-
EDG – Failure to Start/Load
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Hurricane, Tropical Storm, OR Coastal Flood WARNINGS are issued for the area
AB.MISC-0001, Acts of Nature
-
Loss of SFSC Heat Removal System AND 8 hour time limit CANNOT be met.
AB.MISC-0004, ISFSI- Spent Fuel Storage Cask (SFSC) Heat Removal System
-
Station Service Water Intake Structure Icing
AB.COOL-0001, Station Service Water
-
Control Area Battery Room Ventilation is lost
AB.HVAC-0001, HVAC
-
A Seismic Event has occurred
AB.MISC-0001, Acts of Nature
-
Loss of inventory with excessive Reactor Building Equipment Drain sump runs
AB.COOL-0004, Fuel Pool Cooling
-
Loss of Inventory from the Cavity with Vessel Head Removed during Refueling
AB.RPV-0004, Reactor Level Control
-
Damage to one or more SFSC
AB.MISC-0004, ISFSI- Spent Fuel Storage Cask (SFSC) Heat Removal System
-
Loss of 1 (A-D) D481 INVERTER
AB.ZZ-0136, Loss of 120 VAC Inverter
-
ANY SSWS MALFUNCTION
AB.COOL-0001, Station Service Water
-
Rising Radioactive Gaseous Release rate
AB.CONT-0004, Radioactive Gaseous Release
-
Single Recirculation Pump Runaway
AB.RPV-0001, Reactor Power
-
Reactor Pressure is ³ 900 psig AND Charging Water Header Pressure is < 940 psig and two or more Control Rod Scram Accumulators are INOPERABLE, at least one of which is associated with a WITHDRAWN Control Rod
AB.IC-0001, Control Rod
-
Loss of inventory with excessive Reactor Building Equipment Drain sump runs
AB.COOL-0005, Total Loss of Station Service Water
-
Drywell Pressure >= 0.75psig AND No Evidence of Elevated Coolant System Leakage
AB.CONT-0001, Primary Containment
-
Loss of AVH-407 AND BVH-407
AB.HVAC-0001, HVAC
-
High Level in the Head Tank
AB.COOL-0003, Reactor Auxiliary Cooling
-
TIP CANNOT be isolated manually AND it is a source of leakage
AB.CONT-0002, Primary Containment
-
LOP with concurrent loss of EDG D
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
TIP fails to automatically retract
AB.CONT-0002, Primary Containment
-
Traveling Screen D/P High AND Screen is NOT moving
AB.COOL-0001, Station Service Water
-
River Water Temperature is >= 88°F
AB.COOL-0001, Station Service Water
-
Inadvertent HPCI Initiation
AB.RPV-0001, Reactor Power
-
Sustained Winds >= 40 mph or >= 58 mph gusts
AB.MISC-0001, Acts of Nature
-
Loss/Malfunction of the Heat Balance
AB.MISC-0002, CRIDS / Overhead Annunciators
-
Entered GRID Disturbance abnormal for any reason
AB.BOP-0004, Grid Disturbances
-
Isolation of Condensate through all 3, 4 and 5 Feedwater Heaters
AB.RPV-0004, Reactor Level Control
-
Service Water Strainer D/P High in the SSW Loop NOT Supplying TACS
AB.COOL-0001, Station Service Water
-
Any Loss of Feedwater Heating – Prompt Fuel Reliability Actions
AB.BOP-0001, Feedwater Heating
-
Simultaneous failures of indication and/or control of multiple systems
AB.ZZ-0136, Loss of 120 VAC Inverter
-
Emergency Makeup from Service Water to the 'A' SACS loop is required
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
Main Turbine high vibration.
AB.BOP-0002, Main Turbine
-
Indication or Potential for Failed Fuel
AB.RPV-0008, Reactor Coolant Activity
-
BOTH Recirculation Pumps TRIPPED AND Potential exists for Thermal Stratification
AB.RPV-0003, Recirculation System/Power Oscillations
-
Any SRV OPEN AND Suppression Chamber Venting or Purging in progress
AB.RPV-0006, Safety / Relief Valve
-
Steam Tunnel Temperature Rising
AB.BOP-0005, Main Steam Tunnel Temperature
-
Room Temperature CANNOT be maintained <100degF (specific rooms listed in Table 1)
AB.HVAC-0001, HVAC
-
Hard Torus Vent Activity Rising
AB.CONT-0004, Radioactive Gaseous Release
-
Loss of Stator Cooling
AB.BOP-0002, Main Turbine
-
EDG Trip
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Complete and sustained loss of TACS.
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
APRM Malfunction
AB.IC-0004, Neutron Monitoring
-
Loss of CRD Purge to RWCU pumps(s)
AB.IC-0001, Control Rod
-
Control Signal Failure
AB.RPV-0004, Reactor Level Control
-
Rising Bellows Temperature for any 3-Stage SRV
AB.RPV-0006, Safety / Relief Valve
-
1 SCP Tripped
AB.RPV-0004, Reactor Level Control
-
Isolation of Condensate through all 1 & 2 Feedwater Heaters
AB.RPV-0004, Reactor Level Control
-
Drywell Pressure Lowering
AB.CONT-0002, Primary Containment
-
Open SRV Fails to CLOSE
AB.RPV-0006, Safety / Relief Valve
-
Pressure Control Valve has failed
AB.IC-0001, Control Rod
-
Both the Emergency Seal Oil Pump and The Main Seal Oil Pump CANNOT be started, or BEFORE Generator H2 pressure drops below 30 psig
AB.BOP-0002, Main Turbine
-
Oscillating Reactor Recirculation Pump Speed
AB.RPV-0003, Recirculation System/Power Oscillations
-
Unplanned 1&2 Drain Cooler Isolation
AB.BOP-0001, Feedwater Heating
-
A Seismic Event EXCEEDS the allowable Operating Basis Earthquake (0.1g)
AB.MISC-0001, Acts of Nature
-
Additional Air Dryer Capacity is Required
AB.COMP-0001, Instrument and/or Service Air
-
Any Secondary Containment Automatic Isolation Damper is INOPERABLE
AB.CONT-0003, Reactor Building
-
FRVS CANNOT maintain a NEGATIVE Reactor Building Reactor Building d/p of at least < -0.30 inches WG
AB.CONT-0003, Reactor Building
-
Potential High Reactor Coolant Activity
AB.RPV-0008, Reactor Coolant Activity
-
Reactor power is >5% and the Offgas System cannot be re-established.
AB.BOP-0006, Main Condenser Vacuum
-
Loss of inventory with Rising CST level
AB.COOL-0004, Fuel Pool Cooling
-
RACS Flow Control Valve Failure
AB.COOL-0003, Reactor Auxiliary Cooling
-
High Stator Water Cooling Temperature
AB.BOP-0002, Main Turbine
-
Uncoupled Rod AND Movement Permitted by the RWM
AB.IC-0001, Control Rod
-
Elevated Scram Discharge Volume Level
AB.IC-0002, Scram Discharge Volume
-
Alternate Loop of RHR is required to restore Shutdown Cooling
AB.RPV-0009, Shutdown Cooling
-
Uncoupled Rod AND Movement NOT Permitted by RWM OR First Attempt to Recouple Failed
AB.IC-0001, Control Rod
-
LPRM Malfunction
AB.IC-0004, Neutron Monitoring
-
Turbine Bldg. Chill Water System is lost to the Drywell
AB.CONT-0001, Primary Containment
-
LOP / SBO / ELAP
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Heavy snowfall is forecast for the area
AB.MISC-0001, Acts of Nature
-
Suspected Condenser Waterbox Fouling
AB.BOP-0006, Main Condenser Vacuum
-
Reactor Bldg/Suppression Chamber Vacuum Breaker failed OPEN
AB.CONT-0002, Primary Containment
-
Rod Drive Control System Malfunction
AB.IC-0001, Control Rod
-
Offgas Malfunction.
AB.BOP-0006, Main Condenser Vacuum
-
Reactor Pressure >= 1020 psig
AB.RPV-0005, Reactor Pressure
-
RPV Temperature and Pressure CANNOT be maintained using Normal OR Alternate Decay Heat Removal
AB.RPV-0009, Shutdown Cooling
-
RPV Pressure Changing
AB.RPV-0005, Reactor Pressure
-
Restoration of Offsite Power via T2
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Suppression Chamber/Drywell Vacuum Breaker NOT CLOSED
AB.CONT-0002, Primary Containment
-
Loss of 1 (A-D) D484 INVERTER
AB.ZZ-0136, Loss of 120 VAC Inverter
-
Diesel Area Battery Room Ventilation is lost
AB.HVAC-0001, HVAC
-
Any Loss of Feedwater Heating – Balance of Plant Actions
AB.BOP-0001, Feedwater Heating
-
Temperature of RACS cannot be maintained below 95ºF
AB.COOL-0003, Reactor Auxiliary Cooling
-
EHC Leak
AB.BOP-0003, Turbine Hydraulic Pressure
-
Loss of inventory with excessive Drywell Equipment/Floor Drain sump runs
AB.COOL-0005, Total Loss of Station Service Water
-
A Tornado has struck the plant
AB.MISC-0001, Acts of Nature
-
Degraded FPCC cannot handle Pool Heat Load
AB.COOL-0005, Total Loss of Station Service Water
-
Following ANY GRID Disturbance resulting in a Power Reduction.
AB.BOP-0004, Grid Disturbances
-
SRV(s) that were Open indicate CLOSED
AB.RPV-0006, Safety / Relief Valve
-
Emergency Makeup from Fire Water is required
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
SJAE Malfunction
AB.BOP-0006, Main Condenser Vacuum
-
Condensate Transfer is required for S/D cooling
AB.RPV-0009, Shutdown Cooling
-
Predicted Voltage Drop Event will result in an instantaneous voltage drop at the 500 KV switchyard of greater than 2.5%.
AB.BOP-0004, Grid Disturbances
-
Potential Dropped Control Rod.
AB.RPV-0001, Reactor Power
-
Loss of the RHR system providing Shutdown Cooling
AB.RPV-0009, Shutdown Cooling
-
Inadvertent Isolation of ALL PCIG Primary Containment Valves.
AB.COMP-0002, Primary Containment Instrument Gas
-
Loss of 1 (A-D) D483 INVERTER
AB.ZZ-0136, Loss of 120 VAC Inverter
-
Average Suppression Pool Water Temperature >95°F
AB.RPV-0006, Safety / Relief Valve
-
Forced Circulation CANNOT be established using preferred RHR loops or Reactor Recirculation
AB.RPV-0009, Shutdown Cooling
-
Main Turbine Trip
AB.BOP-0002, Main Turbine
-
System Isolation has occurred
AB.CONT-0002, Primary Containment
-
Dual Rod Selection
AB.IC-0001, Control Rod
-
Additional SSW Pump required to be placed in service WITH evidence of fouling
AB.COOL-0001, Station Service Water
-
Rising Reactor Coolant Conductivity
AB.RPV-0007, Reactor Coolant Conductivity
-
Loss of inventory with rising RACS head tank level
AB.COOL-0005, Total Loss of Station Service Water
-
Evidence of physical damage on EITHER: Main Turbine OR Turbine Auxiliaries
AB.BOP-0002, Main Turbine
-
S/U Valve Fails CLOSED
AB.RPV-0004, Reactor Level Control
-
Inadvertent D Channel Isolation
AB.COMP-0002, Primary Containment Instrument Gas
-
EDG is required for a LOP and EDG Jacket Water Leak >54 ml/minute
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
2 PCP’s Tripped/Stopped
AB.RPV-0004, Reactor Level Control
-
3 PCP’s Tripped
AB.RPV-0004, Reactor Level Control
-
Circulating Water Pump(s) tripped
AB.BOP-0006, Main Condenser Vacuum
-
Service Water Strainer D/P High in the SSW Loop Supplying TACS
AB.COOL-0001, Station Service Water
-
Stuck Control Rod in defueled cell
AB.IC-0001, Control Rod
-
FRVS Vent Activity is Rising
AB.CONT-0004, Radioactive Gaseous Release
-
Suspected in-leakage from another system
AB.COOL-0003, Reactor Auxiliary Cooling
-
Hydrogen Seal Oil System Malfunction
AB.BOP-0002, Main Turbine
-
Complete loss CRIDS
AB.MISC-0002, CRIDS / Overhead Annunciators
-
Stuck Control Rod at Notch 00
AB.IC-0001, Control Rod
-
Level above the ROD BLOCK Setpoint AND Level Continuing to rise
AB.IC-0002, Scram Discharge Volume
-
The National Weather Service Probabilistic Quantitative Precipitation Forecast (PQPF) predicts Local Intense Precipitation (LIP) to exceed 6 inches over the next 24 hours
AB.MISC-0001, Acts of Nature
-
Temperature of either OR both SACS loops cannot be maintained below 95ºF
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
High Turbine Bldg. Chill Water Temperature
AB.CONT-0001, Primary Containment
-
Loss of 1AD492/1BD492 BOP COMPUTER INVERTERS
AB.ZZ-0136, Loss of 120 VAC Inverter
-
Geomagnetic Induced Current Alarm (at Main Transformer Local Alarm Panel) AND/OR DC Neutral Ground Current Alarm (via Salem Control Room)
AB.BOP-0004, Grid Disturbances
-
ALL Aux. Boilers TRIPPED AND Outside Ambient Air Temperature > 40°F
AB.MISC-0003, Loss of Auxiliary Steam
-
2 SCP’s Tripped/Stopped
AB.RPV-0004, Reactor Level Control
-
Recirc Pump Vibration Alarm
AB.RPV-0003, Recirculation System/Power Oscillations
-
Suspected breach of Secondary Containment
AB.CONT-0003, Reactor Building
-
Instrument Air Header pressure is <=70 psig
AB.COMP-0001, Instrument and/or Service Air
-
SRV’s CANNOT be opened using the control switches in the MCR, LRR, OR RSP
AB.RPV-0006, Safety / Relief Valve
-
Lowering Fuel Pool level
AB.COOL-0004, Fuel Pool Cooling
-
Cold Water Transient
AB.RPV-0001, Reactor Power
-
Instrument Air Header Pressure is <=85 psig.
AB.COMP-0001, Instrument and/or Service Air
-
North Plant Vent Activity Rising
AB.CONT-0004, Radioactive Gaseous Release
-
Instrument Gas Pressure Lowering.
AB.COMP-0002, Primary Containment Instrument Gas
-
Explosion or Fire in the Offgas System,OR in any of the following Offgas System equipment rooms: 3159-1, 3160-2, 3155, 3167, 3168, 3181, OR 3182
AB.BOP-0006, Main Condenser Vacuum
-
RACS Room Flooded AND Multiple Station Service Water Isolations
AB.COOL-0003, Reactor Auxiliary Cooling
-
RPIS Malfunction
AB.IC-0001, Control Rod
-
Any Recirc Pump Seal Cavity temperature >160F OR Indication of an adverse trend
AB.RPV-0003, Recirculation System/Power Oscillations
-
Suspected Jet Pump Failure
AB.RPV-0003, Recirculation System/Power Oscillations
-
>5°F Lowering of any 3-Stage SRV 1st Stage (Pilot) Temperature
AB.RPV-0006, Safety / Relief Valve
-
Multiple seal failure of a Recirculation Pump
AB.RPV-0003, Recirculation System/Power Oscillations
-
DLD EQPT DRN FLOW >=5.0 gpm or a sustained change >1.0 gpm in a 24 hr. period. OR DLD FLOOR DRN FLOW >=0.75 gpm or a sustained change >0.15 gpm in a 24 hr. period OR ANY Recirc Pump Seal CRIDS point in alarm
AB.CONT-0006, Drywell Leakage
-
Delaware River level IS anticipated to reach 99.5’
AB.MISC-0001, Acts of Nature
-
Main Condenser Waterbox Isolation Required
AB.RPV-0007, Reactor Coolant Conductivity
-
Restore Offsite Power to a 1E 4kV Vital Bus
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
SRM / IRM Malfunction
AB.IC-0004, Neutron Monitoring
-
Loss of instrumentation and/or control of 1E Systems of the same channel/division
AB.ZZ-0136, Loss of 120 VAC Inverter
-
Sequencer Failure
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Feed Pump Trip
AB.RPV-0004, Reactor Level Control
-
Degrading Condenser Vacuum
AB.BOP-0006, Main Condenser Vacuum
-
LOP with concurrent loss of EDG B
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
A Fire is burning near a Transmission Line that MAY pose a FUTURE threat to a line.
AB.BOP-0004, Grid Disturbances
-
Evacuation of the Control Room is required
AB.HVAC-0002, Control Room Environment
-
Generator H2 pressure drops below 63 psig.
AB.BOP-0002, Main Turbine
-
Loss of 10D485 INVERTER
AB.ZZ-0136, Loss of 120 VAC Inverter
-
Valid Containment Isolation Signal
AB.CONT-0002, Primary Containment
-
RACS Pump has tripped
AB.COOL-0003, Reactor Auxiliary Cooling
-
TIP detector retracts past the in-shield limit.
AB.IC-0004, Neutron Monitoring
-
S/U Valve Single Element Control Failure (S/U VLV CTRLR in “A” Auto.)
AB.RPV-0004, Reactor Level Control
-
Float Trap Malfunction
AB.BOP-0002, Main Turbine
-
Valid Main Steam Line Radiation Levels >1.5X Normal
AB.RPV-0008, Reactor Coolant Activity
-
Rising Condensate Conductivity Trend
AB.RPV-0007, Reactor Coolant Conductivity
-
One EHC Pressure Transmitter fails
AB.RPV-0005, Reactor Pressure
-
Inadvertent SLC Initiation
AB.RPV-0001, Reactor Power
-
Recirculation Pump Runback OR Emergency Power Reduction
AB.RPV-0001, Reactor Power
-
Loss of inventory with excessive Drywell Equipment/Floor Drain sump runs
AB.COOL-0004, Fuel Pool Cooling
-
South Plant Vent Activity Rising
AB.CONT-0004, Radioactive Gaseous Release
-
SDV Vent and Drain Valves CLOSED
AB.IC-0002, Scram Discharge Volume
-
Hydrogen Seal Oil System Malfunction during LOP
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
EDG Running Without Cooling
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
A Fire is burning near a Transmission Line that poses an IMMEDIATE threat to the line.
AB.BOP-0004, Grid Disturbances
-
Single Reactor Recirc Pump Tripped
AB.RPV-0003, Recirculation System/Power Oscillations
-
500 kV Switchyard Voltage falls below 493 kV OR Predicted event may result in Switchyard Voltage falling below 493 kV.
AB.BOP-0004, Grid Disturbances
-
Damaged irradiated fuel is in the Spent Fuel Pool, OR Reactor Cavity OR Cask Loading Pit
AB.CONT-0005, Irradiated Fuel Damage
-
SRV is OPEN
AB.RPV-0006, Safety / Relief Valve
-
Loss of S/D Cooling AND RCS temp. < 200degF AND RCS temp. is anticipated to reach >= 200degF
AB.RPV-0009, Shutdown Cooling
-
Emergency Makeup from Service Water to the 'B' SACS loop is required
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
One SACS subsystem is inoperable
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
RPS Channel Trip
AB.IC-0003, Reactor Protection System
-
RHR S/D Cooling CANNOT be established within 1 hour
AB.RPV-0009, Shutdown Cooling
-
Steam Tunnel Damper Isolation Signal AND No indications of a High Energy Line Break
AB.BOP-0005, Main Steam Tunnel Temperature
-
Various multiple system alarms. OR Alarms, 120 VAC UPS TROUBLE* D3-E3, * Except for loss of 1BD483 which supplies power to the overhead annunciators. A loss of 1BD483 results in a loss of all overhead annunciators. * Loss of A/B/C/D 482 Inverters does not result in 120VAC Trouble due to loss of Bailey logic to drive alarm.
AB.ZZ-0136, Loss of 120 VAC Inverter
-
Leak in the Reactor Building (00C188 I-1 in alarm)
AB.COMP-0001, Instrument and/or Service Air
-
Lowering Expansion Tank level
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
Reactor Building penetration does not meet Normal Isolation Provisions of Attachment 2
AB.CONT-0003, Reactor Building
-
Delaware River level is expected to reach 96 feet, OR notification of a Dam Failure OR Tsunami
AB.MISC-0001, Acts of Nature
-
Loss of Fuel Pool Heat Removal Capability
AB.COOL-0004, Fuel Pool Cooling
-
TACS Receives Auto Swap Signal
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
RBVS CANNOT maintain a NEGATIVE Reactor BuildingReactor Building d/p of at least < -0.30 inches WG
AB.CONT-0003, Reactor Building
-
Trip of SACS pump in the Standby Loop
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
Loss of SFSC Heat Removal System as indicated by visual observation of vent blockage
AB.MISC-0004, ISFSI- Spent Fuel Storage Cask (SFSC) Heat Removal System
-
Delaware River level >= 96’
AB.MISC-0001, Acts of Nature
-
RWCU is required for Alternate Decay Heat Removal
AB.RPV-0009, Shutdown Cooling
-
Restoration of Offsite Power via T3
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Degraded FPCC cannot handle Pool Heat Load
AB.COOL-0004, Fuel Pool Cooling
-
Restoration of 1E 4KV bus 10A402 via AOT Diesels
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Stuck Control Rod Not at notch “00”
AB.IC-0001, Control Rod
-
Valid high drywell pressure condition (Drywell Pressure >= 1.68 psig)
AB.CONT-0006, Drywell Leakage
-
Outside temperature <= 32°F
AB.MISC-0001, Acts of Nature
-
Loss of inventory with rising SACS head tank level
AB.COOL-0004, Fuel Pool Cooling
-
Loss of 1 (A-D) D482 INVERTER
AB.ZZ-0136, Loss of 120 VAC Inverter
-
A Severe Thunder Storm, High winds OR Tornado Warning has been issued for the area
AB.MISC-0001, Acts of Nature
-
Irradiated Fuel Damage
AB.CONT-0005, Irradiated Fuel Damage
-
RACS is lost to BOTH Reactor Recirculation Pumps
AB.COOL-0003, Reactor Auxiliary Cooling
-
Damaged irradiated fuel is attached to the fuel handling grapple
AB.CONT-0005, Irradiated Fuel Damage
-
Unexpected rise in Drywell Pressure
AB.CONT-0001, Primary Containment
-
LOP with concurrent loss of EDG C
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Smoke OR Toxic Gases are detected in the Control Room air supply
AB.HVAC-0002, Control Room Environment
-
Unplanned loss of Feedwater Heating from a SINGLE #3/4/5 Feedwater Heater
AB.BOP-0001, Feedwater Heating
-
Inadvertent C Channel Isolation.
AB.COMP-0002, Primary Containment Instrument Gas
-
CREF has started due to High Radiation in the Outside Air supply
AB.HVAC-0002, Control Room Environment
-
Unplanned Loss of Feedwater Heating from #3/4/5 Feedwater Heater String (same train) AND Tube Leak is Suspected
AB.BOP-0001, Feedwater Heating
-
Suspected condenser in leakage
AB.BOP-0006, Main Condenser Vacuum
-
DLD FLR DRN FLOW >=5.0 gpm
AB.CONT-0006, Drywell Leakage
-
3 SCP’s Tripped
AB.RPV-0004, Reactor Level Control
-
Reactor Coolant Conductivity EXCEEDS 5 µS/cm.
AB.RPV-0007, Reactor Coolant Conductivity
-
Sustained South / Southeast High Winds (>= 40 mph) WITH LITTLE or NO rain for >= 8 Hours
AB.MISC-0001, Acts of Nature
-
ALL Aux. Boilers TRIPPED WITH Auxiliary Steam supplying Sealing Steam.
AB.MISC-0003, Loss of Auxiliary Steam
-
Loss of inventory with rising RACS head tank level
AB.COOL-0004, Fuel Pool Cooling
-
LOP with concurrent loss of EDG A
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
Instrument Gas Pressure >= 110 psig
AB.COMP-0002, Primary Containment Instrument Gas
-
A Hurricane OR Tropical Storm watch is issued for the area
AB.MISC-0001, Acts of Nature
-
Reactor Recirc Pump Seal Degradation is detected.
AB.RPV-0003, Recirculation System/Power Oscillations
-
Restoration of 1E 4KV bus 10A401 via AOT Diesels
AB.ZZ-0135, Station Blackout / Loss of Offsite Power / Diesel Generator Malfunction
-
One of three pressure control modules/processors (《R》,《S》, or 《T》) within the P1 TMR controller is Off-Line OR two Pressure Transmitters fail.
AB.RPV-0005, Reactor Pressure
-
POST LOCA AND PCIG Compressor Safety Lockout requires resetting
AB.COMP-0002, Primary Containment Instrument Gas
-
River Water Temperature is > 89°F
AB.COOL-0001, Station Service Water
-
Pressure Control Valve (PCV-3096) Malfunction
AB.BOP-0002, Main Turbine
-
RMCS Display INOP
AB.IC-0001, Control Rod
-
1 PCP Tripped
AB.RPV-0004, Reactor Level Control
-
Recirculation Flow cannot be Restored AND There is potential for vessel Thermal Stratification AND HPCI, RCIC, and Feedwater are not needed for RPV level or pressure control
AB.RPV-0003, Recirculation System/Power Oscillations
-
Loss of inventory with rising TORUS level
AB.COOL-0004, Fuel Pool Cooling
-
Loss of inventory with rising SACS head tank level
AB.COOL-0005, Total Loss of Station Service Water
-
Confirmed FIRE in the Lower Cable Spreading Room, LRR, Lower Control Equipment Room or MCR requires evacuation of the Control Room
AB.HVAC-0002, Control Room Environment
-
Recirc Pump VFD Cell Fault/Bypass
AB.RPV-0003, Recirculation System/Power Oscillations
-
S/U Valve Fails OPEN
AB.RPV-0004, Reactor Level Control
-
DLD EQPT DRN FLOW > 6.00 gpm or a sustained change > 2.0 gpm in a 24 hour period. OR DLD FLR DRN FLOW > 1.5 gpm or a sustained change > 0.225 gpm in a 24 hour period
AB.CONT-0006, Drywell Leakage
-
Unplanned entry resulting in Reactor Power >= 26.130% AND Core Flow <= 68%.
AB.RPV-0003, Recirculation System/Power Oscillations
-
Reactor is Sub-Critical AND No Recirc. Pumps running
AB.RPV-0003, Recirculation System/Power Oscillations
-
Loss of Normal power to RPS Bus
AB.IC-0003, Reactor Protection System
-
Loss of Overhead Annunciators
AB.MISC-0002, CRIDS / Overhead Annunciators
-
Reactor Building backdraft damper isolates AND No High Energy line break exists
AB.CONT-0003, Reactor Building
-
SACS is operating with a Single pump in BOTH loops during a LOP
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
-
Instrument Air Pressure Lowering
AB.COMP-0001, Instrument and/or Service Air
-
Loss of AVH-408 AND BVH-408
AB.HVAC-0001, HVAC
-
Failure of the Main Generator Automatic Voltage Regulator.
AB.BOP-0004, Grid Disturbances
-
Loss of inventory with Rising CST level
AB.COOL-0005, Total Loss of Station Service Water
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Any SRV OPEN, AND Suppression Chamber Average Water Temperature ³177°F,AND Reactor Pressure >100 psig
AB.RPV-0006, Safety / Relief Valve
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SSW fouling due to oil spill in river (as evidenced by Tar/Oil Clumping on SSW Screens).
AB.COOL-0001, Station Service Water
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Loss of A(B,C or D)VH-401
AB.HVAC-0001, HVAC
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Inadvertent RCIC Initiation
AB.RPV-0001, Reactor Power
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Low Level in the Head Tank
AB.COOL-0003, Reactor Auxiliary Cooling
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Service Air Compressor Tripped OR Failed to Start AND Required to be placed in-service
AB.COMP-0001, Instrument and/or Service Air
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Loss of inventory with rising TORUS level
AB.COOL-0005, Total Loss of Station Service Water
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Lowering Fuel Pool level
AB.COOL-0005, Total Loss of Station Service Water
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Stator Cooling High Conductivity
AB.BOP-0002, Main Turbine
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SWIS HVAC Malfunction
AB.HVAC-0001, HVAC
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ALL Aux. Boilers TRIPPED AND Outside Ambient Air Temperature £ 40°F, OR Ambient Temperatures reach / are projected to reach 35°F during the shift and an Auxiliary Boiler CANNOT be started
AB.MISC-0003, Loss of Auxiliary Steam
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Delaware River level > 99.5’
AB.MISC-0001, Acts of Nature
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EHC Hydraulic Pressure Low
AB.BOP-0003, Turbine Hydraulic Pressure
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Intersystem leakage into either SACS loop as indicated by Expansion Tank high level alarm OR RM11 Liquid Process Monitor alarm due to high activity.
AB.COOL-0002, Safety/Turbine Auxiliaries Cooling System
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Indication of Major Fuel Failure. (Post LOCA)
AB.CONT-0001, Primary Containment
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Circulating Water temperature high
AB.BOP-0006, Main Condenser Vacuum
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RPV level >= 90 inches
AB.RPV-0004, Reactor Level Control
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Malfunction Results in Inadvertent Rod Motion
AB.IC-0001, Control Rod
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Inadvertent A Channel Isolation.
AB.COMP-0002, Primary Containment Instrument Gas
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River Water Temperature is expected to exceed 85°F
AB.COOL-0001, Station Service Water
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RWM Malfunction
AB.IC-0001, Control Rod
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Unplanned Loss of Feedwater Heating from #6 Feedwater Heater
AB.BOP-0001, Feedwater Heating
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Excessive EHC Pump Current >60 amps
AB.BOP-0003, Turbine Hydraulic Pressure
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Inadvertent B Channel Isolation.
AB.COMP-0002, Primary Containment Instrument Gas
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Loss of instrument air to a component
AB.COMP-0001, Instrument and/or Service Air
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Unplanned loss of Feedwater Heating from MULTIPLE #3/4/5 Feedwater Heaters in different trains
AB.BOP-0001, Feedwater Heating
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