Room Instrumentation Distr Auxiliary 633 Control Room 123 2-CRID-IV-CVT 120Vac Control Room Instrument Distribution Channel IV Constant Voltage Transformer 120Vac Control Room Instrumentation Distr Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-CRID-IV-INV 120Vac Control Room Instrument Distribution System Channel IV Inverter 120Vac Control Room Instrumentation Distr Auxiliary 609 Control Room 123 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 1 of 5 Page: 25 of 25 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CS-304 CVCS Reciprocating Charging Pump Inlet Isolation Valve (CVCS)
Charging Auxiliary 587 Reciprocating Charging Pump Room 39 2-CS-306 CVCS Reciprocating Charging Pump Outlet Isolation Valve (CVCS)
Charging Auxiliary 587 Reciprocating Charging Pump Room 39 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
1 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-CTR-415 East Component Cooling Water Heat Exchanger HE-15E CCW Outlet Temperature Recorder Thermal Sensor Component Cooling Water Auxiliary 609 609 Hallway 609 2-CTR-425 West Component Cooling Water Heat Exchanger CCW Outlet Temperature Recorder Thermal Sensor Component Cooling Water Auxiliary 609 609 Hallway 609 2-DCN 250Vdc Distribution Panel DCN 250Vdc Control and Instrumentation Auxiliary 633 633 Hallway 633 2-DCR-310 Steam Generator OME-3-1 Blowdown Containment Isolation Valve Blowdown Auxiliary 591 Startup Blowdown Flashtank Room 29 2-DCR-320 Steam Generator OME-3-2 Blowdown Containment Isolation Valve Blowdown Auxiliary 591 Startup Blowdown Flashtank Room 29 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
2 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-DCR-330 Steam Generator OME-3-3 Blowdown Containment Isolation Valve Blowdown Auxiliary 591 Startup Blowdown Flashtank Room 29 2-DCR-340 Steam Generator OME-3-4 Blowdown Containment Isolation Valve Blowdown Auxiliary 591 Startup Blowdown Flashtank Room 29 2-DG-102A AB Emergency Diesel Starting Air Compressor QT-142-AB2 Outlet Check Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-DG-102C CD Emergency Diesel Starting Air Compressor QT-142-CD2 Outlet Check Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-DG-104A AB Emergency Diesel Starting Air Compressor QT-142-AB1 Outlet Check Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
3 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-DG-104C CD Emergency Diesel Starting Air Compressor QT-142-CD1 Outlet Check Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-DGAB AB Emergency Diesel Generator OME-150-AB Control Subpanel Diesel Generator, Control &
Instrumentation Auxiliary 587 AB EDG Room 121 2-DGAB-FFCKT AB Emergency Diesel Generator OME-150-AB Field Flash Circuit Transformer Diesel Generator, Control &
Instrumentation Auxiliary 587 AB EDG Room 121 2-DGAB-INV AB Emergency Diesel Generator OME-150-AB Inverter Diesel Generator, Control &
Instrumentation Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
4 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-DGAB-X Equip Ctrl and Indication STN/AB Emergency Diesel Generator 150 Aux Panel Diesel Generator, Control &
Instrumentation Auxiliary 587 AB EDG Room 121 2-DGCD CD Emergency Diesel Generator OME-150-CD Control Subpanel Diesel Generator, Control &
Instrumentation Auxiliary 587 CD EDG Room 122 2-DGCD-FFCKT CD Emergency Diesel Generator OME-150-CD Field Flash CKT Transformer Diesel Generator, Control &
Instrumentation Auxiliary 587 CD EDG Room 122 2-DGCD-INV CD Emergency Diesel Generator OME-150-CD Inverter Diesel Generator, Control &
Instrumentation Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
5 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-DGCD-X Equip Ctrl and Indication STN/CD Emergency Diesel Generator 150 Aux Panel Diesel Generator, Control &
Instrumentation Auxiliary 587 CD EDG Room 122 2-DW-163N Control Room Vent North Chill Water Circulation Manual Isolation Valve Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-DW-163S Control Room Vent South Chill Water Circulation Manual Isolation Valve Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-ELSC 120/208 Vac Emergency Local Shutdown Distribution Panel 120/208Vac Misc Safety Related Power Distribution Auxiliary 587 AB EDG Room 121 2-ELSCX 120/208Vac Emergency Local Shutdown Auxiliary Distribution Panel 120/208Vac Misc Safety Related Power Distribution Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
6 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-ESW-240 ESW Supply Valve to Turbine-Driven AFW Pump PP-4 Essential Service Water Turbine 591 TDAFP Room 49 2-ESW-243 ESW Supply Valve to Motor-Driven AFW Pump PP-3W Essential Service Water Turbine 591 West MDAFP Room 51 2-EZC-A 600Vac Motor Control Center EZC-A 600Vac Auxiliary 613 4kv Room -
Mezzanine Area 205 2-EZC-B 600Vac Motor Control Center EZC-B 600Vac Auxiliary 613 4kv Room -
Mezzanine Area 205 2-EZC-C 600Vac Motor Control Center EZC-C 600Vac Auxiliary 613 4kv Room -
Mezzanine Area 205 2-EZC-D 600Vac Motor Control Center EZC-D 600Vac Auxiliary 613 4kv Room -
Mezzanine Area 205 2-FFC-210 Feedwater to Steam Generator #1 Channel I Flow Control Transmitter Feedwater Auxiliary 621 East Main Steam Stop Enclosure 10 2-FFC-211 Feedwater to Steam Generator #1 Channel II Flow Control Transmitter Feedwater Auxiliary 621 East Main Steam Stop Enclosure 11 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
7 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-FFC-220 Feedwater to Steam Generator #2 Channel I Flow Control Transmitter Feedwater Auxiliary 587 West Feedwater Regulating Valve Area 48 2-FFC-221 Feedwater to Steam Generator #2 Channel II Flow Control Transmitter Feedwater Auxiliary 587 West Feedwater Regulating Valve Area 48 2-FFC-230 Feedwater to Steam Generator #3 Channel I Flow Control Transmitter Feedwater Auxiliary 587 West Feedwater Regulating Valve Area 48 2-FFC-231 Feedwater to Steam Generator #3 Channel II Flow Control Transmitter Feedwater Auxiliary 587 West Feedwater Regulating Valve Area 48 2-FFC-240 Feedwater to Steam Generator #4 Channel I Flow Control Transmitter Feedwater Auxiliary 612 East Feedwater Regulating Valve Area 13 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
8 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-FFC-241 Feedwater to Steam Generator #4 Channel II Flow Control Transmitter Feedwater Auxiliary 612 East Feedwater Regulating Valve Area 13 2-FFI-210 Auxiliary Feedwater to Steam Generator OME-3-1 Flow Indicator Transmitter Auxiliary Feedwater Auxiliary 621 East Main Steam Stop Enclosure 10 2-FFI-220 Auxiliary Feedwater to Steam Generator OME-3-2 Flow Indicator Transmitter Auxiliary Feedwater Auxiliary 621 West Main Steam Stop Enclosure 9
2-FFI-230 Auxiliary Feedwater to Steam Generator OME-3-3 Flow Indicator Transmitter Auxiliary Feedwater Auxiliary 621 West Main Steam Stop Enclosure 9
2-FFI-240 Auxiliary Feedwater to Steam Generator OME-3-4 Flow Indicator Transmitter Auxiliary Feedwater Auxiliary 621 East Main Steam Stop Enclosure 10 2-FFS-244 West Motor Driven Auxiliary Feedwater Pump PP-3W Discharge Flow Switch Auxiliary Feedwater Turbine 591 West MDAFP Room 51 2-FFS-245 West Motor Driven Auxiliary Feedwater Pump PP-3W Discharge Flow Switch Auxiliary Feedwater Turbine 591 West MDAFP Room 51 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page:
9 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-FFS-254 East Motor Driven Auxiliary Feedwater Pump PP-3E Discharge Flow Switch Auxiliary Feedwater Turbine 591 Auxiliary Feed Pump East Hallway 83 2-FFS-255 East Motor Driven Auxiliary Feedwater Pump PP-3E Discharge Flow Switch Auxiliary Feedwater Turbine 591 Auxiliary Feed Pump East Hallway 83 2-FFS-258 Turbine Driven Auxiliary Feedwater Pump PP-4 Discharge Flow Switch Auxiliary Feedwater Turbine 591 Auxiliary Feed Pump East Hallway 83 2-FFS-260 Turbine Driven Auxiliary Feedwater Pump PP-4 Discharge Flow Switch Auxiliary Feedwater Turbine 591 TDAFP Room 49 2-FMO-211 Turbine Driven Auxiliary Feed Pump PP-4 Discharge to Steam Generator OME-3-1 4" Motor Operated Control Valve Auxiliary Feedwater Auxiliary 612 East Main Steam Stop Enclosure 10 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 10 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-FMO-212 West Motor Driven Auxiliary Feedwater Pump PP-3W Supply to Steam Generator OME-3-1 4" Motor Operated Control Valve Auxiliary Feedwater Auxiliary 612 East Main Steam Stop Enclosure 10 2-FMO-221 Turbine Driven Auxiliary Feed Pump PP-4 Discharge to Steam Generator OME-3-2 4" Motor Operated Control Valve Auxiliary Feedwater Auxiliary 591 Startup Blowdown Flashtank Room 29 2-FMO-222 East Motor Driven Auxiliary Feedwater Pump PP-3E Supply to Steam Generator OME-3-2 4" Motor Operated Control Valve Auxiliary Feedwater Auxiliary 591 Startup Blowdown Flashtank Room 29 2-FMO-231 Turbine Driven Auxiliary Feed Pump PP-4 Supply to Steam Generator OME-3-3 4" Motor Operated Control Valve Auxiliary Feedwater Auxiliary 591 Startup Blowdown Flashtank Room 29 2-FMO-232 East Motor Driven Auxiliary Feedwater Pump PP-3E Supply to Steam Generator OME-3-3 4" Motor Operated Control Valve Auxiliary Feedwater Auxiliary 591 Startup Blowdown Flashtank Room 29 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 11 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-FMO-241 Turbine Driven Auxiliary Feed Pump PP-4 Supply to Steam Generator OME-3-4 4" Motor Operated Control Valve Auxiliary Feedwater Auxiliary 612 East Main Steam Stop Enclosure 10 2-FMO-242 West Motor Driven Auxiliary Feedwater Pump PP-3W Supply to Steam Generator OME-3-4 4" Motor Operated Control Valve Auxiliary Feedwater Auxiliary 612 East Main Steam Stop Enclosure 10 2-FRV-210 Steam Generator OME-3-1 Feedwater Regulating Valve Feedwater Auxiliary 612 East Feedwater Regulating Valve Area 13 2-FRV-220 Steam Generator OME-3-2 Feedwater Regulating Valve Feedwater Auxiliary 587 West Feedwater Regulating Valve Area 48 2-FRV-230 Steam Generator OME-3-3 Feedwater Regulating Valve Feedwater Auxiliary 587 West Feedwater Regulating Valve Area 48 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 12 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-FRV-240 Steam Generator OME-3-4 Feedwater Regulating Valve Feedwater Auxiliary 612 East Feedwater Regulating Valve Area 13 2-FRV-245 West Motor Driven Auxiliary Feed Pump PP-3W 2" Air Operated Test Valve Auxiliary Feedwater Turbine 591 West MDAFP Room 51 2-FRV-247 West Motor Driven Auxiliary Feed Pump PP-3W Emergency 1" Air Operated Leakoff Globe Valve Auxiliary Feedwater Turbine 591 West MDAFP Room 51 2-FRV-255 East Motor Driven Auxiliary Feedwater Pump PP-3E 2" Air Operated Test Valve Auxiliary Feedwater Turbine 591 East MDAFP Room 50 2-FRV-256 Turbine Driven Auxiliary Feed Pump PP-4 2" Air Operated Test Valve Auxiliary Feedwater Turbine 591 TDAFP Room 49 2-FRV-257 East Motor Driven Auxiliary Feedwater Pump PP-3E Emergency 1" Air Operated Leakoff Valve Auxiliary Feedwater Turbine 591 East MDAFP Room 50 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 13 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-FRV-258 Turbine Driven Auxiliary Feed Pump PP-4 Emergency 1" Air Operated Leakoff Globe Valve Auxiliary Feedwater Turbine 591 TDAFP Room 49 2-FW-118-1 Feedwater to Steam Generator #1 Containment Isolation Check Valve Feedwater Auxiliary 621 East Main Steam Stop Enclosure 10 2-FW-118-2 Feedwater to Steam Generator #2 Containment Isolation Check Valve Feedwater Auxiliary 621 West Main Steam Stop Enclosure 9
2-FW-118-3 Feedwater to Steam Generator #3 Containment Isolation Check Valve Feedwater Auxiliary 621 West Main Steam Stop Enclosure 9
2-FW-118-4 Feedwater to Steam Generator #4 Containment Isolation Check Valve Feedwater Auxiliary 621 East Main Steam Stop Enclosure 10 2-FW-129 East Motor Driven Aux Feedwater Pump PP-3E Disc to Unit 1 Crosstie Shutoff Valve Auxiliary Feedwater Turbine 591 East MDAFP Room 50 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 14 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HE-11 Reactor Coolant Pump Seal Water Heat Exchanger (Pressure Boundary Only)
Reactor Coolant Pump Seal Water INJ/Leakoff Auxiliary 609 Seal Water Heat Exchanger Room 18 2-HE-15E East CCW Heat Exchanger Component Cooling Water Auxiliary 609 609 Hallway 609 2-HE-15W West CCW Heat Exchanger Component Cooling Water Auxiliary 609 609 Hallway 609 2-HE-17E East Residual Heat Removal Heat Exchanger Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
2-HE-17W West Residual Heat Removal Heat Exchanger Residual Heat Removal Auxiliary 609 West RHR Heat Exchanger Room 6
2-HE-32E East Residual Heat Removal Pump PP-35E Mechanical Seal Heat Exchanger Component Cooling Water Auxiliary 573 East RHR Pump Room 54 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 15 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HE-32W West Residual Heat Removal Pump PP-35W Mechanical Seal Heat Exchanger Component Cooling Water Auxiliary 573 West RHR Pump Room 55 2-HE-34NE North Safety Injection Pump Mech Seal Heat Exchanger Component Cooling Water Auxiliary 587 North Safety Injection Pump Room 42 2-HE-34NW North Safety Injection Pump Mech Seal Heat Exchanger Component Cooling Water Auxiliary 587 North Safety Injection Pump Room 42 2-HE-34SE South Safety Injection Pump Mech Seal Heat Exchanger Component Cooling Water Auxiliary 587 South Safety Injection Pump Room 43 2-HE-34SW South Safety Injection Pump Mech Seal Heat Exchanger Component Cooling Water Auxiliary 587 South Safety Injection Pump Room 43 2-HE-35N North Safety Injection Pump Oil Cooler Component Cooling Water Auxiliary 587 North Safety Injection Pump Room 42 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 16 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HE-35S South Safety Injection Pump Oil Cooler Component Cooling Water Auxiliary 587 South Safety Injection Pump Room 43 2-HE-37E East Centrifugal Charging Pump Gear Oil Cooler Component Cooling Water Auxiliary 587 East Centrifugal Charging Pump Room 40 2-HE-37W West Centrifugal Charging Pump Gear Oil Cooler Component Cooling Water Auxiliary 587 West Centrifugal Charging Pump Room 41 2-HE-38E East Centrifugal Charging Pump Bearing Oil Cooler Component Cooling Water Auxiliary 587 East Centrifugal Charging Pump Room 40 2-HE-38W West Centrifugal Charging Pump Bearing Oil Cooler Component Cooling Water Auxiliary 587 West Centrifugal Charging Pump Room 41 2-HE-47-ABN AB Emergency Diesel North Combustion Air Aftercooler Diesel Combustion Air Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 17 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HE-47-ABS AB Emergency Diesel South Combustion Air Aftercooler Diesel Combustion Air Auxiliary 587 AB EDG Room 121 2-HE-47-CDN CD Emergency Diesel North Combustion Air Aftercooler Diesel Combustion Air Auxiliary 587 CD EDG Room 122 2-HE-47-CDS CD Emergency Diesel South Combustion Air Aftercooler Diesel Combustion Air Auxiliary 587 CD EDG Room 122 2-HE-63N Control Room Air Conditioning North Liquid Chiller HV-ACR-1 Evaporator Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HE-63S Control Room Air Conditioning South Liquid Chiller HV-ACR-2 Evaporator Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HE-64N Control Room Air Conditioning North Liquid Chiller HV-ACR-1 Condenser Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HE-64S Control Room Air Conditioning South Liquid Chiller HV-ACR-2 Condenser Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 18 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-ACR-1 Control Room Air Conditioning North Liquid Chiller Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HV-ACR-2 Control Room Air Conditioning South Liquid Chiller Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HV-ACRA-1 Control Room Ventilation North Air Conditioning Unit Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HV-ACRA-2 Control Room Ventilation South Air Conditioning Unit Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HV-ACR-DA-1 Outside Air to Control Room Ventilation Units HV-ACRA-1 and HV-ACRA-2 Vent Damper Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HV-ACR-DA-2 Control Room Ventilation Outside Air Intake Damper Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HV-ACR-DA-3 Control Room Ventilation Return Air Damper Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 19 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-ACRF-1 Control Room Pressurizer/Cleanup Filter Supply Fan Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HV-ACRF-2 Control Room Pressurizer/Cleanup Filter Supply Fan Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-HV-AES-1 Auxiliary Building Ventilation Engineered Safety Feature Exhaust - Unit 1 Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AES-1 (FLT) Auxiliary Building Ventilation Engineered Safety Feature Exhaust Air Filter Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AES-1D1 Auxiliary Building Ventilation Engineered Safety Feature Exhaust Unit HV-AES-1 Charcoal Filter Bypass Damper #1 Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AES-1D2 Auxiliary Building Ventilation Engineered Safety Feature Exhaust Unit HV-AES-1 Charcoal Filter Bypass Damper #2 Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 20 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-AES-1D3 Aux Building Ventilation Engineered Safety Feature Exhaust Unit HV-AES-1 Charcoal Filter Face Damper Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AES-2 Auxiliary Building Ventilation Engineered Safety Feature Exhaust Unit Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AES-2 (FLT)
Auxiliary Building Ventilation Engineered Safety Feature Exhaust Air Filter Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AES-2D1 Aux Building Ventilation Engineered Safety Feature Exhaust Unit HV-AES-2 Charcoal Filter Bypass Damper #1 Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AES-2D2 Aux Building Ventilation Safety Feature Exhaust Unit HV-AES-2 Charcoal Filter Bypass Damper #2 Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 21 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-AES-2D3 Aux Building Ventilation Engineered Safety Feature Exhaust Unit HV-AES-2 Charcoal Filter Face Damper Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AFP-BRE-1 Train 'N' Battery Room East Exhaust Fan AFW Battery Rm Ventilation Auxiliary 633 Plant Battery Train 'N' Auxiliary Equipment Room 263 2-HV-AFP-BRE-2 Train 'N' Battery Room West Exhaust Fan Auxiliary Building Ventilation Auxiliary 633 Normal Blowdown Flashtank Room 8
2-HV-AFP-EAC East Motor Driven Auxiliary Feedwater Pump Room Cooler Turbine Building Ventilation Turbine 591 East MDAFP Room 50 2-HV-AFP-T1AC Turbine Driven Auxiliary Feedwater Pump Room Cooler Turbine Building Ventilation Turbine 591 TDAFP Room 49 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 22 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-AFP-T2AC Turbine Driven Auxiliary Feedwater Pump Room Cooler Turbine Building Ventilation Turbine 591 TDAFP Room 49 2-HV-AFP-WAC West Motor Driven Auxiliary Feedwater Pump Room Cooler Turbine Building Ventilation Turbine 591 West MDAFP Room 51 2-HV-DDP-AB1 AB Emergency Diesel Generator Room Ventilation Exhaust Fan HV-DGX-2 Tempering Air Damper Emergency Diesel Generator Room Ventilation Auxiliary 587 AB EDG Room 121 2-HV-DDP-AB2 AB Emergency Diesel Generator Room Ventilation Supply Fan HV-DGS-2 Tempering Air Damper Emergency Diesel Generator Room Ventilation Auxiliary 587 AB EDG Room 121 2-HV-DDP-CD1 CD Emergency Diesel Generator Room Ventilation Exhaust Fan HV-DGX-1 Tempering Air Damper Emergency Diesel Generator Room Ventilation Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 2 of 5 Page: 23 of 23 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-DDP-CD2 CD Emergency Diesel Generator Room Ventilation Supply Fan HV-DGS-1 Tempering Air Damper Diesel Room Ventilation Auxiliary 587 CD EDG Room 122 2-HV-DGS-1 CD Emergency Diesel Generator Room Ventilation Supply Fan Diesel Room Ventilation Auxiliary 587 CD EDG Room 122 2-HV-DGS-2 AB Emergency Diesel Generator Room Ventilation Supply Fan Diesel Room Ventilation Auxiliary 587 AB EDG Room 121 2-HV-DGS-3 AB Emergency Diesel Generator Room Cabinet Ventilation Supply Fan Diesel Room Ventilation Auxiliary 587 AB EDG Room 121 2-HV-DGS-4 CD Emergency Diesel Generator Room Cabinet Ventilation Supply Fan Diesel Room Ventilation Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
1 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-DGS-DAB AB Emergency Diesel Generator Room Ventilation Supply Fan HV-DGS-1 Outside Air Shutoff Damper Diesel Room Ventilation Auxiliary 609 Inner Plant Grounds 244 2-HV-DGS-DCD CD Emergency Diesel Generator Room Ventilation Supply Fan HV-DGS-2 Outside Air Shutoff Damper Emergency Diesel Generator Room Ventilation Auxiliary 596 Reactor Cable Tunnel Quad #3 26 2-HV-DGX-1 CD Emergency Diesel Generator Room Ventilation Exhaust Fan Emergency Diesel Generator Room Ventilation Auxiliary 587 CD EDG Room 122 2-HV-DGX-2 AB Emergency Diesel Generator Room Ventilation Exhaust Fan Emergency Diesel Generator Room Ventilation Auxiliary 587 AB EDG Room 121 2-HV-SGR-MD-1 Control Rod Drive Equipment Room and Inverter Area Ventilation Recirculating Air Inlet Damper ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
2 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-SGR-MD-2 Control Rod Drive Equipment Room and Inverter Area Ventilation Outside Air Inlet Damper ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-HV-SGR-MD-3 4kv Rm 600 Volt Switchgear Xformers TR21A & TR21C Area Vent Supply Fan HV-SGRS-8 Suction Damper ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-HV-SGR-MD-4 4kv Room 600v Switchgear Transformers Area Ventilation Supply Fan HV-SGRS-7 Suction Damper ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-HV-SGR-MD-5 600Vac Motor Control Center Mezzanine Area Ventilation Supply Fan HV-SGRS-9 Vent Damper ELEC. SWGR.
Ventilation Auxiliary 613 4kv Room -
Mezzanine Area 205 2-HV-SGRS-1A Control Rod Drive Equipment Room and Inverter Area Ventilation North Supply Fan ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-HV-SGRS-2 4kv Room AB 4kv Switchgear Area Ventilation Supply Fan ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
3 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-SGRS-3 4kv Room CD 4kv Switchgear Area Ventilation Supply Fan ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-HV-SGRS-4A Control Rod Drive Equipment Room and Inverter Area Ventilation South Supply Fan ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-HV-SGRS-7 4kv Room 600 Volt Switchgear Transformers TR21B and TR21D Area Ventilation Supply Fan ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-HV-SGRS-8 4kv Room 600 Volt Switchgear Transformers TR21A and TR21C Area Ventilation Supply Fan ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-HV-SGRS-9 600Vac Motor Control Center Mezzanine Area Ventilation Supply Fan ELEC. SWGR.
Ventilation Auxiliary 613 4kv Room -
Mezzanine Area 205 2-HV-SGRX-2 4kv Room AB 4kv Switchgear Area Ventilation Exhaust Fan ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
4 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-HV-SGRX-3 4kv Room CD 4kv Switchgear Area Ventilation Exhaust Fan ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-HV-SGRX-5 AB Battery Equipment Area Battery Room Ventilation Exhaust Fan ELEC. SWGR.
Ventilation Auxiliary 609 AB BATT Equip Area 200 2-HV-SGRX-6 CD Battery Equipment Area Battery Room Ventilation Exhaust Fan ELEC. SWGR.
Ventilation Auxiliary 626 CD BATT Equip Area 201 2-ICM-111 RHR to Reactor Coolant Loops #2 & #3 Cold Legs Containment Isolation Valve Residual Heat Removal Containment 598 Annulus -
Quadrant #2 59 2-ICM-129 Reactor Coolant Loop #2 Hot Leg to Residual Heat Removal Pumps Suction Containment Isolation Valve Residual Heat Removal Containment 598 Annulus -
Quadrant #2 59 2-ICM-250 Boron Injection Tank Train 'A' Outlet Containment Isolation Valve Boron Injection Auxiliary 612 BIT Outlet Valve Room 15 2-ICM-251 Boron Injection Tank Train 'B' Outlet Containment Isolation Valve Boron Injection Auxiliary 612 BIT Outlet Valve Room 15 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
5 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-ICM-260 North Safety Injection Pump PP-26N Discharge Containment Isolation Valve Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-ICM-265 South Safety Injection Pump PP-26S Discharge Containment Isolation Valve Safety Injection Auxiliary 587 South Safety Injection Pump Room 43 2-ICM-305 Recirculation Sump to East RHR/CTS Pumps Suction Containment Isolation Valve Residual Heat Removal Auxiliary 591 Vestibule 28 2-ICM-306 Recirculation Sump to West RHR/CTS Pumps Suction Containment Isolation Valve Residual Heat Removal Auxiliary 591 Vestibule 28 2-ICM-311 East Residual Heat Removal to RC Loops
- 1 and #4 Cold Legs Containment Isolation Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
2-ICM-321 West RHR to Reactor Coolant Loops #2 and #3 Cold Legs Containment Isolation Valve Residual Heat Removal Auxiliary 609 West RHR Heat Exchanger Room 6
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
6 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IFC-315 East Residual Heat Removal Pump PP-35E Discharge Flow Switch Residual Heat Removal Auxiliary 573 573 Hallway 573 2-IFC-325 West Residual Heat Removal Pump PP-35W Discharge Flow Switch Residual Heat Removal Auxiliary 573 573 Hallway 573 2-IFI-260 Safety Injection Pump Discharge Flow Indicator Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-IFI-266 Safety Injection Pump Discharge Flow Indicator Safety Injection Auxiliary 587 South Safety Injection Pump Room 43 2-IFI-310 East Residual Heat Removal Heat Exchanger HE-17E Outlet Low Range Flow Indicator Transmitter Residual Heat Removal Auxiliary 609 609 Hallway 609 2-IFI-311 East Residual Heat Removal Heat Exchanger HE-17E Outlet High Range Flow Indicator Transmitter Residual Heat Removal Auxiliary 609 609 Hallway 609 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
7 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IFI-320 West Residual Heat Removal Heat Exchanger HE-17W Outlet Low Range Flow Indicator Transmitter Residual Heat Removal Auxiliary 609 609 Hallway 609 2-IFI-321 West Residual Heat Removal Heat Exchanger HE-17W Outlet High Range Flow Indicator Transmitter Residual Heat Removal Auxiliary 609 609 Hallway 609 2-IFI-335 Residual Heat Removal to Reactor Coolant Loops #2 and #3 Cold Legs Flow Indicator Transmitter Residual Heat Removal Auxiliary 591 Vestibule 28 2-IFI-51 Boron Injection to Reactor Coolant Loop
Quadrant #1 58 2-IFI-52 Boron Injection to Reactor Coolant Loop
Quadrant #2 59 2-IFI-53 Boron Injection to Reactor Coolant Loop
Quadrant #3 56 2-IFI-54 Boron Injection to Reactor Coolant Loop
Quadrant #4 57 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
8 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IMO-128 Reactor Coolant Loop #2 Hot Leg to Residual Heat Removal Pumps Suction Shutoff Valve Residual Heat Removal Containment 617 Lower Containment, Quadrant #2 61 2-IMO-215 RWST to East Containment Spray Pump PP-9E Suction Motor Operated Shut-Off Valve Containment Spray Auxiliary 573 East Containment Spray Pump Room 53 2-IMO-225 RWST to West Containment Spray Pump PP-9W Suction Motor Operated Shut-Off Valve Containment Spray Auxiliary 573 West Containment Spray Pump Room 52 2-IMO-255 Boron Injection Tank Train 'A' Inlet Shutoff Valve Boron Injection Auxiliary 612 BIT Room 16 2-IMO-256 Boron Injection Tank Train 'B' Inlet Shutoff Valve Boron Injection Auxiliary 612 BIT Room 16 2-IMO-261 Refueling Water Storage Tank TK-33 Supply to Safety Injection Pumps Shutoff Valve Safety Injection Auxiliary 587 South Safety Injection Pump Room 43 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page:
9 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IMO-262 Safety Injection Pumps Recirc to Refueling Water Storage Tank TK-33 Train 'A' Shutoff Valve Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-IMO-263 Safety Injection Pumps Recirc to Refueling Water Storage Tank TK-33 Train 'B' Shutoff Valve Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-IMO-270 Safety Injection Pumps Discharge Crosstie Train 'A' Shutoff Valve Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-IMO-275 Safety Injection Pumps Discharge Crosstie Train 'B' Shutoff Valve Safety Injection Auxiliary 587 South Safety Injection Pump Room 43 2-IMO-310 East Residual Heat Removal Pump PP-35E Suction Shutoff Valve Residual Heat Removal Auxiliary 573 East RHR Pump Room 54 2-IMO-312 East Residual Heat Removal Heat Exchanger HE-17E Outlet Mini-Flow Line Shutoff Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 10 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IMO-314 East Residual Heat Removal Heat Exchanger 2-HE-17E to RC Loops #2 and
- 3 Cold Legs Shutoff Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
2-IMO-315 East RHR and North Safety Injection to Reactor Coolant Loops #1 and #4 Hot Legs Shutoff Valve Residual Heat Removal Containment 612 East Containment Lower Vent Room 72 2-IMO-316 East RHR and North Safety Injection to Reactor Coolant Loops #1 and #4 Cold Legs Shutoff Valve Residual Heat Removal Containment 612 East Containment Lower Vent Room 72 2-IMO-320 West Residual Heat Removal Pump PP-35W Suction Shutoff Valve Residual Heat Removal Auxiliary 573 West RHR Pump Room 55 2-IMO-322 West Residual Heat Removal Heat Exchanger HE-17W Outlet Mini-Flow Line Shutoff Valve Residual Heat Removal Auxiliary 609 West RHR Heat Exchanger Room 6
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 11 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IMO-324 West Residual Heat Removal Heat Exchanger 2-HE-17W to RC Loops #2 and
- 3 Cold Legs Shutoff Valve Residual Heat Removal Auxiliary 609 West RHR Heat Exchanger Room 6
2-IMO-325 West RHR and South Safety Injection to Reactor Coolant Loops #2 and #3 Hot Legs Shutoff Valve Residual Heat Removal Containment 612 West Containment Lower Vent Room 73 2-IMO-326 West RHR and South Safety Injection to Reactor Coolant Loops #2 and #3 Cold Legs Shutoff Valve Residual Heat Removal Containment 612 West Containment Lower Vent Room 73 2-IMO-330 East Residual Heat Removal to Upper Containment Spray Shutoff Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
2-IMO-331 West RHR to Upper Containment Spray Shutoff Valve Residual Heat Removal Auxiliary 609 West RHR Heat Exchanger Room 6
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 12 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IMO-340 East Residual Heat Removal Heat Exchanger to Charging Pumps Suction Shutoff Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
2-IMO-350 West RHR Heat Exchanger Outlet to Safety Injection Pump Suction Shutoff Valve Residual Heat Removal Auxiliary 609 West RHR Heat Exchanger Room 6
2-IMO-360 Safety Injection Pumps to CVCS Charging Pumps Suction Header Crosstie Shutoff Valve (CVCS)
Charging Auxiliary 587 West Centrifugal Charging Pump Room 41 2-IMO-361 Safety Injection Pumps Suction to and From Charging Pumps Suction Train 'A' Shutoff Valve Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-IMO-362 Safety Injection Pumps Suction to and From Charging Pumps Suction Train 'B' Shutoff Valve Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-IMO-390 Refueling Water Storage Tank TK-33 to Residual Heat Removal Pumps Suction Shutoff Valve Residual Heat Removal Auxiliary 591 Vestibule 28 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 13 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IMO-51 Boron Injection to Reactor Coolant Loop
Quadrant #1 58 2-IMO-52 Boron Injection to Reactor Coolant Loop
Quadrant #2 59 2-IMO-53 Boron Injection to Reactor Coolant Loop
Quadrant #3 56 2-IMO-54 Boron Injection to Reactor Coolant Loop
Quadrant #4 57 2-IMO-910 Refueling Water Storage Tank to CVCS Charging Pumps Suction Header Train 'A' Shutoff Valve (CVCS)
Charging Auxiliary 587 Reciprocating Charging Pump Room 39 2-IMO-911 Refueling Water Storage Tank to CVCS Charging Pumps Suction Header Train 'B' Shutoff Valve (CVCS)
Charging Auxiliary 587 East Centrifugal Charging Pump Room 40 2-IRV-310 East Residual Heat Removal Heat Exchanger HE-17E 8" Air Operated Outlet Flow Control Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 14 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-IRV-311 Residual Heat Removal Heat Exchangers Bypass Flow 8" Air Operated Control Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
2-IRV-320 West Residual Heat Removal Heat Exchanger HE-17W 8" Air Operated Outlet Flow Control Valve Residual Heat Removal Auxiliary 609 West RHR Heat Exchanger Room 6
2-IRV-60 Safety Injection to Accumulator Fill Line Control Valve Safety Injection Containment 598 Annulus -
Quadrant #2 59 2-ITR-335 Residual Heat Removal to Reactor Coolant Loops #2 & #3 Cold Legs Temperature Recorder Thermal Sensor Residual Heat Removal Auxiliary 591 Vestibule 28 2-LLS-120 AB Emergency Diesel Fuel Oil Day Tank QT-107-AB High Level Switch #1 Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 2-LLS-121 AB Emergency Diesel Fuel Oil Day Tank QT-107-AB Low Level Switch #1 Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 15 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-LLS-122 AB Emergency Diesel Fuel Oil Day Tank QT-107-AB High Level Switch #2 Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 2-LLS-123 AB Emergency Diesel Fuel Oil Day Tank QT-107-AB Low Level Switch #2 Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 2-LLS-125 CD Emergency Diesel Fuel Oil Day Tank QT-107-CD High Level Switch #1 Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-LLS-126 CD Emergency Diesel Fuel Oil Day Tank QT-107-CD Low Level Switch #1 Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-LLS-127 CD Emergency Diesel Fuel Oil Day Tank QT-107-CD High Level Switch #2 Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-LLS-128 CD Emergency Diesel Fuel Oil Day Tank QT-107-CD Low Level Switch #2 Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 16 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-LRV-240 AB Emergency Diesel Upper Valve Gear Lube Oil Regulator #1 Diesel Lube Oil Auxiliary 587 AB EDG Room 121 2-LRV-241 AB Emergency Diesel Upper Valve Gear Lube Oil Regulator #2 Diesel Lube Oil Auxiliary 587 AB EDG Room 121 2-LRV-245 CD Emergency Diesel Upper Valve Gear Oil Pressure Regulating Valve #1 Diesel Lube Oil Auxiliary 587 CD EDG Room 122 2-LRV-246 CD Emergency Diesel Upper Valve Gear Lube Oil Regulator #2 Diesel Lube Oil Auxiliary 587 CD EDG Room 122 2-LSO-240 AB Emergency Diesel Upper Valve Gear Lubrication Control Solenoid #1 Diesel Lube Oil Auxiliary 587 AB EDG Room 121 2-LSO-241 AB Emergency Diesel Upper Valve Gear Lubrication Control Solenoid #2 Diesel Lube Oil Auxiliary 587 AB EDG Room 121 2-LSO-245 CD Emergency Diesel Gen Upper Valve Gear Lubrication Control Solenoid #1 Diesel Lube Oil Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 17 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-LSO-246 CD Emergency Diesel Gen Upper Valve Gear Lubrication Control Solenoid #2 Diesel Lube Oil Auxiliary 587 CD EDG Room 122 2-MCAB 250Vdc Distribution Panel MCAB 250Vdc Auxiliary 609 AB BATT Equip Area 200 2-MCCD 250Vdc Distribution Panel MCCD 250Vdc Auxiliary 626 CD BATT Equip Area 201 2-MCM-221 Main Steam Lead #2 to Auxiliary Feed Pump Turbine 4" Motor Operated Shutoff Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MCM-231 Main Steam Lead #3 to Auxiliary Feed Pump Turbine 4" Motor Operated Shutoff Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MDAB 250Vdc Distribution Panel MDAB 250Vdc Auxiliary 609 AB BATT Equip Area 200 2-MDCD 250Vdc Distribution Panel MDCD 250Vdc Auxiliary 626 CD BATT Equip Area 201 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 18 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-MFC-110 Steam Generator OME-3-1 Channel I Steam Flow Control Transmitter Main Steam Containment 598 Annulus -
Quadrant #1 58 2-MFC-111 Steam Generator OME-3-1 Channel II Steam Flow Control Transmitter Main Steam Containment 598 Annulus -
Quadrant #1 58 2-MFC-120 Steam Generator OME-3-2 Channel II Steam Flow Control Transmitter Main Steam Containment 598 Annulus -
Quadrant #2 59 2-MFC-121 Steam Generator OME-3-2 Channel I Steam Flow Control Transmitter Main Steam Containment 598 Annulus -
Quadrant #2 59 2-MFC-130 Steam Generator OME-3-3 Channel II Steam Flow Control Transmitter Main Steam Containment 598 Annulus -
Quadrant #3 56 2-MFC-131 Steam Generator OME-3-3 Channel I Steam Flow Control Transmitter Main Steam Containment 598 Annulus -
Quadrant #3 56 2-MFC-140 Steam Generator OME-3-4 Channel I Steam Flow Control Transmitter Main Steam Containment 598 Annulus -
Quadrant #4 57 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 19 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-MFC-141 Steam Generator OME-3-4 Channel II Steam Flow Control Transmitter Main Steam Containment 598 Annulus -
Quadrant #4 57 2-MMO-210 Steam Stop Valve MRV-210 Steam Cylinder Dump 4" Motor Operated Valves Selector Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MMO-220 Steam Stop Valve MRV-220 Steam Cylinder Dump 4" Motor Operated Valves Selector Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MMO-230 Steam Stop Valve MRV-230 Steam Cylinder Dump 4" Motor Operated Valves Selector Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MMO-240 Steam Stop Valve MRV-240 Steam Cylinder Dump 4" Motor Operated Valves Selector Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MPP-210 Steam Generator OME-3-1 Channel I Steam Pressure Transmitter Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 20 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-MPP-211 Steam Generator OME-3-1 Channel II Steam Pressure Transmitter Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MPP-212 Steam Generator OME-3-1 Channel IV Reactor Protection Input Steam Pressure Transmitter Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MPP-220 Steam Generator OME-3-2 Channel I Steam Pressure Transmitter Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MPP-221 Steam Generator OME-3-2 Channel II Steam Pressure Transmitter Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MPP-222 Steam Generator OME-3-2 Channel III Reactor Protection Input Steam Pressure Transmitter Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MPP-230 Steam Generator OME-3-3 Channel I Steam Pressure Transmitter Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 21 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-MPP-231 Steam Generator OME-3-3 Channel II Steam Pressure Transmitter Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MPP-232 Steam Generator OME-3-3 Channel III Reactor Protection Input Steam Pressure Transmitter Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MPP-240 Steam Generator OME-3-4 Channel I Steam Pressure Transmitter Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MPP-241 Steam Generator OME-3-4 Channel II Steam Pressure Transmitter Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MPP-242 Steam Generator OME-3-4 Channel IV Reactor Protection Input Steam Pressure Transmitter Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MRV-210 Steam Generator OME-3-1 Stop Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 22 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-MRV-211 Steam Generator #1 Stop Valve MRV-210 Steam Cylinder Train 'A' Dump Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MRV-212 Steam Generator #1 Stop Valve MRV-210 Steam Cylinder Train 'B' Dump Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MRV-213 Steam Generator OME-3-1 Power Operated Relief Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MRV-220 Steam Generator OME-3-2 Stop Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MRV-221 Steam Generator #2 Stop Valve MRV-220 Steam Cylinder Train 'A' Dump Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MRV-222 Steam Generator #2 Stop Valve MRV-220 Steam Cylinder Train 'B' Dump Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 23 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-MRV-223 Steam Generator OME-3-2 Power Operated Relief Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MRV-230 Steam Generator OME-3-3 Stop Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MRV-231 Steam Generator #3 Stop Valve MRV-230 Steam Cylinder Train 'A' Dump Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MRV-232 Steam Generator #3 Stop Valve MRV-230 Steam Cylinder Train 'B' Dump Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MRV-233 Steam Generator OME-3-3 Power Operated Relief Valve Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-MRV-240 Steam Generator OME-3-4 Stop Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 24 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-MRV-241 Steam Generator #4 Stop Valve MRV-240 Steam Cylinder Train 'A' Dump Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MRV-242 Steam Generator #4 Stop Valve MRV-240 Steam Cylinder Train 'B' Dump Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-MRV-243 Steam Generator OME-3-4 Power Operated Relief Valve Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-NIS-I Nuclear Instrumentation System Protection Channel I Control Panel Equipment Control and Indication Stations Auxiliary 633 Control Room 123 2-NIS-III Nuclear Instrumentation System Protection Channel III Control Panel Equipment Control and Indication Stations Auxiliary 633 Control Room 123 2-NLI-151 Pressurizer OME-4 Level Indicator Transmitter Reactor Coolant Containment 612 Instrumentation Room 67 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 25 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NLP-151 Pressurizer OME-4 Protection Channel I Level Transmitter Reactor Coolant Containment 612 Instrumentation Room 67 2-NLP-152 Pressurizer OME-4 Protection Channel II Level Transmitter Reactor Coolant Containment 612 Instrumentation Room 67 2-NLP-153 Pressurizer OME-4 Protection Channel III Level Transmitter Reactor Coolant Containment 612 Instrumentation Room 67 2-NMO-151 Pressurizer Relief Valve NRV-151 Upstream 3" Motor Operated Shutoff Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NMO-152 Pressurizer Relief Valve NRV-152 Upstream 3" Motor Operated Shutoff Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NMO-153 Pressurizer Relief Valve NRV-153 Upstream 3" Motor Operated Shutoff Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NPP-151 Pressurizer OME-4 Protection Channel I Pressure Transmitter Reactor Coolant Containment 612 Instrumentation Room 67 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 3 of 5 Page: 26 of 26 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NPP-152 Pressurizer OME-4 Protection Channel II Pressure Transmitter Reactor Coolant Containment 612 Instrumentation Room 67 2-NPP-153 Pressurizer OME-4 Protection Channel III Pressure Transmitter Reactor Coolant Containment 612 Instrumentation Room 67 2-NPS-121 Reactor Coolant Loop #2 Hot Leg Wide Range Pressure Transmitter Reactor Coolant Containment 612 West Containment Lower Vent Room 73 2-NPS-122 Reactor Coolant Loop #1 Hot Leg Wide Range Pressure Transmitter Reactor Coolant Containment 612 East Containment Lower Vent Room 72 2-NPS-153 Pressurizer OME-4 Protection Channel IV Pressure Transmitter Reactor Coolant Containment 612 Instrumentation Room 67 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
1 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NRI-1 Nuclear Instrumentation Source Range Monitor Reactor Coolant Auxiliary 633 Control Room 123 2-NRI-21 Nuclear Instrumentation Source Range Radiation Detector Nuclear Instrumentation Containment 626 Reactor Cavity 105 2-NRI-21-AMP Nuclear Instrumentation Wide Range Radiation Amplifier Cabinet Nuclear Instrumentation Auxiliary 596 Reactor Cable
- Tunnel, Quadrant #1 25 2-NRI-21-PRCSR Nuclear Instrumentation Wide Range Signal Processor Cabinet Nuclear Instrumentation Auxiliary 633 Control Room 123 2-NRI-23 Nuclear Instrumentation Source Range Radiation Detector Nuclear Instrumentation Containment 626 Reactor Cavity 105 2-NRI-23-AMP Nuclear Instrumentation Source Range Radiation Detector NRI-23 Amplifier Cabinet Nuclear Instrumentation Auxiliary 596 Reactor Cable
- Tunnel, Quadrant #1 25 2-NRI-23-ISOL Nuclear Instrumentation Source Range Signal Isolator Cabinet Nuclear Instrumentation Auxiliary 596 Reactor Cable
- Tunnel, Quadrant #1 25 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
2 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NRI-23-PRCSR Nuclear Instrumentation Source Range Signal Processor Cabinet Nuclear Instrumentation Auxiliary 633 Control Room 123 2-NRI-5 Nuclear Instrumentation Source Range Monitor Reactor Coolant Auxiliary 633 Control Room 123 2-NRV-151 Pressurizer Train 'B' Pressure Relief Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NRV-152 Pressurizer Train 'B' Pressure Relief Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NRV-153 Pressurizer OME-4 Train 'A' Pressure Relief Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NSO-62 Pressurizer OME-4 Post Accident Vent Train 'A' Solenoid Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
3 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NSO-61 Post-Accident Vent Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NSO-63 Post-Accident Vent Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NSO-64 Pressurizer OME-4 Post Accident Vent Train 'B' Solenoid Valve Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-NTP-110A Reactor Coolant Loop #1 Hot Leg Channel I Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #1 60 2-NTP-110B Reactor Coolant Loop #1 Hot Leg Channel I Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #1 60 2-NTP-111A Reactor Coolant Loop #1 Hot Leg Channel I Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #1 60 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
4 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NTP-111B Reactor Coolant Loop #1 Hot Leg Channel I Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #1 60 2-NTP-112A Reactor Coolant Loop #1 Hot Leg Channel I Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #1 60 2-NTP-112B Reactor Coolant Loop #1 Hot Leg Channel I Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #1 60 2-NTP-120A Reactor Coolant Loop #2 Hot Leg Channel II Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #2 61 2-NTP-120B Reactor Coolant Loop #2 Hot Leg Channel II Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #2 61 2-NTP-121A Reactor Coolant Loop #2 Hot Leg Channel II Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #2 61 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
5 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NTP-121B Reactor Coolant Loop #2 Hot Leg Channel II Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #2 61 2-NTP-122A Reactor Coolant Loop #2 Hot Leg Channel II Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #2 61 2-NTP-122B Reactor Coolant Loop #2 Hot Leg Channel II Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #2 61 2-NTP-130A Reactor Coolant Loop #3 Hot Leg Channel III Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #3 62 2-NTP-130B Reactor Coolant Loop #3 Hot Leg Channel III Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #3 62 2-NTP-131A Reactor Coolant Loop #3 Hot Leg Channel III Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #3 62 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
6 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NTP-131B Reactor Coolant Loop #3 Hot Leg Channel III Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #3 62 2-NTP-132A Reactor Coolant Loop #3 Hot Leg Channel III Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #3 62 2-NTP-132B Reactor Coolant Loop #3 Hot Leg Channel III Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #3 62 2-NTP-140A Reactor Coolant Loop #4 Hot Leg Channel IV Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #4 63 2-NTP-140B Reactor Coolant Loop #4 Hot Leg Channel IV Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #4 63 2-NTP-141A Reactor Coolant Loop #4 Hot Leg Channel IV Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #4 63 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
7 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NTP-141B Reactor Coolant Loop #4 Hot Leg Channel IV Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #4 63 2-NTP-142A Reactor Coolant Loop #4 Hot Leg Channel IV Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #4 63 2-NTP-142B Reactor Coolant Loop #4 Hot Leg Channel IV Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 598 Lower Containment, Quadrant #4 63 2-NTP-210A Reactor Coolant Loop #1 Cold Leg Channel I Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 625 Lower Containment, Quadrant #1 60 2-NTP-210B Reactor Coolant Loop #1 Cold Leg Channel I Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 625 Lower Containment, Quadrant #1 60 2-NTP-220A Reactor Coolant Loop #2 Cold Leg Channel II Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 617 Lower Containment, Quadrant #2 61 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
8 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-NTP-220B Reactor Coolant Loop #2 Cold Leg Channel II Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 617 Lower Containment, Quadrant #2 61 2-NTP-230A Reactor Coolant Loop #3 Cold Leg Channel III Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 617 Lower Containment, Quadrant #3 62 2-NTP-230B Reactor Coolant Loop #3 Cold Leg Channel III Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 617 Lower Containment, Quadrant #3 62 2-NTP-240A Reactor Coolant Loop #4 Cold Leg Channel IV Reactor Protection Input Narrow Range Thermal Sensor Reactor Coolant Containment 625 Lower Containment, Quadrant #4 63 2-NTP-240B Reactor Coolant Loop #4 Cold Leg Channel IV Reactor Protection Input Spare Narrow Range Thermal Sensor Reactor Coolant Containment 625 Lower Containment, Quadrant #4 63 2-OME-150-AB AB Emergency Diesel Generator Diesel Generator, Control &
Instrumentation Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page:
9 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-OME-150-CD CD Emergency Diesel Generator Diesel Generator, Control &
Instrumentation Auxiliary 587 CD EDG Room 122 2-OME-3-1 Steam Generator No. 1 Main Steam Containment 609 Lower Containment, Quadrant #1 60 2-OME-3-2 Steam Generator No. 2 Main Steam Containment 609 Lower Containment, Quadrant #2 61 2-OME-3-3 Steam Generator No. 3 Main Steam Containment 609 Lower Containment, Quadrant #3 62 2-OME-3-4 Steam Generator No. 4 Main Steam Containment 609 Lower Containment, Quadrant #4 63 2-OME-34E East Essential Service Water Pump PP-7E Discharge Strainer Essential Service Water Screenhouse 591 East ESW Pump Room 135 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 10 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-OME-34W West Essential Service Water Pump PP-7W Discharge Strainer Essential Service Water Screenhouse 591 West ESW Pump Room 136 2-OME-39 Auxiliary Feed Pump Turbine Auxiliary Feedwater/Main Steam Turbine 591 TDAFP Room 49 2-POV-1-AB Starting Air Syst/Pilot Operated 4-Way Valve for Air Start of XRVs for Diesel Engine Compressed Air Auxiliary 587 AB EDG Room 121 2-POV-1-CD Starting Air Syst/Pilot Operated 4-Way Valve for Air Start of XRVs for Diesel Engine Compressed Air Auxiliary 587 CD EDG Room 122 2-POV-2-AB Starting Air Syst/Pilot Operated 4-Way Valve for Air Start of XRVs for Diesel Engine Compressed Air Auxiliary 587 AB EDG Room 121 2-POV-2-CD Starting Air Syst/Pilot Operated 4-Way Valve for Air Start of XRVs for Diesel Engine Compressed Air Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 11 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-PP-10E East CCW Pump Component Cooling Water Auxiliary 609 609 Hallway 609 2-PP-10W West CCW Pump Component Cooling Water Auxiliary 609 609 Hallway 609 2-PP-120-AB Engine Driven Pump Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 2-PP-120-CD Engine Driven Pump Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-PP-26N North Safety Injection Pump Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-PP-26S South Safety Injection Pump Safety Injection Auxiliary 587 South Safety Injection Pump Room 43 2-PP-35E East Residual Heat Removal Pump Residual Heat Removal Auxiliary 573 East RHR Pump Room 54 2-PP-35W West Residual Heat Removal Pump Residual Heat Removal Auxiliary 573 West RHR Pump Room 55 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 12 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-PP-3E East Motor Driven Auxiliary Feedwater Pump Auxiliary Feedwater Turbine 591 East MDAFP Room 50 2-PP-3W West Motor Driven Auxiliary Feedwater Pump Auxiliary Feedwater Turbine 591 West MDAFP Room 51 2-PP-4 Turbine Driven Auxiliary Feed Pump Auxiliary Feedwater Turbine 591 TDAFP Room 49 2-PP-50E East Centrifugal Charging Pump (CVCS)
Charging Auxiliary 587 East Centrifugal Charging Pump Room 40 2-PP-50W West Centrifugal Charging Pump (CVCS)
Charging Auxiliary 587 West Centrifugal Charging Pump Room 41 2-PP-7E East Essential Service Water Pump Essential Service Water Screenhouse 591 East ESW Pump Room 135 2-PP-7W West Essential Service Water Pump Essential Service Water Screenhouse 591 West ESW Pump Room 136 2-PP-82N Control Room Air Conditioning North Chill Water Circulation Pump Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 13 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-PP-82S Control Room Air Conditioning South Chill Water Circulation Pump Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-PPP-301 Lower Containment Channel III Pressure Protection Transmitter Containment Ventilation Auxiliary 612 612 Airlock Area 12 2-PPP-302 Lower Containment Channel II Pressure Protection Transmitter Containment Ventilation Auxiliary 612 612 Airlock Area 12 2-PPP-303 Lower Containment Channel I Pressure Protection Transmitter Containment Ventilation Auxiliary 612 612 Airlock Area 12 2-PRV-1-AB Pressure Regulator for Starting Air Solenoid 20-SV-1-AB Compressed Air Auxiliary 587 AB EDG Room 121 2-PRV-1-CD Pressure Regulator for Starting Air Solenoid 20-SV-1-CD Compressed Air Auxiliary 587 AB EDG Room 121 2-PRZ Pressurizer Control Panel Reactor Coolant Auxiliary 633 Control Room 123 2-PS-A 600Vac Motor Control Center PS-A 600Vac Screenhouse 594 Traveling Screen MCC Upper Room 221 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 14 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-PS-D 600Vac Motor Control Center PS-D 600Vac Screenhouse 594 Traveling Screen MCC Upper Room 221 2-QCM-250 Reactor Coolant Pump Seal Water Return Train 'A' Containment Isolation 4" Motor Operated Valve (CVCS)
Letdown Containment 598 Annulus -
Quadrant #2 59 2-QCM-350 Reactor Coolant Pump Seal Water Return Train 'B' Containment Isolation 4" Motor Operated Valve (CVCS)
Letdown Auxiliary 591 Vestibule 28 2-QCR-300 Reactor Coolant Letdown Train 'B' Containment Isolation Valve (CVCS)
Letdown Auxiliary 591 Vestibule 28 2-QCR-301 CVCS Letdown Isolation (CVCS)
Letdown Containment 598 Annulus -
Quadrant #2 59 2-QFA-210 RCP Seal Water Injection to Reactor Coolant Pump PP-45-1 Low Flow Alarm Transmitter Reactor Coolant Pump Seal Water INJ/Leakoff Auxiliary 587 587 Hallway 587 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 15 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QFA-220 RCP Seal Water Injection to Reactor Coolant Pump PP-45-2 Low Flow Alarm Transmitter Reactor Coolant Pump Seal Water INJ/Leakoff Auxiliary 587 587 Hallway 587 2-QFA-230 RCP Seal Water Injection to Reactor Coolant Pump PP-45-3 Low Flow Alarm Transmitter Reactor Coolant Pump Seal Water INJ/Leakoff Auxiliary 587 587 Hallway 587 2-QFA-240 RCP Seal Water Injection to Reactor Coolant Pump PP-45-4 Low Flow Alarm Transmitter Reactor Coolant Pump Seal Water INJ/Leakoff Auxiliary 587 587 Hallway 587 2-QFI-200 CVCS Charging Pumps Discharge Flow Indicator Transmitter (CVCS)
Charging Auxiliary 587 587 Hallway 587 2-QMO-200 CVCS Charging to Regenerative Heat Exchanger Train 'A' Shutoff Valve (CVCS)
Charging Auxiliary 587 Reciprocating Charging Pump Room 39 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 16 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QMO-201 CVCS Charging to Regenerative Heat Exchanger Train 'B' Shutoff Valve (CVCS)
Charging Auxiliary 587 Reciprocating Charging Pump Room 39 2-QMO-225 East Centrifugal Charging Pump Mini-Flow to RCP Seal Water Heat Exchanger HE-11 2" Motor Operated Shutoff Valve (CVCS)
Charging Auxiliary 587 East Centrifugal Charging Pump Room 40 2-QMO-226 West Centrifugal Charging Pump Mini-Flow to RCP Seal Water Heat Exchanger HE-11 2" Motor Operated Shutoff Valve (CVCS)
Charging Auxiliary 587 West Centrifugal Charging Pump Room 41 2-QMO-451 Reactor Coolant Letdown Volume Control Tank TK-10 to CVCS Charging Pumps Train 'A' Shutoff 4" Motor Operated Valve (CVCS)
Letdown Auxiliary 609 Volume Control Tank East Hallway 19 2-QMO-452 Reactor Coolant Letdown Volume Control Tank TK-10 to CVCS Charging Pumps Train 'B' Shutoff 4" Motor Operated Valve (CVCS)
Letdown Auxiliary 609 Volume Control Tank East Hallway 19 2-QRV-10 Reactor Coolant Pump #1 Seal #1 Leakoff to RCP Seal Water Return Filter QC-109 2" Air Operated Shutoff Valve Reactor Coolant Pump Seal Water INJ/Leakoff Containment 617 Lower Containment, Quadrant #1 60 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 17 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QRV-150 Reactor Coolant Pumps Startup Seal System Bypass to Seal Water Return Filter QC-109 0.75" Air Operated Shutoff Valve Reactor Coolant Pump Seal Water INJ/Leakoff Containment 598 Annulus -
Quadrant #2 59 2-QRV-20 Reactor Coolant Pump #2 Seal #1 Leakoff to RCP Seal Water Return Filter QC-109 2" Air Operated Shutoff Globe Valve Reactor Coolant Pump Seal Water INJ/Leakoff Containment 625 Lower Containment, Quadrant #2 61 2-QRV-251 CVCS Centrifugal Charging Pumps Discharge Flow 3" Air Operated Control Globe Valve (CVCS)
Charging Auxiliary 587 Reciprocating Charging Pump Room 39 2-QRV-30 Reactor Coolant Pump #3 Seal #1 Leakoff to RCP Seal Water Return Filter QC-109 2" Air Operated Shutoff Globe Valve Reactor Coolant Pump Seal Water INJ/Leakoff Containment 612 Lower Containment, Quadrant #3 62 2-QRV-40 Reactor Coolant Pump #4 Seal #1 Leakoff to RCP Seal Water Return Filter QC-109 2" Air Operated Shutoff Globe Valve Reactor Coolant Pump Seal Water INJ/Leakoff Containment 612 Lower Containment, Quadrant #4 63 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 18 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QT-100-AB AB Emergency Diesel Air Intake Filter Diesel Combustion Air Grounds 609 Inner Plant Grounds 244 2-QT-100-CD CD Emergency Diesel Air Intake Filter Diesel Combustion Air Grounds 609 Inner Plant Grounds 244 2-QT-101-AB AB Emergency Diesel Air Intake Silencer Diesel Combustion Air Auxiliary 587 AB EDG Room 121 2-QT-101-CD CD Emergency Diesel Air Intake Silencer Diesel Combustion Air Auxiliary 587 CD EDG Room 122 2-QT-104-AB AB Emergency Diesel Exhaust Silencer Diesel Combustion Air Grounds 609 Inner Plant Grounds 244 2-QT-104-CD CD Emergency Diesel Exhaust Silencer Diesel Combustion Air Grounds 609 Inner Plant Grounds 244 2-QT-106-AB1 AB Emergency Diesel Fuel Oil Transfer Pump #1 Diesel Fuel Oil Auxiliary 587 AB EDG Fuel Oil Transfer Pump Room 126 2-QT-106-AB2 AB Emergency Diesel Fuel Oil Transfer Pump #2 Diesel Fuel Oil Auxiliary 587 AB EDG Fuel Oil Transfer Pump Room 126 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 19 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QT-106-CD1 CD Emergency Diesel Fuel Oil Transfer Pump #1 Diesel Fuel Oil Auxiliary 587 CD EDG Fuel Oil Transfer Pump Room 125 2-QT-106-CD2 CD Emergency Diesel Fuel Oil Transfer Pump #2 Diesel Fuel Oil Auxiliary 587 CD EDG Fuel Oil Transfer Pump Room 125 2-QT-107-AB AB Emergency Diesel Fuel Oil Day Tank Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 2-QT-107-CD CD Emergency Diesel Fuel Oil Day Tank Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-QT-110-AB AB Emergency Diesel Lube Oil Cooler Diesel Lube Oil Auxiliary 587 AB EDG Room 121 2-QT-110-CD CD Emergency Diesel Lube Oil Cooler Diesel Lube Oil Auxiliary 587 CD EDG Room 122 2-QT-111-AB AB Emergency Diesel Lube Oil Before and After Pump Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-111-CD CD Emergency Diesel Lube Oil Before and After Pump Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 20 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QT-112-AB AB Emergency Diesel Full Flow Lube Oil Filter Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-112-CD CD Emergency Diesel Full Flow Lube Oil Filter Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 2-QT-113-AB1 AB Emergency Diesel Full Flow Lube Oil Strainer #1 Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-113-AB2 AB Emergency Diesel Full Flow Lube Oil Strainer #2 Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-113-CD1 CD Emergency Diesel Full Flow Lube Oil Strainer #1 Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 2-QT-113-CD2 CD Emergency Diesel Full Flow Lube Oil Strainer #2 Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 2-QT-114-AB AB Emergency Diesel Lube Oil Cooler QT-110-AB Lube Oil Thermostatic Inlet/Bypass Valve Diesel Lube Oil Auxiliary 587 AB EDG Room 121 2-QT-114-CD CD Emergency Diesel Lube Oil Cooler QT-110-CD Lube Oil Thermostatic Inlet/Bypass Valve Diesel Lube Oil Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 21 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QT-115-AB AB Emergency Diesel Lube Oil Sump Tank Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-115-CD CD Emergency Diesel Lube Oil Sump Tank Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 2-QT-116-AB AB Emergency Diesel Lube Oil Heater Tank Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-116-CD CD Emergency Diesel Lube Oil Heater Tank Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 2-QT-117-AB AB Emergency Diesel Lube Oil Heater QT-116-AB Pump Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-117-CD CD Emergency Diesel Lube Oil Heater QT-116-CD Pump Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 2-QT-118-AB AB Emergency Diesel Bypass Lube Oil Filter Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-118-CD CD Emergency Diesel Bypass Lube Oil Filter Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 22 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QT-119-AB AB Emergency Diesel Bypass Lube Oil Filter QT-118-AB Pump Diesel Lube Oil Auxiliary 579 AB EDG Lube Oil Pit 257 2-QT-119-CD CD Emergency Diesel Bypass Lube Oil Filter QT-118-CD Pump Diesel Lube Oil Auxiliary 579 CD EDG Lube Oil Pit 258 2-QT-130-AB1 AB Emergency Diesel Jacket Water Pump #1 Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-QT-130-AB2 AB Emergency Diesel Jacket Water Pump #2 Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-QT-130-CD1 CD Emergency Diesel Jacket Water Pump #1 Diesel Jacket Water Auxiliary 587 CD EDG Room 122 2-QT-130-CD2 CD Emergency Diesel Jacket Water Pump #2 Diesel Jacket Water Auxiliary 587 CD EDG Room 122 2-QT-131-AB AB Emergency Diesel Jacket Water Cooler Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-QT-131-CD CD Emergency Diesel Jacket Water Cooler Diesel Jacket Water Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 23 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QT-132-AB AB Emergency Diesel Jacket Water Cooler QT-131-AB Jacket Water Thermostatic Inlet/Bypass Valve Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-QT-132-CD CD Emergency Diesel Jacket Water Cooler QT-131-CD Jacket Water Thermostatic Inlet/Bypass Diesel Jacket Water Auxiliary 587 CD EDG Room 122 2-QT-133-AB AB Emergency Diesel Jacket Water Surge Tank Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-QT-133-CD CD Emergency Diesel Jacket Water Surge Tank Diesel Jacket Water Auxiliary 587 CD EDG Room 122 2-QT-134-AB AB Emergency Diesel Auxiliary Jacket Water Heater Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-QT-134-CD CD Emergency Diesel Auxiliary Jacket Water Heater (Tank)
Diesel Jacket Water Auxiliary 587 CD EDG Room 122 2-QT-135-AB AB Emergency Diesel Auxiliary Jacket Water Pump Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-QT-135-CD CD Emergency Diesel Auxiliary Jacket Water Pump Diesel Jacket Water Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 24 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QT-141-AB1 AB Emergency Diesel Starting Air Receiver #1 Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-QT-141-AB2 AB Emergency Diesel Starting Air Receiver #2 Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-QT-141-CD1 CD Emergency Diesel Starting Air Receiver #1 Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-QT-141-CD2 CD Emergency Diesel Starting Air Receiver #2 Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-QT-143-AB1 AB Emergency Diesel Control Air Dryer #1 Diesel Control Air Auxiliary 587 AB EDG Room 121 2-QT-143-AB2 AB Emergency Diesel Control Air Dryer #2 Diesel Control Air Auxiliary 587 AB EDG Room 121 2-QT-143-CD1 CD Emergency Diesel Control Air Dryer #1 Diesel Control Air Auxiliary 587 CD EDG Room 122 2-QT-143-CD2 CD Emergency Diesel Control Air Dryer #2 Diesel Control Air Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 25 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-QT-144-AB AB Emergency Diesel Fuel Oil Transfer Filter Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 2-QT-144-CD CD Emergency Diesel Fuel Oil Transfer Filter Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-QT-502-AB AB Emergency Diesel Turbocharger Diesel Combustion Air Auxiliary 587 AB EDG Room 121 2-QT-502-CD CD Emergency Diesel Turbocharger Diesel Combustion Air Auxiliary 587 CD EDG Room 122 2-QT-506 Turbine Driven Aux Feed Pump PP-4 Trip and Throttle Valve Auxiliary Feedwater/Main Steam Turbine 591 TDAFP Room 49 2-QT-507 TDAFP Governor Valve Main Steam Turbine 591 TDAFP Room 49 2-RC Reactor Control Rods Control Panel Rod Control and Instrumentation Auxiliary 633 Control Room 123 2-RH-117 RHR Bypass Isolation Manual Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 26 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-RHR Residual Heat Removal Control Panel Residual Heat Removal Auxiliary 633 Control Room 123 2-RPC-I Reactor Protection Channel I Cabinet #1, 2, 3 & 4 Reactor Protection Auxiliary 633 Control Room 123 2-RPC-II Reactor Protection Channel II Cabinet #5, 6 & 7 Reactor Protection Auxiliary 633 Control Room 123 2-RPC-III Reactor Protection Channel III Cabinet #9, 10 & 11 Reactor Protection Auxiliary 633 Control Room 123 2-RPC-IV Reactor Protection Channel IV Cabinet #12 Reactor Protection Auxiliary 633 Control Room 123 2-RPS-A Reactor Protection and Safeguard Actuation Train 'A' Cabinet Reactor Protection Auxiliary 633 Control Room 123 2-RPS-B Reactor Protection and Safeguard Actuation Train 'B' Cabinet Reactor Protection Auxiliary 633 Control Room 123 2-RPSX-A Reactor Protection and Safeguard Actuation Train "A" Auxiliary Cabinet Reactor Protection Auxiliary 633 Control Room 123 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 27 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-RPSX-B Reactor Protection and Safeguard Actuation Train "B" Auxiliary Cabinet Reactor Protection Auxiliary 633 Control Room 123 2-SA Station Auxiliaries Control Panel 4160Vac Auxiliary 633 Control Room 123 2-SG Steam Generator and Auxiliary Feed Pump Control Panel Auxiliary Feedwater Auxiliary 633 Control Room 123 2-SI-152N RHR to SI Pumps Check Valve Residual Heat Removal Containment 612 East Containment Lower Vent Room 72 2-SI-152S RHR to SI Pumps Check Valve Residual Heat Removal Containment 612 West Containment Lower Vent Room 73 2-SI-210 Boron Injection to Charging Pump Crosstie Check Valve Boron Injection Auxiliary 612 BIT Room 16 2-SSV-A1 250Vdc Train 'A' Nuclear Sampling Feeder Panel #1 250Vdc Auxiliary 587 Nuclear Sampling Room 36 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 28 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SSV-A2 250Vdc Train 'A' Nuclear Sampling Feeder Panel #2 250Vdc Auxiliary 587 Nuclear Sampling Room 36 2-SSV-B 250Vdc Train 'B' Nuclear Sampling Feeder Panel 250Vdc Auxiliary 587 Nuclear Sampling Room 36 2-SV-102 Residual Heat Removal to Reactor Coolant Loops #2 & #3 Cold Legs Safety Valve Residual Heat Removal Containment 598 Annulus -
Quadrant #2 59 2-SV-103 Reactor Coolant Loop #2 Hot Leg to Residual Heat Removal Pumps Safety Valve Residual Heat Removal Containment 598 Annulus -
Quadrant #2 59 2-SV-104E East Residual Heat Removal Heat Exchanger HE-17E Outlet Safety Valve Residual Heat Removal Auxiliary 609 East RHR Heat Exchanger Room 5
2-SV-104W West Residual Heat Removal Heat Exchanger HE-17W Outlet Safety Valve Residual Heat Removal Auxiliary 609 West RHR Heat Exchanger Room 6
2-SV-120-AB 2-XTC-301 & 2-XTC-302 Control Air Safety Valve Control Air Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 26.0 Table: 14.4.2-1 Part 4 of 5 Page: 29 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-120-CD 2-XTC-306 and 2-XTC-307 Control Air Safety Valve Control Air Auxiliary 587 CD EDG Room 122 2-SV-139-AB AB Emergency Diesel Starting Air to Turbocharger Safety Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-SV-139-CD CD Emergency Diesel Starting Air to Turbocharger Safety Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-SV-140-1 Turbine Driven Aux Feed Pump Governor Oil Cooler Cooling Water Inlet Safety Valve Auxiliary Feedwater Turbine 591 TDAFP Room 49 2-SV-140-2 Turbine Driven Aux Feed Pump Oil Cooler Cooling Water Inlet Safety Valve Auxiliary Feedwater Turbine 591 TDAFP Room 49 2-SV-169E East Motor Driven Auxiliary Feedwater Pump PP-3E Suction Safety Valve Auxiliary Feedwater Turbine 591 East MDAFP Room 50 2-SV-169W West Motor Driven Auxiliary Feed Pump PP-3W Suction Safety Valve Auxiliary Feedwater Turbine 591 West MDAFP Room 51 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
1 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-1A-1 Steam Generator OME-3-1 Safety Valve 1A Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-1A-2 Steam Generator OME-3-2 Safety Valve 1A Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-SV-1A-3 Steam Generator OME-3-3 Safety Valve 1A Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-SV-1A-4 Steam Generator OME-3-4 Safety Valve 1A Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-1B-1 Steam Generator OME-3-1 Safety Valve 1B Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-1B-2 Steam Generator OME-3-2 Safety Valve 1B Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
2 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-1B-3 Steam Generator OME-3-3 Safety Valve 1B Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-SV-1B-4 Steam Generator OME-3-4 Safety Valve 1B Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-200-AB AB Emergency Diesel Fuel Oil Manifolds to Fuel Oil Day Tank Safety Valve Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 2-SV-200-CD CD Emergency Diesel Fuel Oil Manifolds to Fuel Oil Day Tank Safety Valve Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-SV-201-AB1 AB Emergency Diesel Front Bank Fuel Oil Manifold Safety Valve Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-SV-201-AB2 AB Emergency Diesel Rear Bank Fuel Oil Manifold Safety Valve Diesel Fuel Oil Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
3 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-201-CD1 CD Emergency Diesel Front Bank Fuel Oil Manifold Safety Valve Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-SV-201-CD2 CD Emergency Diesel Rear Bank Fuel Oil Manifold Safety Valve Diesel Fuel Oil Auxiliary 587 CD EDG Room 122 2-SV-2A-1 Steam Generator OME-3-1 Safety Valve 2A Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-2A-2 Steam Generator OME-3-2 Safety Valve 2A Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-SV-2A-3 Steam Generator OME-3-3 Safety Valve 2A Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-SV-2A-4 Steam Generator OME-3-4 Safety Valve 2A Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-2B-1 Steam Generator OME-3-1 Safety Valve 2B Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
4 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-2B-2 Steam Generator OME-3-2 Safety Valve 2B Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-SV-2B-3 Steam Generator OME-3-3 Safety Valve 2B Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-SV-2B-4 Steam Generator OME-3-4 Safety Valve 2B Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-3-1 Steam Generator OME-3-1 Safety Valve #3 Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-3-2 Steam Generator OME-3-2 Safety Valve #3 Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
2-SV-3-3 Steam Generator OME-3-3 Safety Valve #3 Main Steam Auxiliary 633 West Main Steam Stop Enclosure 9
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
5 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-3-4 Steam Generator OME-3-4 Safety Valve #3 Main Steam Auxiliary 633 East Main Steam Stop Enclosure 10 2-SV-45A Pressurizer OME-4 Safety Valve 'A' Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-SV-45B Pressurizer OME-4 Safety Valve 'B' Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-SV-45C Pressurizer OME-4 Safety Valve 'C' Reactor Coolant Containment 650 Pressurizer Enclosure, Interior 81 2-SV-50 RC Pumps Seal #1 and Startup Seal System Bypass to Seal Water Return Filters Safety Valve Reactor Coolant Pump Seal Water INJ/Leakoff Containment 598 Annulus -
Quadrant #3 56 2-SV-54 Reactor Coolant Pump Seal Water Heat Exchanger HE-11 Safety Valve (CVCS)
Letdown Auxiliary 609 Seal Water Heat Exchanger Room 18 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
6 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-56 CVCS Charging Pumps Suction Header Safety Valve (CVCS)
Charging Auxiliary 587 Reciprocating Charging Pump Room 39 2-SV-61-AB AB Emergency Diesel Auxiliary Jacket Water Heater QT-134-AB Safety Valve Diesel Jacket Water Auxiliary 587 AB EDG Room 121 2-SV-61-CD CD Emergency Diesel Auxiliary Jacket Water Heater QT-134-CD Safety Valve Diesel Jacket Water Auxiliary 587 CD EDG Room 122 2-SV-78-AB1 AB Emergency Diesel Starting Air Receiver QT-141-AB1 Safety Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-SV-78-AB2 AB Emergency Diesel Starting Air Receiver QT-141-AB2 Safety Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-SV-78-CD1 CD Emergency Diesel Starting Air Receiver QT-141-CD1 Safety Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
7 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-78-CD2 CD Emergency Diesel Starting Air Receiver QT-141-CD2 Safety Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-SV-79-AB1 AB Emergency Diesel Control Air Dryer QT-143-AB1 Safety Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-SV-79-AB2 AB Emergency Diesel Control Air Dryer QT-143-AB2 Safety Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-SV-79-CD1 CD Emergency Diesel Control Air Dryer QT-143-CD1 Safety Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-SV-79-CD2 CD Emergency Diesel Control Air Dryer QT-143-CD2 Safety Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-SV-96 Safety Injection Pumps Suction Header Safety Valve Safety Injection Auxiliary 587 South Safety Injection Pump Room 43 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
8 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-SV-97 Boron Injection Tank TK-11 Outlet Safety Valve Boron Injection Auxiliary 612 BIT Room 16 2-SV-98N North Safety Injection Pump PP-26N Discharge Header Safety Valve Safety Injection Auxiliary 587 North Safety Injection Pump Room 42 2-SV-98S South Safety Injection Pump PP-26S Discharge Header Safety Valve Safety Injection Auxiliary 587 South Safety Injection Pump Room 43 2-T21A 4kv Bus T21A Switchgear 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21A10 Transformer TR21A to 600Vac Bus 21A Supply Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21A11 AB Emergency Diesel Generator to 4kv Bus T21A Supply Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page:
9 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-T21A12 Circuit Breaker From 69kv to Bus T21A 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21A2 West Motor Driven Aux Feedwater Pump PP-3W Supply Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21A4 West Residual Heat Removal Pump PP-35W Supply Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21A5 West Essential Service Water Pump PP-7W Supply Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21A7 West Component Cooling Water Pump PP-10W Supply Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21A8 West Centrifugal Charging Pump PP-50W Supply Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 10 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-T21A9 4kv Bus 2A to Bus T21A Tie Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21B 4kv Bus T21B Switchgear 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21B1 4kv Bus 2B to 4kv Bus T21B Tie Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21B2 Circuit Breaker From 69kv Bus to Bus T21B 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21B4 AB Emergency Diesel Generator to 4kv Bus T21B Supply Breaker 4160Vac Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-T21C 4kv Bus T21C Switchgear 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 11 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-T21C1 4kv Bus 2c to 4kv Bus T21C Tie Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21C2 Circuit Breaker - 4kv From 69kv to Bus T21C 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21C3 CD Emergency Diesel Generator to 4kv Bus T21C Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21D 4kv Bus T21D Switchgear 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21D1 4kv Emergency Power Bus EP to 4kv Bus T21D Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21D10 East Essential Service Water Pump PP-7E Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 12 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-T21D11 East Motor Driven Auxiliary Feedwater Pump PP-3E Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21D12 4kv Bus 2d to 4kv Bus T21D Tie Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21D2 Transformer TR21D to 600Vac Bus 21D Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21D3 East Component Cooling Water Pump PP-10E Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21D6 East RHR Pump PP-35E Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-T21D7 East Centrifugal Charging Pump PP-50e Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 13 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-T21D8 CD Emergency Diesel Generator to 4kv Bus T21D Supply Breaker 4160Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-TDAB 250 Vdc Train 'B' Transfer Cabinet 250Vdc Auxiliary 609 AB BATT Equip Area 200 2-TDCD 250 Vdc Train 'A' Transfer Cabinet 250Vdc Auxiliary 626 CD BATT Equip Area 201 2-TK-11 Boron Injection Tank Boron Injection Auxiliary 612 BIT Room 16 2-TK-253-1 Pressurizer Train 'B' Pressure Relief Valve NRV-152 Reserve Control Air Tank Control Air Containment 625 Lower Containment, Quadrant #3 62 2-TK-253-2 Pressurizer Train 'A' Pressure Relief Valve NRV-153 Reserve Control Air Tank Control Air Containment 625 Lower Containment, Quadrant #3 62 2-TK-253-3 Pressurizer Train 'B' Pressure Relief Valve NRV-152 Emergency Air Tank Control Air Containment 650 Upper Containment, Quadrant #4 86 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 14 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-TK-253-4 Pressurizer Train 'A' Pressure Relief Valve NRV-153 Emergency Air Tank Control Air Containment 650 Upper Containment, Quadrant #4 86 2-TK-32 Condensate Storage Tank Condensate Storage Tank Supply Grounds 609 Condensate Storage Tank Area 20 2-TK-33 Refueling Water Storage Tank RWST Supply Grounds 609 RWST Area 21 2-TK-37 Component Cooling Water Surge Tank Component Cooling Water Auxiliary 650 650 Hallway 650 2-TK-76N Control Room Air Conditioning North Chill Water Expansion Tank Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-TK-76S Control Room Air Conditioning South Chill Water Expansion Tank Control Room Ventilation Auxiliary 650 Control Rm A/C Room 129 2-TR21A 600v Bus 21A Supply Transformer 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 15 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-TR21B 600v Bus 21B Supply Transformer 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-TR21C 600v Bus 21C Supply Transformer 600Vac Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-TR21D 600v Bus 21D Supply Transformer 600Vac Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-TR-AFW Auxiliary Feedwater 120/208Vac Distribution Panel AFW Supply Transformer 120/208Vac Misc Safety Related Power Distribution Auxiliary 587 CD EDG Room 122 2-TR-ELSC 120/208Vac Emergency Local Shutdown Distribution Transformer 120/208Vac Misc Safety Related Power Distribution Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 16 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-VDAB-1 250Vdc Valve Distribution Panel VDAB-1 250Vdc Auxiliary 633 Control Room 123 2-VDAB-2 250Vdc Valve Distribution Panel VDAB-2 250Vdc Auxiliary 633 Control Room 123 2-VDCD-1 250Vdc Valve Distribution Panel VDCD-1 250Vdc Auxiliary 633 Control Room 123 2-VDCD-2 250Vdc Valve Distribution Panel VDCD-2 250Vdc Auxiliary 633 Control Room 123 2-VRV-315 Control Room Ventilation Unit HV-ACRA-1 Chill Water Inlet/Bypass Valve Control Room Ventilation Auxiliary 650 Control Room A/C Room 129 2-VRV-325 Control Room Ventilation Unit HV-ACRA-2 Chill Water Inlet/Bypass Valve Control Room Ventilation Auxiliary 650 Control Room A/C Room 129 2-VTS-201 East Motor Driven Auxiliary Feedwater Pump Room Cooler 2-HV-AFP-EAC Temperature Switch Turbine Building Ventilation Turbine 591 East MDAFP Room 50 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 17 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-VTS-203 Turbine Driven Auxiliary Feed Pump Room Cooler 2-HV-AFP-T1AC Temperature Switch Turbine Building Ventilation Turbine 591 TDAFP Room 49 2-VTS-204 Turbine Driven Auxiliary Feed Pump Room Cooler 2-HV-AFP-T2AC Temperature Switch Turbine Building Ventilation Turbine 591 TDAFP Room 49 2-VTS-206 West Motor Driven Auxiliary Feedwater Pump Room Cooler 2-HV-AFP-WAC Temperature Switch Turbine Building Ventilation Turbine 591 West MDAFP Room 51 2-VTS-340 AB Emergency Diesel Generator Room Ventilation Supply Fan HV-DGS-2 Outside Air Thermostat Emergency Diesel Generator Room Ventilation Grounds 609 RWST Area 21 2-VTS-341 AB Emergency Diesel Generator Room Ventilation Fans HV-DGX-2 Thermostat Emergency Diesel Generator Room Ventilation Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 18 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-VTS-345 CD Emergency Diesel Generator Room Ventilation Supply Fan HV-DGS-1 Outside Air Thermostat Emergency Diesel Generator Room Ventilation Auxiliary 596 Reactor Cable
- Tunnel, Quadrant #3 26 2-VTS-346 CD Emergency Diesel Generator Room Ventilation Exhaust Fan HV-DGX-1 Thermostat Emergency Diesel Generator Room Ventilation Auxiliary 587 CD EDG Room 122 2-VTS-350 Control Rod Drive Equip Room and Inv Area Vent North Supply Fan HV-SGRS-1a Temperature Switch ELEC. SWGR.
Ventilation Auxiliary 609 Inverter Area 202 2-VTS-351 Control Rod Drive Equip Room and Inv Area Vent North Supply Fan HV-SGRS-1a Temperature Switch ELEC. SWGR.
Ventilation Auxiliary 609 Control Rod Drive Equipment Room 203 2-VTS-352 4kv Room 600 Volt Switchgear Xfrms TR21B and TR21D Area Vent Supply Fan HV-SGRS-7 Temperature Switch ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 19 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-VTS-353 600Vac Motor Control Center Mezzanine Area Vent Supply Fan HV-SGRS-9 Temperature Switch ELEC. SWGR.
Ventilation Auxiliary 613 4kv Room -
Mezzanine Area 205 2-VTS-354 Ctrl Rod Drv Equip Room and Inv Area Vent Outside Air Inlet Damper HV-Sgr-MD-2 Temperature Switch ELEC. SWGR.
Ventilation Auxiliary 609 Inverter Area 202 2-VTS-355 Ctrl Rod Drive Equip Room and Inv Area Vent Recirc Air Inlet Damper HV-Sgr-MD-1 Temperature Switch ELEC. SWGR.
Ventilation Auxiliary 609 Inverter Area 202 2-VTS-356 Crd Equipment Room and Inverter Area Ventilation North Supply Fan HV-SGRS-4A Temp Switch ELEC. SWGR.
Ventilation Auxiliary 609 Inverter Area 202 2-VTS-357 Ctrl Rod Drive Equip Room and Inv Area Ventilation South Supply Fan HV-SGRS-4A Temperature Switch ELEC. SWGR.
Ventilation Auxiliary 609 Control Rod Drive Equipment Room 203 2-VTS-702 Unit 2 East ESW Pump Room Temperature Switch ESW Ventilation Screenhouse 591 East ESW Pump Room 135 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 20 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-VTS-704 Unit 2 West ESW Pump Room Temperature Switch ESW Ventilation Screenhouse 591 West ESW Pump Room 136 2-VTS-802 4kv Room AB 4kv Switchgear Area Ventilation Supply Fan HV-SGRS-2 Thermal Sensor ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room - AB 4kv Switchgear Area 140 2-VTS-803 4kv Room CD 4kv Switchgear Area Ventilation Supply Fan HV-SGRS-3 Thermal Sensor ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room - CD 4kv Switchgear Area 206 2-VTS-805 4kv Room 600v SWGR Xfmrs TR21B and TR21D Area Vent Supply Fan HV-SGRS-7 Temp Switch Thermal Sensor ELEC. SWGR.
Ventilation Auxiliary 613 4kv Room -
Mezzanine Area 205 2-VTS-808 4kv Room 600v SWGR Xfmrs TR21A and TR21C Area Vent Supply Fan HV-SGRS-8 Temp Switch Temp Switch ELEC. SWGR.
Ventilation Auxiliary 609 4kv Room -
600v Switchgear Area 204 2-WFA-702 East Essential Service Water Supply Header Flow Transmitter Essential Service Water Turbine 569 ESW Pipe Tunnel 131 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 21 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-WFA-706 West Essential Service Water Supply Header Flow Transmitter Essential Service Water Turbine 569 ESW Pipe Tunnel 131 2-WMO-703 East Essential Service Water Pump PP-7E Discharge Shutoff Valve Essential Service Water Screenhouse 591 East ESW Pump Room 135 2-WMO-704 West Essential Service Water Pump PP-7W Discharge Shutoff Valve Essential Service Water Screenhouse 591 West ESW Pump Room 136 2-WMO-706 West Essential Service Water Supply Header Crosstie to Unit 1 Shutoff Valve Essential Service Water Turbine 569 ESW Pipe Tunnel 131 2-WMO-708 East Essential Service Water Supply Header Crosstie to Unit 1 Shutoff Valve Essential Service Water Turbine 569 ESW Pipe Tunnel 131 2-WMO-712 East CS Hx HE-18E ESW Inlet Shutoff Valve Essential Service Water Auxiliary 633 633 Hallway 633 2-WMO-716 West CS Hx ESW Inlet Shutoff Valve Essential Service Water Auxiliary 633 633 Hallway 633 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 22 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-WMO-722-AB West Essential Service Water Supply Header to AB Emergency Diesel Heat Exchangers Shutoff Valve Essential Service Water Auxiliary 587 CD EDG Room North Pipe Tunnel 171 2-WMO-724-AB East Essential Service Water Supply Header to AB Emergency Diesel Heat Exchangers Shutoff Valve Essential Service Water Auxiliary 587 CD EDG Room North Pipe Tunnel 171 2-WMO-726-CD East Essential Service Water Supply Header to CD Emergency Diesel Heat Exchangers Shutoff Valve Essential Service Water Auxiliary 587 CD EDG Room North Pipe Tunnel 171 2-WMO-728-CD West Essential Service Water Supply Header to CD Emergency Diesel Heat Exchangers Shutoff Valve Essential Service Water Auxiliary 587 CD EDG Room North Pipe Tunnel 171 2-WMO-732 East Component Cooling Water Heat Exchanger HE-15E Essential Service Water Inlet Shutoff Valve Essential Service Water Auxiliary 609 609 Hallway 609 2-WMO-734 East Component Cooling Water Heat Exchanger HE-15E Essential Service Water Outlet Shutoff Valve Essential Service Water Auxiliary 609 609 Hallway 609 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 23 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-WMO-736 West Component Cooling Water Heat Exchanger Essential Service Water Inlet Shutoff Valve Essential Service Water Auxiliary 609 609 Hallway 609 2-WMO-738 West Component Cooling Water Heat Exchanger Essential Service Water Outlet Shutoff Valve Essential Service Water Auxiliary 609 609 Hallway 609 2-WPI-706 West Essential Service Water Supply Header Pressure Indicator Transmitter Essential Service Water Turbine 569 ESW Pipe Tunnel 131 2-WPI-708 East Essential Service Water Supply Header Pressure Indicator Transmitter Essential Service Water Turbine 569 ESW Pipe Tunnel 131 2-WPS-702 East Essential Service Water Supply Header Pressure Switch Essential Service Water Turbine 569 ESW Pipe Tunnel 131 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 24 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-WPS-706 West Essential Service Water Supply Header Pressure Switch Essential Service Water Turbine 569 ESW Pipe Tunnel 131 2-WRV-711-1N ESW from CRAC N Lqd Chiller 2-HV-ACR-1 Cndsr Wtr Reg Vlv (Ckt 1)
Essential Service Water Auxiliary 650 Control Rm A/C Room 129 2-WRV-711-2N ESW from CRAC N Lqd Chiller 2-HV-ACR-1 Cndsr Wtr Reg Vlv (Ckt 2)
Essential Service Water Auxiliary 650 Control Rm A/C Room 129 2-WRV-712-1S ESW from CRAC S Lqd Chiller 2-HV-ACR-2 Cndsr Wtr Reg Vlv (Ckt 1)
Essential Service Water Auxiliary 650 Control Rm A/C Room 129 2-WRV-712-2S ESW from CRAC S Lqd Chiller 2-HV-ACR-2 Cndsr Wtr Reg Vlv (Ckt 2)
Essential Service Water Auxiliary 650 Control Rm A/C Room 129 2-WRV-722-CD CD Emergency Diesel North Combustion Air Aftercooler HE CDn ESW Inlet/Bypass Valve Essential Service Water Auxiliary 587 CD EDG Room 122 2-WRV-724-CD CD Emergency Diesel South Combustion Air Aftercooler HE CDS ESW Inlet/Bypass Valve Essential Service Water Auxiliary 587 CD EDG Room 122 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 25 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-WRV-726-AB AB Emergency Diesel North Combustion Air Aftercooler HE ABN ESW Inlet/Bypass Valve Essential Service Water Auxiliary 587 AB EDG Room 121 2-WRV-728-AB AB Emergency Diesel South Combustion Air Aftercooler HE ABS ESW Inlet/Bypass Valve Essential Service Water Auxiliary 587 AB EDG Room 121 2-XPS-300 Diesel Combustion Air/AB Front Bank Air Chest Extreme High Pressure Switch Diesel Combustion Air Auxiliary 587 AB EDG Room 121 2-XPS-305 Diesel Combustion Air/CD Front Bank Air Chest Extreme High Pressure Switch Diesel Combustion Air Auxiliary 587 CD EDG Room 122 2-XRV-152 Backup Air to 2-NRV-152 Pressure Regulator Valve Control Air Containment 650 Upper Containment, Quadrant #4 86 2-XRV-153 Backup Air to 2-NRV-153 Pressure Regulator Valve Control Air Containment 650 Upper Containment, Quadrant #4 86 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 26 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-XRV-154 Backup Air to 2-NRV-152 Low Pressure Trip Valve Control Air Containment 650 Upper Containment, Quadrant #4 86 2-XRV-155 Backup Air to 2-NRV-152 Positive Air Shutoff Valve Control Air Containment 650 Upper Containment, Quadrant #4 86 2-XRV-156 Backup Air to 2-NRV-153 Low Pressure Trip Valve Control Air Containment 650 Upper Containment, Quadrant #4 86 2-XRV-157 Backup Air to 2-NRV-153 Positive Air Shutoff Valve Control Air Containment 650 Upper Containment, Quadrant #4 86 2-XRV-220 AB Emergency Diesel Starting Air Jet Assist Control Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-XRV-221 AB Emergency Diesel Front Bank Starting Air Shutoff Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 27 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-XRV-222 AB Emergency Diesel Rear Bank Starting Air Shutoff Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-XRV-223 AB Emergency Diesel Starting Air to Turbocharger Pressure Reducing Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-XRV-225 CD Emergency Diesel Starting Air Jet Assist Control Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-XRV-226 CD Emergency Diesel Front Bank Starting Air Shutoff Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-XRV-227 CD Emergency Diesel Rear Bank Starting Air Shutoff Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-XRV-228 CD Emergency Diesel Starting Air to Turbocharger Pressure Reducing Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-XRV-231 AB Emergency Diesel Starting Air to Control Air Dryer #1 Pressure Reducing Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 28 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-XRV-232 AB Emergency Diesel Starting Air to Control Air Dryer #2 Pressure Reducing Valve Diesel Starting Air Auxiliary 587 AB EDG Room 121 2-XRV-236 CD Emergency Diesel Starting Air to Control Air Dryer #1 Pressure Reducing Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-XRV-237 CD Emergency Diesel Starting Air to Control Air Dryer #2 Pressure Reducing Valve Diesel Starting Air Auxiliary 587 CD EDG Room 122 2-XRV-240 2-XTC-301 and 2-XTC-302 Control Air Pressure Reducing Valve (AB)
Diesel Control Air Auxiliary 587 AB EDG Room 121 2-XRV-245 2-XTC-306 and 2-XTC-307 Control Air Pressure Reducing Valve (CD)
Diesel Control Air Auxiliary 587 CD EDG Room 122 2-XRV-RACK-152 Pressurizer Train 'B' Pressure Relief Valve NRV-152 Valve Rack Emergency Air Pressure Regulator Control Air Containment 652 Upper Containment, Quadrant #4 82 UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised: 27.0 Table: 14.4.2-1 Part 5 of 5 Page: 29 of 29 Unit 2 Equipment Required to Shutdown Reactor (Unit 2)
(For High Energy Pipe Ruptures Outside the Containment)
Equip Id Equipment Description System Building Elev Room Rm#
2-XRV-RACK-153 Pressurizer Train 'A' Pressure Relief Valve NRV-153 Valve Rack Emergency Air Pressure Regulator Control Air Containment 652 Upper Containment, Quadrant #4 82 2-XSO-255 East Motor Driven Auxiliary Feed Pump Test Valve AFW Turbine 591 East Motor Driven Auxiliary Feed Pump Room 50 2-XSO-345 West Motor Driven Auxiliary Feed Pump Test Valve AFW Turbine 591 West Motor Driven Auxiliary Feed Pump Room 51 2-XSO-505 Pressurizer Train 'B' Pressure Relief Valve NRV-152 Control Solenoid Control Air Containment 652 Pressurizer Enclosure, Interior 81 2-XSO-507 Pressurizer Train 'A' Pressure Relief Valve NRV-153 Control Solenoid Control Air Containment 652 Pressurizer Enclosure, Interior 81 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYYAANNAALLYYSSIISS RREEPPOORRTT Revision: 16.4 Table: 14.4.2-2 Page:
1 of 1 UNIT 2 OTHER HIGH ENERGY SYSTEMS/LINES System Sampling System Steam Generator Sample Lines Steam Generator Blowdown Sample Lines Pressurizer Sample Lines Reactor Coolant System Sample Lines System From To Bleed Steam Turbine Heater 6 Turbine Heater 6A Turbine Heater 6B Blowdown Control Valves Seat Drains Condensate Heater Bypass Feed Pump Heater 2A Heater 3A Heater 2B Heater 3B Heater 3A Heater 4A Heater 3B Heater 4B Heater 4A Feed Pump Heater 4B Feed Pump Heater 4A & 4B Feed Pump Heater 4A & 4B Feed Pump E Reheater Coil Drain Moisture Separator Reheater Drain Tank Reheater Coil Drain Reheater Drain Tank Heater 6A UFSAR Revision 31.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised:
27.0 Table:14.4.2-3A Page:
1 of 1 Unit 2 Peak Environmental Qualification Conditions for LOCA, MSLB, and Feedwater Line Break Inside Containment LOCA Location Temperature (ºF)
Pressure (psig)
Upper Compartment 1601 11.62 Lower Compartment 2353 11.62 Instrument and F/A Room 2354,3 13.95 MSLB and Feedwater Line Break Location Temperature (ºF)
Pressure (psig)
Upper Compartment 135 (U1)6, 128 (U2)6 20.85 Lower Compartment 3257 20.85 1 UFSAR Figure 14.3.4-7 2 UFSAR Figure 14.3.4-6A 3 UFSAR Figure 14.3.4-8 4 Deleted 5 UFSAR Table 14.3.4-40 reports this value calculated for the Steamline Break in the Steam Generator Doghouse.
The Steam Generator Doghouse peak pressure is a bounding value for Upper and Lower Containment.
6 UFSAR Figure 14.3.4-11 (Unit 1) and Figure 14.3.4-11A (Unit 2) 7 UFSAR Figure 14.3.4-12 (Unit 1) and Figure 14.3.4-12B (Unit 2)
UFSAR Revision 31.0
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
22 Table: 14.4.2-3B Page:
1 of 1 AIRBORNE SOURCE TERM DOSES AND DOSE RATES Containment Centerline Dose Rates and Doses1 Time Gamma Dose Rate [rad/hr[
Beta Dose Rate
[rad/hr[
Total Dose Rate
[rad/hr]
Gamma Dose
[rad]
Beta Dose
[rad]
Total Dose
[rad]
1 second 4.293E+06 2.028E+07 2.46E+07 5.962E+02 2.817E+03 3.41E+03 30 minutes 1.905E+06 7.674E+06 9.58E+06 1.330E+06 5.196E+06 6.53E+06 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1.418E+06 6.592E+06 8.01E+06 2.145E+06 8.756E+06 1.09E+07 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 9.818E+05 4.849E+06 5.83E+06 3.319E+06 1.443E+07 1.77E+07 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.013E+05 1.508E+06 1.91E+06 6.889E+06 3.046E+07 3.73E+07 1 day 2.181E+05 5.753E+05 7.93E+05 1.131E+07 4.382E+07 5.51E+07 7 days 8.274E+04 2.350E+05 3.18E+05 3.014E+07 9.492E+07 1.25E+08 30 days 4.543E+03 1.708E+04 2.16E+04 4.480E+07 1.385E+08 1.83E+08 90 days 3.484E+01 5.456E+03 5.49E+03 4.580E+07 1.487E+08 1.94E+08 180 days 2.515E+01 5.352E+03 5.38E+03 4.586E+07 1.603E+08 2.06E+08 365 days 2.431E+01 5.175E+03 5.20E+03 4.597E+07 1.837E+08 2.30E+08 Inside Containment Wall Surface Dose Rates and Doses (1)
Time Gamma Dose Rate [rad/hr[
Beta Dose Rate
[rad/hr[
Total Dose Rate
[rad/hr]
Gamma Dose
[rad]
Beta Dose
[rad]
Total Dose
[rad]
1 second 3.408E+06 2.028E+07 2.37E+07 4.734E+02 2.817E+03 3.29E+03 30 minutes 1.906E+06 7.674E+06 9.58E+06 1.205E+06 5.196E+06 6.40E+06 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1.499E+06 6.592E+06 8.09E+06 2.046E+06 8.756E+06 1.08E+07 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.080E+06 4.849E+06 5.93E+06 3.314E+06 1.443E+07 1.77E+07 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.627E+05 1.508E+06 1.97E+06 7.346E+06 3.046E+07 3.78E+07 1 day 2.259E+05 5.753E+05 8.01E+05 1.228E+07 4.382E+07 5.61E+07 7 days 6.730E+04 2.350E+05 3.02E+05 2.832E+07 9.492E+07 1.23E+08 30 days 5.276E+03 1.708E+04 2.24E+04 4.141E+07 1.385E+08 1.80E+08 90 days 3.538E+01 5.456E+03 5.49E+03 4.274E+07 1.487E+08 1.91E+08 180 days 1.313E+01 5.352E+03 5.37E+03 4.277E+07 1.603E+08 2.03E+08 365 days 1.268E+01 5.175E+03 5.19E+03 4.283E+07 1.837E+08 2.27E+08 UNIT 2 1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
22 Table: 14.4.2-3C Page:
1 of 1 SUBMERGED LOWER VOLUME / CONTAINMENT SUMP DOSE RATES & DOSES1 Time Gamma Dose Rate (rad/hr)
Beta Dose Rate (rad/hr)
Total Dose Rate (rad/hr)
Gamma Dose (rad)
Beta Dose (rad)
Total Dose (rad) 1 second 1.201E+06 1.791E+05 1.38E+06 1.668E+02 2.488E+01 1.92E+02 30 minutes 9.675E+05 1.388E+05 1.11E+06 5.377E+05 7.812E+04 6.16E+05 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 8.100E+05 1.177E+05 9.28E+05 9.799E+05 1.418E+05 1.12E+06 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 6.118E+05 9.462E+04 7.06E+05 1.682E+06 2.467E+05 1.93E+06 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.834E+05 5.775E+04 3.41E+05 4.061E+06 6.719E+05 4.73E+06 1 day 1.315E+05 3.291E+04 1.64E+05 7.072E+06 1.364E+06 8.44E+06 7 days 3.467E+04 8.429E+03 4.31E+04 1.511E+07 3.346E+06 1.85E+07 30 days 9.922E+03 3.262E+03 1.32E+04 2.527E+07 6.123E+06 3.14E+07 90 days 3.470E+03 1.753E+03 5.22E+03 3.307E+07 9.351E+06 4.24E+07 180 days 1.733E+03 1.221E+03 2.95E+03 3.838E+07 1.249E+07 5.09E+07 365 days 7.349E+02 7.538E+02 1.49E+03 4.328E+07 1.673E+07 6.00E+07 UNIT 2 1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
22 Table:14.4.2-3D Page:
1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)
Thickness of Unit Density Material (mils)
Time 10 20 30 40 50 60 70 1 second 78.68%
68.30%
60.73%
54.66%
49.58%
45.22%
41.38%
30 minutes 75.18%
64.48%
56.96%
51.04%
46.14%
41.94%
38.30%
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 75.37%
65.13%
57.92%
52.22%
47.48%
43.41%
39.83%
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 75.21%
65.41%
58.57%
53.16%
48.62%
44.71%
41.28%
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 70.04%
60.58%
54.41%
49.62%
45.62%
42.23%
39.24%
1 day 58.35%
48.97%
43.53%
39.50%
36.24%
33.49%
31.11%
7 days 31.56%
23.58%
20.49%
18.47%
16.88%
15.57%
14.44%
30 days 24.49%
16.73%
14.23%
12.73%
11.60%
10.68%
9.90%
90 days 24.78%
16.40%
13.60%
12.01%
10.87%
9.98%
9.24%
180 days 25.51%
16.28%
13.08%
11.34%
10.18%
9.30%
8.59%
365 days 26.67%
16.08%
12.22%
10.24%
9.03%
8.18%
7.52%
UNIT 2 1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
22 Table: 14.4.2-3E Page:
1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)
Thickness of Aluminum (mils)
Time 10 20 30 40 50 60 70 1 second 62.82%
47.77%
37.66%
30.25%
24.53%
20.03%
16.43%
30 minutes 59.01%
44.39%
34.79%
27.80%
22.49%
18.33%
15.05%
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 59.89%
45.77%
36.38%
29.42%
24.07%
19.84%
16.46%
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 60.44%
46.99%
37.93%
31.11%
25.77%
21.51%
18.05%
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 56.09%
44.21%
36.31%
30.30%
25.53%
21.64%
18.42%
1 day 44.98%
35.09%
28.78%
24.07%
20.33%
17.27%
14.74%
7 days 21.26%
16.33%
13.36%
11.16%
9.42%
8.00%
6.83%
30 days 14.81%
11.21%
9.15%
7.65%
6.45%
5.48%
4.68%
90 days 14.25%
10.50%
8.53%
7.12%
6.01%
5.11%
4.36%
180 days 13.81%
9.80%
7.93%
6.61%
5.58%
4.74%
4.04%
365 days 13.09%
8.65%
6.92%
5.77%
4.87%
4.14%
3.53%
UNIT 2 1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
22 Table: 14.4.2-3F Page:
1 of 1 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)
Thickness of Steel (mils)
Time 10 20 30 40 50 60 70 1 second 38.44%
20.75%
11.76%
6.82%
4.01%
2.39%
1.43%
30 minutes 35.52%
19.00%
10.83%
6.41%
3.89%
2.41%
1.52%
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 37.10%
20.53%
12.05%
7.34%
4.59%
2.92%
1.88%
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 38.62%
22.20%
13.46%
8.42%
5.39%
3.50%
2.30%
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 36.91%
22.27%
14.05%
9.08%
5.96%
3.95%
2.64%
1 day 29.27%
17.77%
11.29%
7.33%
4.83%
3.22%
2.16%
7 days 13.58%
8.23%
5.23%
3.40%
2.24%
1.49%
1.00%
30 days 9.31%
5.64%
3.58%
2.33%
1.53%
1.02%
0.68%
90 days 8.68%
5.26%
3.34%
2.17%
1.43%
0.95%
0.64%
180 days 8.06%
4.88%
3.10%
2.01%
1.33%
0.88%
0.59%
365 days 7.05%
4.26%
2.70%
1.76%
1.16%
0.77%
0.52%
UNIT 2 1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA AANNDD M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
22 Table:14.4.2-3G Page:
1 of 1 UNIT 2 PIPES CONSIDERED IN CALCULATING OUTSIDE CONTAINMENT DOSES1 System Designation 2 Outside Diameter OD (inches)
Wall Thickness, T (inches)
OD/T CC M-14 4.5 0.438 10.3 CC M-14 3.5 0.438 7.99 CC M-14 2.0 0.344 5.81 CC B-14 6.625 0.134 49.44 CC B-14 8.625 0.148 58.28 SI K-14 4.5 0.337 13.35 SI B-14 4.5 0.12 37.5 SI B-14 6.625 0.134 49.44 SI K-14 2.375 0.276 8.61 SI K-14 1.9 0.2 9.5 SI K-14 1.05 0.154 6.82 RHR G-14 14.0 0.438 31.96 RHR G-14 3.5 0.216 16.20 RHR G-14 8.625 0.322 26.79 CS E-14 10.75 0.365 29.45 CS E-14 8.625 0.322 26.79 CS E-14 6.625 0.28 23.66 CS E-14 3.5 0.216 16.20 CS E-14 1.315 0.133 9.89 CS B-14 8.625 0.148 58.28 CS G-14 12.75 0.406 31.40 CS G-14 2.375 0.154 15.42 Key:
CC - Centrifugal Charging SI - Safety Injection RHR - Residual Heat Removal CS - Containment Spray 1 AEP: NRC: 05781, Attachment 4 2 Note: Pipe designation indicates materials of construction, seismic classification, and quality level. For further information, AEPSC specifications should be consulted.
UFSAR Revision 31.0
INDIANA AND MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT REPORT REPORT Revision: 24.0 Table:14.4.2-3H Page:
1 of 1 UNIT 2 PEAK ENVIRONMENTAL QUALIFICATION CONDITIONS FOR HELB OUTSIDE CONTAINMENT COMPARTMENT TEMPERATURE (ºF)
PRESSURE (psia)
East Main Steam Enclosure 440 18.7 West Main Steam Enclosure 485 20.6 Main Steam Accessway 347.8 18.2 Diesel Generator Pipe Tunnel 300 15.3 Turbine Driven Pump Room 298 16.7 ESW Tunnel 300 15.1 Turbine Room (Turbine Bldg. 609' Elev.)
473.8 15.45 Startup Blowdown Flashtank Room 216.5 15.2 NOTE:
Only major areas are identified in the table above.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision:
17 Table: 14.4.2-5 Page:
1 of 1 UNIT 2 POSTULATED MAJOR HIGH ENERGY LINE BREAKS System Line Size (in)
No. of Line Breaks Description/Location Building Area MS 30 2
Containment Penetrations Auxiliary ESE MS 30 2
Containment Penetrations Auxiliary WSE MS 30 2
5-way Restraint Auxiliary ESE MS 30 2
5-way Restraint Auxiliary WSE MS 4
2 At 30 in. Header Turbine Near Main Turbine MS 4
1 AFP Turbine Turbine TDAFP Room FW 14 2
Containment Penetrations Auxiliary ESE FW 14 2
Containment Penetrations Auxiliary WSE FW 20 1
Heater 6 Nozzle Turbine Heater 6 (A&B)
AFW/FW 6
2 At 14 in. Heater Auxiliary ESE AFW/FW 6
2 At 14 in. Heater Auxiliary WSE CVCS-LD 2
1 Letdown Heat Exchanger Auxiliary Letdown Heat Exchanger Room Notes:
- 1. Breaks in high energy systems that are not listed above are postulated to occur anywhere in the high energy portion of piping.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-1 Page:
1 of 1 UNIT 2 WEST STEAM ENCLOSURE/MAIN STEAM ACCESSWAY VENT AREA AND VOLUME INPUTS TO TMD Element No.1 Vent Area (ft2)
Volume (ft3) 1 Atmosphere Atmosphere 2
827 2919 3
875 4737 4
988 5736 5
487 6145 6
336 3900 7
530 9078 8
816 9078 9
558 9078 10 258 2033 11 507 7006 12 320 3266 1 Element numbers refer to Figures 14.4.6-1 and 14.4.6-2.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-2 Page:
1 of 1 UNIT 2 EAST STEAM ENCLOSURE VENT AREA AND VOLUME INPUTS TO TMD Element No.1 Vent Area (ft2)
Volume (ft3) 1 Atmosphere Atmosphere 2
898 4608 3
899 5102 4
880 4102 5
532 8145 6
547 7093 7
834 4041 1 Element numbers refer to Figures 14.4.6-3 and 14.4.6-4.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-3 Page:
1 of 1 UNIT 2 MODEL PARAMETERS (WEST MAIN STEAM ENCLOSURE AND MAIN STEAM ACCESSWAY)
LARGE BREAK Element No.1 Volume (ft3)
Height (ft)
Elevation (ft)
Heat Slab Area (ft2) 2 10600 29 633 2400 3
10600 29 633 2500 4
8400 11.5 621.5 1500 5
4500 21 600.5 3950 6
173000 20 587 3950 7
173000 20 587 1900 8
11300 18 662 1900 9
11300 18 662 1 Element numbers refer to Figure 14.4.6-5.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-3a Page:
1 of 1 UNIT 2 MODEL PARAMETERS (WEST MAIN STEAM ENCLOSURE AND MAIN STEAM ACCESSWAY)
SMALL BREAK Element No.1 Volume (ft3)
Height (ft)
Elevation (ft) 2 10600 29 633 3
10600 29 633 4
8400 11.5 622 5
4500 21 601 6
173000 20 587 7
173000 20 587 8
11300 18 664 9
11300 18 664 1 Element numbers refer to Figure 14.4.6-5.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-4 Page:
1 of 1 UNIT 2 MODEL PARAMETERS (EAST MAIN STEAM ENCLOSURE)
LARGE BREAK Element No.1 Volume (ft3)
Height (ft)
Elevation (ft)
Heat Slab Area (ft2) 2 10600 29 633 2250 3
10600 29 633 2550 4
8100 11.5 621.5 2500 5
5800 9.5 612 4700 6
9600
- 16.
612 1400 7
6900 18 662 1400 8
6900 18 662 9
1 Element numbers refer to Figure 14.4.6-6.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-4a Page:
1 of 1 UNIT 2 MODEL PARAMETERS (EAST MAIN STEAM ENCLOSURE)
SMALL BREAK Element No.1 Volume (ft3)
Height (ft)
Elevation (ft) 2 10600 29 633 3
10600 29 633 4
8100 11.5 622 5
5800 9.5 612 6
9600
- 16.
612 7
6900 18 664 8
6900 18 664 1 Element numbers refer to Figure 14.4.6-6.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 21.2 Table: 14.4.6-5 Page:
1 of 1 UNIT 2 MASS AND ENERGY RELEASE FOR STEAM LINE BREAK IN MAIN STEAM ENCLOSURE LARGE BREAK Time (sec)
Mass/Flow (lbm/sec)
Enthalpy (Btu/lbm) 0 0
1198 0.001 1 6508 1198 0.5 6508 1198 1.5 6124 1199 4.0 5599 1201 4.5 6091 1201 7.0 6091 1201 12.5 5788 1202 13.0 1976 1202 30.0 1158 1204 40.0 994.7 1204 60.0 890.3 1203 74.0 874.9 1205 75.0 866.8 1209 85.0 644.1 1245 95.0 256.2 1276 105.0 29.1 1294 200.0 29.2 1310 400.0 34.6 1312 600.0 34.6 1311 1800.00 34.6 1311 1800.01 0
1311 3600.0 0
1311 1 Full break opening assumed in 0.001 sec.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-5a Page:
1 of 1 UNIT 2 MASS AND ENERGY RELEASE FOR STEAM LINE BREAK IN MAIN STEAM ENCLOSURE SMALL BREAK Time (sec)
Flow (lbm/sec)
Enthalpy (Btu/lbm) 0.5 2102.
1196.
10.0 1832.
1199.
25.0 1645.
1201.
50.0 1575.
1202.
100.0 1568.
1202.
108.0 1568.
1202.
109.0 1673.
1201.
117.0 2057.
1197.
135.0 1823.
1200.
150.0 1642.
1202.
179.0 1453.
1203.
181.0 1447.
1204.
200.0 1410.
1208.
258.0 1099.
1238.
259.0 1089.
1239.
275.0 226.1 1281.
300.0 29.9 1296.
400.0 34.4 1297.
500.0 34.6 1298.
600.0 34.6 1299.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-6 Page:
1 of 1 UNIT 2 FEEDWATER LINE BREAK AT THE CONTAINMENT PENETRATION (APPLICABLE TO EAST OR WEST STEAM ENCLOSURE)
Mass and Enthalpy Forward Flow m = 4400 lbm/sec
Energy Flow = 1.896 x 106 n = 431 Btu/lbm Back Flow m = 6800 lbm/sec
3.713 x 106 n = 546 Btu/lbm 25 seconds Total = 5.609 x 106 (Up to 25 Seconds)
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-6a Page:
1 of 2 UNIT 2 STEAM LINE BREAK - FORWARD FLOW EAST/WEST STEAM ENCLOSURES (Pressure Response)
Time (sec)
Mass Flow 103 lb/sec Energy Release 106 Btu/sec 0.0 5.55 6.62 0.1 4.15 4.94 0.2 3.05 3.64 0.4 2.95 3.52 0.6 2.90 3.46 0.8 2.78 3.31 1.0 2.75 3.28 1.5 2.67 3.19 2.0 3.45 3.38 2.5 9.50 5.26 3.0 9.42 5.21 3.5 9.38 5.19 4.0 9.33 5.16 4.5 9.28 5.13 5.0 9.23 5.10 5.5 9.16 5.07 6.0 9.10 5.04 6.5 9.03 5.01 7.0 8.95 4.97 7.5 8.86 4.93 8.0 8.80 4.91 8.5 8.70 4.86 9.0 8.58 4.81 9.5 8.46 4.76 10.0 8.33 4.70 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-6a Page:
2 of 2 UNIT 2 STEAM LINE BREAK - FORWARD FLOW EAST/WEST STEAM ENCLOSURES (Pressure Response)
Time (sec)
Mass Flow 103 lb/sec Energy Release 106 Btu/sec 12.0 7.67 4.42 14.0 6.75 4.05 16.0 5.49 3.53 18.0 4.04 2.95 19.0 3.37 2.67 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-6b Page:
1 of 2 UNIT 2 EAST STEAM ENCLOSURE STEAMLINE BREAK - BACKFLOW (PRESSURE RESPONSE)
Time (sec)
Mass Flow 103 lb/sec Energy Release 106 Btu/sec 0.0 7.54 8.99 0.1 5.09 6.07 0.2 4.61 5.50 0.3 4.41 5.26 0.4 4.34 5.17 0.5 4.26 5.08 0.6 4.19 4.99 0.7 4.36 5.20 0.8 4.80 5.72 0.9 4.78 5.70 1.0 4.77 5.69 1.5 4.90 5.84 2.0 5.00 5.96 2.5 4.75 5.66 3.0 4.71 5.61 3.5 4.65 5.54 4.0 4.59 5.47 4.5 4.52 5.39 5.0 4.35 5.19 5.5 4.15 4.95 6.0 3.98 4.75 6.5 3.96 4.72 7.0 4.26 4.50 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-6b Page:
2 of 2 UNIT 2 EAST STEAM ENCLOSURE STEAMLINE BREAK - BACKFLOW (PRESSURE RESPONSE)
Time (sec)
Mass Flow 103 lb/sec Energy Release 106 Btu/sec 7.5 4.93 4.70 8.0 5.71 5.03 8.5 6.45 5.37 9.0 7.14 5.81 9.5 7.70 6.05 10.0 8.23 6.39 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-6c Page:
1 of 2 UNIT 2 WEST STEAM ENCLOSURE STEAMLINE BREAK - BACKFLOW (PRESSURE RESPONSE)
Time (sec)
Mass Flow 103 lb/sec Energy Release 106 Btu/sec 0.0 7.54 8.99 0.1 5.09 6.07 0.2 4.61 5.50 0.3 4.41 5.26 0.4 4.30 5.13 0.5 4.58 5.46 0.6 4.97 5.92 0.7 5.09 6.07 0.8 5.11 6.09 0.9 5.13 6.11 1.0 5.07 6.04 1.5 5.29 6.31 2.0 5.11 6.10 2.5 4.96 5.91 3.0 4.93 5.88 3.5 4.81 5.77 4.0 4.68 5.58 4.5 4.59 5.47 5.0 4.53 5.40 5.5 4.65 5.16 6.0 5.28 5.17 6.5 5.90 5.55 7.0 6.46 5.78 7.5 6.88 5.93 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-6c Page:
2 of 2 UNIT 2 WEST STEAM ENCLOSURE STEAMLINE BREAK - BACKFLOW (PRESSURE RESPONSE)
Time (sec)
Mass Flow 103 lb/sec Energy Release 106 Btu/sec 8.0 7.32 6.10 8.5 7.79 6.32 9.0 8.23 6.53 9.5 8.61 6.72 10.0 8.92 6.88 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-7 Page:
1 of 1 UNIT 2 FEEDWATER LINE BREAK AT THE TEE BETWEEN THE 20 INCH AND 30 INCH LINES, 20 INCH LINE RUNNING TO STEAM GENERATORS 2 AND 3 (APPLICABLE TO MAIN STEAM ACCESSWAY)
Mass and Enthalpy Forward Flow m = 9050 lbm/sec n = 431 Btu/lbm Back Flow m = 9050 lbm/sec n = 431 Btu/lbm 1.5 seconds UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-8 Page:
1 of 1 UNIT 2 RELATION OF NODE CALCULATED PRESSURE TO PRESSURE CAPABILITY OF SLABS Area Node Number Long Term Pressure Following Anticipated Transient Psi 1 Weakest Slab Capability for Static Differential Pressure Psi East Steam Enclosure 2
5.5 13.4 (See Figure 14.4.6-3) 3 5.5 11.6 4
5.5 11.6 5
5.5 11.6 2 6
5.5 11.6 (2) 7 5.5 13.4 West Steam Enclosure 2
4.7 10.9 (1)
(See Figure14.4.6-1) 3 4.7 10.9 (1) 4 4.7 22.1 5
4.7 4.5 3 (W SL1) 6 4.7 26.2 11 4.7 4.5 (3) (W SL1) 12 4.7 22.1 Main Steam Accessway 7
5.8 9.3 (See Figure14.4.6-1) 8 5.3 9.3 9
5.1 9.4 10 1.0 15.7 1 Tables 14.4.6-18, -19 and -20 show results of dynamic analyses for the respective slabs.
2 Other than lightly reinforced portion panel section E-W4, which will be allowed to fail without causing any damage to equipment required to safely shutdown the plant.
3 See Section 14.4.9.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-9 Page:
1 of 1 UNIT 2 PEAK PRESSURE DIFFERENTIAL MAIN STEAM LINE BREAK WEST STEAM ENCLOSURE Element No. 1 Peak Pressure Differential (psi) 1 0
2 11.9 3 (Break Location) 11.3 4
8.7 5
11.7 6
6.2 7
4.2 8
4.1 9
3.7 10
.65 11 8.8 12 7.6 1 Element numbers refer to Figure 14.4.6-1.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-10 Page:
1 of 1 UNIT 2 PEAK DIFFERENTIAL PRESSURE FEEDWATER LINE BREAK IN WEST STEAM ENCLOSURE Element No. 1 Peak Pressure (psig) 1 0
2 4.2 3 (Break Location) 4.3 4
2.7 5
3.7 6
2.1 7
1.7 8
1.6 9
1.4 10
.3 11 3.2 12 2.6 1 Element numbers refer to Figure 14.4.6-1.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-11 Page:
1 of 1 UNIT 2 PEAK DIFFERENTIAL PRESSURE FEEDWATER LINE BREAK IN MAIN STEAM ACCESSWAY Element No. 1 Peak Pressure (psi) 1 0
2 1.8 3
1.8 4
1.8 5
2.0 6
2.5 7 (Break Location) 5.8 8
5.3 9
5.1 10 1.0 11 2.0 12 1.8 1 Element numbers refer to Figure 14.4.6-1.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-12 Page:
1 of 1 UNIT 2 PEAK DIFFERENTIAL PRESSURE MAIN STEAM LINE BREAK IN EAST STEAM ENCLOSURE Element No. 1 Peak Pressure (psi) 1 0
2 7.7 3
7.8 4 (Break Location) 11.8 5
8.3 6
12.0 7
11.0 1 Element numbers refer to Figure 14.4.6-3.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-13 Page:
1 of 1 UNIT 2 PEAK DIFFERENTIAL PRESSURE FEEDWATER LINE BREAK IN EAST STEAM ENCLOSURE Element No. 1 Peak Pressure (psig) 1 0
2 2.7 3
2.8 4 (Break Location) 4.1 5
3.0 6
4.2 7
3.9 1 Element numbers refer to Figure 14.4.6-3.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-14 Page:
1 of 1 UNIT 2 RELATION OF NODES USED IN MAIN STEAM ACCESSWAY ANALYSIS TO PANEL IDENTIFICATION PRESENTED IN TABLE 14.4.6-17 Node No. 1 Affected Slabs 7
W-SL3, W-SL4, W-WN3, W-WS7, WS9, W-W7 8
W-SL3, W-SL4, W-SL5, W-WN3, W-WS7, W-WS8, W-WS9 9
W-SL3, W-SL5, W-WN4, W-WN3, W-WS8, W-WS9, W-WS10 10 W-W8, W-W9, W-WN4, W-W10, W-W9A 1 Node numbers refer to Figure 14.4.6-1.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-15 Page:
1 of 1 UNIT 2 PRESSURE CAPABILITY OF WALLS & SLABS AROUND MAIN STEAM LINE ENCLOSURE EAST OF CONTAINMENT
- 1.
MATERIAL PROPERTIES
- a. Concrete fc' = 3500 psi;
- b. Reinforcing steel fy= 40000 psi
- 2.
PRESSURE CAPABILITIES TABULATED
- a. Are ultimate values under static conditions;
- b. Do not include any other loading condition Panel ID Thickness (in.)
Pressure Capability (psi)
Remarks E-SL2 12 11.6 Punching Shear Around Col. Governs E-SL3 30 72.5 1 E-WN1 24 16.1 (1)
E-WN2 24 80.0 (1)
E-WS1 24 16.0 (1)
E-WS2 24 83.2 (1)
E-W1 24 13.4 (1)
E-W2 24 78.0 (1)
E-W3 24 11.6 (1)
E-W3 & E-W4, both curved are solved using planar projections E-W4 24 4.5 Critical Value of 4.5 PSI. Results from 1 way action of lightly reinforced portion of panel between the two large openings. The side portions of the panel have capability of 86.1 (1)
See Figure 14.4.6-3 for wall and slab identification.
1 Indicates diagonal tension failure governs.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table:14.4.6-15a Page:
1 of 1 UNT 2 RELATION OF NODES USED IN EAST STEAM ENCLOSURE ANALYSIS TO PANEL IDENTIFICATION PRESENTED IN TABLE 14.4.6-15 Node No. 1 Affected Slabs 2
E-WS1, E-W1 3
E-WS1, E-W3 4
E-WS3, E-WN1 5
E-W1, E-WS1, E-SL2, E-W4, E-W3, E-WS2, E-W2 6
E-W3, E-W4, E-SL2, E-WN1, E-WN2, E-W1, E-W2 7
E-W1, E-WN1 1 Node numbers refer to Figure 14.4.6-3.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-16 Page:
1 of 1 UNIT 2 PRESSURE CAPABILITY OF WALLS AND SLABS AT MAIN STEAM ENCLOSURE WEST OF CONTAINMENT
- 1.
MATERIAL PROPERTIES
- a. Concrete fc' = 3500 psi;
- b. Reinforcing steel fy = 40000 psi
- 2.
PRESSURE CAPABILITIES TABULATED
- a. Are ultimate values under static conditions;
- b. Do not include any other loading condition Panel ID Thickness (in.)
Pressure Capability (psi)
Remarks W-SL1 12 4.5 W-SL2 12 26.2 1 W-WN1 24 10.9 W-WN2 24 48.6 (1)
W-WS1 24 36.7 W-WS2 24 22.1 W-WS3 24 46.4 W-WS4 24 62.7 W-WS5 12 40.2 (1)
W-WS6 12 34.9 (1)
W-W1 12 27.3 W-W2 12 26.8 (1)
W-W3 36 54.9 W-W4 36 36.5 (1)
W-W5 36 84.5 W-W6 36 113.1 W-W7 36 121.6 (1)
See Figure 14.4.2-10 for wall and slab identification.
1 Indicates diagonal tension failure governs UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table:14.4.6-16a Page:
1 of 1 UNIT 2 RELATION OF NODES USED IN WEST STEAM ENCLOSURE ANALYSIS TO PANEL IDENTIFICATION PRESENTED IN TABLE 14.4.6-16 Node No. 1 Affected Slabs 2
W-W3, W-W4, W-W5, W-WN1 3
W-WN1 4
W-WS1, W-WS2 5
W-W4, W-W5, W-WN1, W-SL1 6
W-W5, W-W6, W-WN2, W-SL2, W-WS6, W-WS5 11 W-W4, W-W5, W-SL1, W-WS2, W-WS3 12 W-WS1, W-WS2, W-W3, W-W4 1 Node numbers refer to Figure 14.4.6-1.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-17 Page:
1 of 1 UNIT 2 PRESSURE CAPABILITY OF WALLS AND SLABS OF AUXILIARY BUILDING ADJACENT TO MAIN STEAM LINE ACCESSWAY
- 1.
MATERIAL PROPERTIES
- a. Concrete fc' = 3500 psi;
- b. Reinforcing steel fy = 40000 psi
- 2.
PRESSURE CAPABILITIES TABULATED
- a. Are ultimate values under static conditions;
- b. Do not include any other loading condition Panel ID Thickness (in.)
Pressure Capability (psi)
Remarks W-SL3 24 9.8 1 W-SL4 12 46.5 (1)
W-SL5 12 47.9 (1)
W-WN3 36 37.4 (1)
W-WN4 36 126.0 (1)
W-WS7 12 9.3 W-WS8 12 9.4 W-WS9 28 26.6 (1)
W-W8 12 15.7 W-W9 12 41.0 W-W10 42 30.0 W-W9A 12 38.4 See Figure 14.4.8-1 for layout and identification of walls and slabs.
1 Indicates diagonal tension failure governs UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.4 Table: 14.4.6-18 Page:
1 of 4 UNIT 2 EFFECTS OF PRESSURES AND CIRCUMFERENTIAL BREAK IMPINGEMENT LOADS ON WALLS AND SLABS (1) PANELS AT MAIN STEAM LINES ENCLOSURE EAST OF CONTAINMENT Panel Identification Governing Pipe Break Peak Applied Impingement Force (Kips)
Peak Applied Pressure (Psi)
Required Ductility Factor Allowable Ductility Factor Adequacy of Panel Remarks E-SL2 4F (MSB) 0 12.0 2.33 3.0 O.K.
E-SL3 4F (MSB) 0 12.0 1.00 3.0 O.K.
W-WN1 4G (MSB) 0 12.0 1.42 3.00 O.K.
Assuming 4G has same pressure build up as 4F E-WN2 4F (MSB) 0 12.0 1.00 3.00 O.K.
E-WN1 1C (MSB) 0 12.0 1.42 2.00 O.K.
Assuming 1C has same pressure build up as 1F E-WS2 1F (MSB) 0 12.0 1.00 3.00 O.K.
E-W1 1F or 4F (MSB) 0 12.0 2.13 3.00 O.K.
E-W2 1F or 4F (MSB) 0 12.0 1.00 3.00 O.K.
E-W3 1F or 4F (MSB) 0 12.0 1.51 3.00 O.K.
E-W4 1F or 4F 0
12.0 1.00 3.00 O.K.
Assuming central portion of panel is allowed to fail, but the larger side portions are adequate UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.4 Table: 14.4.6-18 Page:
2 of 4 UNIT 2 EFFECTS OF PRESSURES AND CIRCUMFERENTIAL BREAK IMPINGEMENT LOADS ON WALLS AND SLABS (2) PANELS AT MAIN STEAM LINES ENCLOSURE WEST OF CONTAINMENT Panel Identification Governing Pipe Break Peak Applied Impingement Force (Kips)
Peak Applied Pressure (Psi)
Required Ductility Factor Allowable Ductility Factor Adequacy of Panel Remarks W-SL1 2E or 3E (MSB) 0 11.7 60.44 10.0 N.G Slab modified and determined to be acceptable (see 14.4.9.1)
W-SL2 2E or 3E (MSB) 0 6.2 1.00 3.00 O.K.
W-WN1 3D (MSB) 0 11.9 2.56 10.00 O.K.
Assuming 3D has same pressure build up as 3E W-WN2 2E or 3E (MSB) 0 6.2 1.00 3.00 O.K.
W-WS1 2E (MSB) 0 11.9 1.00 10.00 O.K.
W-WS2 2D (MSB) 0 11.9 1.00 10.00 O.K.
Assuming 2D has same pressure build up as 2E W-WS3 2E (MSB) 0
- 11. 7 1.00 10.00 O.K.
W-WS4 Not affected by any pipe break within the west enclosure W-WS5 2E or 3E (MSB) 0 6.2 1.00 3.00 O.K.
W-WS6 2E or 3E (MSB) 0 6.2 1.00 3.00 O.K.
W-W1 2E or 3E (MSB) 0 6.2 1.00 10.0 O.K.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.4 Table: 14.4.6-18 Page:
3 of 4 UNIT 2 EFFECTS OF PRESSURES AND CIRCUMFERENTIAL BREAK IMPINGEMENT LOADS ON WALLS AND SLABS (2) PANELS AT MAIN STEAM LINES ENCLOSURE WEST OF CONTAINMENT Panel Identification Governing Pipe Break Peak Applied Impingement Force (Kips)
Peak Applied Pressure (Psi)
Required Ductility Factor Allowable Ductility Factor Adequacy of Panel Remarks W-W2 2E or 3E (MSB) 0 6.2 1.00 3.00 O.K.
W-W3 2E or 3F (MSB) 0 11.9 1.00 10.00 O.K.
W-W4 2E or 3E (MSB) 0 11.9 1.00 3.00 O.K.
W-W5 2E or 3E (MSB) 0 11.9 1.00 10.00 O.K.
W-W6 2E or 3E (MSB) 0 11.9 1.00 10.00 O.K.
UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.4 Table: 14.4.6-18 Page:
4 of 4 UNIT 2 EFFECTS OF PRESSURES AND CIRCUMFERENTIAL BREAK IMPINGEMENT LOADS ON WALLS AND SLABS (3) AUXILIARY BUILDING PANELS ADJACENT TO MAIN STEAM LINES ACCESSWAY Panel Identification Governing Pipe Break Peak Applied Impingement Force (Kips)
Peak Applied Pressure (Psi)
Required Ductility Factor Allowable Ductility Factor Adequacy of Panel Remarks W-SL3 F8 (FWB) 355 5.8 1.00 3.00 O.K.
W-SL4 F8 (FWB) 0 5.8 1.00 3.00 O.K.
W-SL5 F8 (FWB) 0 5.3 1.00 3.00 O.K.
W-WN3 F8 (FWB) 0 5.8 1.00 3.00 O.K.
W-WN4 F8 (FWB) 0 1.0 1.00 3.00 O.K.
W-WS7 F8 (FWB) 0 5.8 1.17 10.00 O.K.
W-WS8 F8 (FWB) 0 5.8 1.05 10.00 O.K.
W-WS9 F8 (FWB) 0 5.8 1.00 3.00 O.K.
W-W7 F8 (FWB) 0 5.8 1.00 3.00 O.K.
W-W8 F8 (FWB) 0 1.0 1.00 10.00 O.K.
W-W9 F8 (FWB) 0 1.0 1.00 10.00 O.K.
W-W9A F8 (FWB) 0 1.0 1.00 10.00 O.K.
W-W10 F10 (FWB) 355 5.1 1.00 10.00 O.K.
Assuming F10 has same pressure build up as F8 (3) MSB = main steam line break FWB = feedwater line break N.G. = no good UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-19 Page:
1 of 1 UNIT 2 PANELS TO BE PROTECTED FROM MAIN STEAM LINE LONGITUDINAL BREAKS Longitudinal Breaks Panels To Be Protected Remarks 1F E-SL1, E-WN1, E-WS1 4F E-SL2, E-WN1, E-WS1 1G E-SL2, E-W1 4G E-SL2, E-W1 2E W-WS2, W-SL1, W-WN1 3E W-WS2, W-SL1, W-WN1 2D W-SL1, W-W4 3D W-SL1, W-W4 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.6 Table: 14.4.6-20 Page:
1 of 1 UNIT 2 FEEDWATER LINE BREAKS Longitudinal Breaks Panels To Be Protected Remarks F26, F25 E-SL2 F15, F16, F17 W-SL1 Calculations made for F15 F9, F10, F11, F12, F13 W-WS7 Calculations made for F9 only UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.4 Table: 14.4.8-1 Page 1 of 2 UNIT 2 ULTIMATE SHEAR STRESS AT DISTANCE DE FROM THE SUPPORTS FOR TWO-WAY ELEMENTS I. THREE EDGES FIXED AND ONE EDGE FREE LIMITS ULTIMATE HORIZONTAL SHEAR STRESS (Vµ)H LIMITS ULTIMATE VERTICAL SHEAR STRESS(Vµ)r 2
1 e x
/
d 0
x d
4 5
x d
x d
1 r
3 e
e 2
e
µ 2
1 e H
/
d 0
HL x
d 4
L x
3 H
d HL x
d L
x 1
H d
1 r
3 e
e e
e
µ 1
x
/
de 2
1
x d
2 x
d 1
r e
e
µ 1
H
/
de 2
1
HL x
d 2
1 H
d HL x
d L
x 1
H d
1 r
e e
e e
µ 4
1 e L
/
d 0
LH y
d 8
H y
6 L
d 2
LH y
d 2
H y
2 L
d 2
1 r
3 e
e e
e
µ 1
y
/
d 0
e
y d
4 5
y d
y d
1 r
3 e
e 2
e
µ 2
1 e
4 1
L
/
d
LH y
d 2
1 L
d 4
LH y
d 2
H y
2 L
d 2
1 r
e e
e e
µ 1
y
/
de 2
1
y d
2 y
d 1
r e
e
µ UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.4 Table: 14.4.8-1 Page 2 of 2 UNIT 2 II. FOUR EDGES FIXED NOTE: L MAY EITHER BE LONGER OR SHORTER THAN H 2
1 e x
/
d 0
x d
4 5
x d
x d
1 r
3 e
e 2
e
µ 4
1 e H
/
d 0
HL x
d 8
L x
3 H
d HL x
d 2
L x
1 H
d 2
1 r
3 e
e e
e
µ 1
x
/
de 2
1
x d
2 x
d 1
r e
e
µ 2
1 e
4 1
H
/
d
HL x
d 4
1 H
d HL x
d 2
L x
1 H
d 2
1 r
e e
e e
µ rµ = ULTIMATE PRESSURE LOAD ON ELEMENT de = EFFECTIVE DEPTH OF ELEMENT NOTE: EXPRESSIONS IN THIS TABLE ARE TAKEN FROM REF. 2 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 16.4 Table: 14.4.8-2 Page:
1 of 1 Unit 2 Material Properties Concrete: f'c = 3500 psi Reinforcing Steel: fy = 40,000 psi Ultimate Moment of 1 ft wide Rectangular Section C = (0.85fc)(12)(0.85C)
T= sfy T = C
(
)(
)(
)
85
.0 12 c'
0.85f sf C
y
=
Mu = T(d-0.425c)
After Substitutions, Mu = 3.33s(d-0.56s)
(1)
Permissible Diagonal Tension Shear Stress
[
]
c f
28
.2 2500 c
f 9.1 Vc
+
=
(2)
Permissible Punching Shear Stress c
f 4
Vc
=
(3)
Strength Increase Due to Dynamic Effects (Ref: 2)
(1) Where shear or diagonal tension governs, no increase is allowed.
(2) Where flexure governs, the following increases were used:
f'c = +25%, fy = +10%
Ultimate Moment of 1 ft Wide Rectangular Section: Mu = 3.67s(d-0.49s)
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT Revised:
29.0 Table:14.4.11-1 Page:
1 of 1 Unit 2 Peak Environmental Qualification Conditions for LOCA, MSLB, and Feedwater Line Break Inside Containment LOCA Location Temperature (ºF)
Pressure (psig)
Upper Compartment 1601 11.62 Lower Compartment 2353 11.62 Instrument and F/A Room 2354,3 13.95 MSLB and Feedwater Line Break Location Temperature (ºF)
Pressure (psig)
Upper Compartment Lower Compartment 3257 1 UFSAR Figure 14.3.4-7 2 UFSAR Figure 14.3.4-6A 3 UFSAR Figure 14.3.4-8 4 Deleted 5 UFSAR Table 14.3.4-40 reports this value calculated for the Steamline Break in the Steam Generator Doghouse.
The Steam Generator Doghouse peak pressure is a bounding value for Upper and Lower Containment.
6 UFSAR Figure 14.3.4-11 (Unit 1) and Figure 14.3.4-11A (Unit 2) 7 UFSAR Figure 14.3.4-12 (Unit 1) and Figure 14.3.4-12B (Unit 2) 135 (U1)6, 128 (U2)6 20.85 20.85 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 29.0 Table: 14.4.11-2 Page:
1 of 1 UNIT 2 AIRBORNE SOURCE TERM DOSES AND DOSE RATES Containment Centerline Dose Rates and Doses1 Time Gamma Dose Rate [rad/hr[
Beta Dose Rate
[rad/hr[
Total Dose Rate
[rad/hr]
Gamma Dose
[rad]
Beta Dose
[rad]
Total Dose
[rad]
1 second 4.293E+06 2.028E+07 2.46E+07 5.962E+02 2.817E+03 3.41E+03 30 minutes 1.905E+06 7.674E+06 9.58E+06 1.330E+06 5.196E+06 6.53E+06 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1.418E+06 6.592E+06 8.01E+06 2.145E+06 8.756E+06 1.09E+07 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 9.818E+05 4.849E+06 5.83E+06 3.319E+06 1.443E+07 1.77E+07 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.013E+05 1.508E+06 1.91E+06 6.889E+06 3.046E+07 3.73E+07 1 day 2.181E+05 5.753E+05 7.93E+05 1.131E+07 4.382E+07 5.51E+07 7 days 8.274E+04 2.350E+05 3.18E+05 3.014E+07 9.492E+07 1.25E+08 30 days 4.543E+03 1.708E+04 2.16E+04 4.480E+07 1.385E+08 1.83E+08 90 days 3.484E+01 5.456E+03 5.49E+03 4.580E+07 1.487E+08 1.94E+08 180 days 2.515E+01 5.352E+03 5.38E+03 4.586E+07 1.603E+08 2.06E+08 365 days 2.431E+01 5.175E+03 5.20E+03 4.597E+07 1.837E+08 2.30E+08 Inside Containment Wall Surface Dose Rates and Doses (1)
Time Gamma Dose Rate [rad/hr[
Beta Dose Rate
[rad/hr[
Total Dose Rate
[rad/hr]
Gamma Dose
[rad]
Beta Dose
[rad]
Total Dose
[rad]
1 second 3.408E+06 2.028E+07 2.37E+07 4.734E+02 2.817E+03 3.29E+03 30 minutes 1.906E+06 7.674E+06 9.58E+06 1.205E+06 5.196E+06 6.40E+06 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1.499E+06 6.592E+06 8.09E+06 2.046E+06 8.756E+06 1.08E+07 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.080E+06 4.849E+06 5.93E+06 3.314E+06 1.443E+07 1.77E+07 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.627E+05 1.508E+06 1.97E+06 7.346E+06 3.046E+07 3.78E+07 1 day 2.259E+05 5.753E+05 8.01E+05 1.228E+07 4.382E+07 5.61E+07 7 days 6.730E+04 2.350E+05 3.02E+05 2.832E+07 9.492E+07 1.23E+08 30 days 5.276E+03 1.708E+04 2.24E+04 4.141E+07 1.385E+08 1.80E+08 90 days 3.538E+01 5.456E+03 5.49E+03 4.274E+07 1.487E+08 1.91E+08 180 days 1.313E+01 5.352E+03 5.37E+03 4.277E+07 1.603E+08 2.03E+08 365 days 1.268E+01 5.175E+03 5.19E+03 4.283E+07 1.837E+08 2.27E+08 1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 29.0 Table: 14.4.11-3 Page:
1 of 1 UNIT 2 SUBMERGED LOWER VOLUME / CONTAINMENT SUMP DOSE RATES & DOSES1 Time Gamma Dose Rate (rad/hr)
Beta Dose Rate (rad/hr)
Total Dose Rate (rad/hr)
Gamma Dose (rad)
Beta Dose (rad)
Total Dose (rad) 1 second 1.201E+06 1.791E+05 1.38E+06 1.668E+02 2.488E+01 1.92E+02 30 minutes 9.675E+05 1.388E+05 1.11E+06 5.377E+05 7.812E+04 6.16E+05 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 8.100E+05 1.177E+05 9.28E+05 9.799E+05 1.418E+05 1.12E+06 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 6.118E+05 9.462E+04 7.06E+05 1.682E+06 2.467E+05 1.93E+06 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.834E+05 5.775E+04 3.41E+05 4.061E+06 6.719E+05 4.73E+06 1 day 1.315E+05 3.291E+04 1.64E+05 7.072E+06 1.364E+06 8.44E+06 7 days 3.467E+04 8.429E+03 4.31E+04 1.511E+07 3.346E+06 1.85E+07 30 days 9.922E+03 3.262E+03 1.32E+04 2.527E+07 6.123E+06 3.14E+07 90 days 3.470E+03 1.753E+03 5.22E+03 3.307E+07 9.351E+06 4.24E+07 180 days 1.733E+03 1.221E+03 2.95E+03 3.838E+07 1.249E+07 5.09E+07 365 days 7.349E+02 7.538E+02 1.49E+03 4.328E+07 1.673E+07 6.00E+07 1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 29.0 Table: 14.4.11-4 Page:
1 of 1 UNIT 2 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)
Thickness of Unit Density Material (mils)
Time 10 20 30 40 50 60 70 1 second 78.68%
68.30%
60.73%
54.66%
49.58%
45.22%
41.38%
30 minutes 75.18%
64.48%
56.96%
51.04%
46.14%
41.94%
38.30%
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 75.37%
65.13%
57.92%
52.22%
47.48%
43.41%
39.83%
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 75.21%
65.41%
58.57%
53.16%
48.62%
44.71%
41.28%
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 70.04%
60.58%
54.41%
49.62%
45.62%
42.23%
39.24%
1 day 58.35%
48.97%
43.53%
39.50%
36.24%
33.49%
31.11%
7 days 31.56%
23.58%
20.49%
18.47%
16.88%
15.57%
14.44%
30 days 24.49%
16.73%
14.23%
12.73%
11.60%
10.68%
9.90%
90 days 24.78%
16.40%
13.60%
12.01%
10.87%
9.98%
9.24%
180 days 25.51%
16.28%
13.08%
11.34%
10.18%
9.30%
8.59%
365 days 26.67%
16.08%
12.22%
10.24%
9.03%
8.18%
7.52%
1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 29.0 Table: 14.4.11-5 Page:
1 of 1 UNIT 2 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)
Thickness of Aluminum (mils)
Time 10 20 30 40 50 60 70 1 second 62.82%
47.77%
37.66%
30.25%
24.53%
20.03%
16.43%
30 minutes 59.01%
44.39%
34.79%
27.80%
22.49%
18.33%
15.05%
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 59.89%
45.77%
36.38%
29.42%
24.07%
19.84%
16.46%
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 60.44%
46.99%
37.93%
31.11%
25.77%
21.51%
18.05%
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 56.09%
44.21%
36.31%
30.30%
25.53%
21.64%
18.42%
1 day 44.98%
35.09%
28.78%
24.07%
20.33%
17.27%
14.74%
7 days 21.26%
16.33%
13.36%
11.16%
9.42%
8.00%
6.83%
30 days 14.81%
11.21%
9.15%
7.65%
6.45%
5.48%
4.68%
90 days 14.25%
10.50%
8.53%
7.12%
6.01%
5.11%
4.36%
180 days 13.81%
9.80%
7.93%
6.61%
5.58%
4.74%
4.04%
365 days 13.09%
8.65%
6.92%
5.77%
4.87%
4.14%
3.53%
1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 29.0 Table: 14.4.11-6 Page:
1 of 1 UNIT 2 BETA DOSE FACTORS1 DOSE FROM AIRBORNE SOURCE AFTER ATTENUATION (PERCENTAGE OF DOSE PASSING THROUGH SHIELD)
Thickness of Steel (mils)
Time 10 20 30 40 50 60 70 1 second 38.44%
20.75%
11.76%
6.82%
4.01%
2.39%
1.43%
30 minutes 35.52%
19.00%
10.83%
6.41%
3.89%
2.41%
1.52%
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 37.10%
20.53%
12.05%
7.34%
4.59%
2.92%
1.88%
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 38.62%
22.20%
13.46%
8.42%
5.39%
3.50%
2.30%
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 36.91%
22.27%
14.05%
9.08%
5.96%
3.95%
2.64%
1 day 29.27%
17.77%
11.29%
7.33%
4.83%
3.22%
2.16%
7 days 13.58%
8.23%
5.23%
3.40%
2.24%
1.49%
1.00%
30 days 9.31%
5.64%
3.58%
2.33%
1.53%
1.02%
0.68%
90 days 8.68%
5.26%
3.34%
2.17%
1.43%
0.95%
0.64%
180 days 8.06%
4.88%
3.10%
2.01%
1.33%
0.88%
0.59%
365 days 7.05%
4.26%
2.70%
1.76%
1.16%
0.77%
0.52%
1 Per Calculation RS-C-0046 UFSAR Revision 31.0
IINNDDIIAANNAA M MIICCHHIIGGAANN PPOOW WEERR DD.. CC.. CCOOOOKK NNUUCCLLEEAARR PPLLAANNTT UUPPDDAATTEEDD FFIINNAALL SSAAFFEETTYY AANNAALLYYSSIISS RREEPPOORRTT Revision: 29.0 Table: 14.4.11-7 Page:
1 of 1 UNIT 2 PIPES CONSIDERED IN CALCULATING OUTSIDE CONTAINMENT DOSES1 System Designation 2 Outside Diameter OD (inches)
Wall Thickness, T (inches)
OD/T CC M-14 4.5 0.438 10.3 CC M-14 3.5 0.438 7.99 CC M-14 2.0 0.344 5.81 CC B-14 6.625 0.134 49.44 CC B-14 8.625 0.148 58.28 SI K-14 4.5 0.337 13.35 SI B-14 4.5 0.12 37.5 SI B-14 6.625 0.134 49.44 SI K-14 2.375 0.276 8.61 SI K-14 1.9 0.2 9.5 SI K-14 1.05 0.154 6.82 RHR G-14 14.0 0.438 31.96 RHR G-14 3.5 0.216 16.20 RHR G-14 8.625 0.322 26.79 CS E-14 10.75 0.365 29.45 CS E-14 8.625 0.322 26.79 CS E-14 6.625 0.28 23.66 CS E-14 3.5 0.216 16.20 CS E-14 1.315 0.133 9.89 CS B-14 8.625 0.148 58.28 CS G-14 12.75 0.406 31.40 CS G-14 2.375 0.154 15.42 Key:
CC - Centrifugal Charging SI - Safety Injection RHR - Residual Heat Removal CS - Containment Spray 1 AEP: NRC: 05781, Attachment 4 2 Note: Pipe designation indicates materials of construction, seismic classification, and quality level. For further information, AEPSC specifications should be consulted.
UFSAR Revision 31.0
INDIANA MICHIGAN POWER D. C. COOK NUCLEAR PLANT UPDATED FINAL SAFETY ANALYSIS REPORT REPORT REPORT Revision: 29.0 Table: 14.4.11-8 Page:
1 of 1 UNIT 2 PEAK ENVIRONMENTAL QUALIFICATION CONDITIONS FOR HELB OUTSIDE CONTAINMENT COMPARTMENT TEMPERATURE (ºF)
PRESSURE (psia)
East Main Steam Enclosure 440 18.7 West Main Steam Enclosure 485 20.6 Main Steam Accessway 347.8 18.2 Diesel Generator Pipe Tunnel 300 15.3 Turbine Driven Pump Room 298 16.7 ESW Tunnel 300 15.1 Turbine Room (Turbine Bldg. 609' Elev.)
473.8 15.45 Startup Blowdown Flashtank Room 216.5 15.2 NOTE:
Only major areas are identified in the table above.
UFSAR Revision 31.0