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SALEM

⌂ Home ◇ Plant overview

4KV 13KV 115V AC 460/230V AC 500KV ABV AFW AMSAC Annunciators CAV CCW CFCUs Chill Water Circ Water Condenser Air Removal Containment Containment Spray Control Air Control Rod Drive CVCS DC Power Demin Water ECCS EDGs ESF & Design Excore NIs Feed & Condensate FHV Fire Protection Incores Main Steam Main Turbine MTLO Pressurizer & PRT Pressurizer Level & Press Control Radiation Monitoring RCPs RCS Refueling RHR RPS/SSPS RVLIS Rx Vessel & Internals SECs Service Water SPAV Spent Fuel Pool Stator Cooling Water Steam Dumps Steam Generator & Blowdown TAC TGA Ventilation Waste Gas Waste Liquid

Technical Specifications Overview TS 1.0 — Definitions TS 2.0 — Safety Limits and LSSS TS 3/4.0 — Applicability TS 3/4.1.1 — Boration Control TS 3/4.1.2 — Boration Systems TS 3/4.1.3 — Movable Control Assemblies TS 3/4.2 — Power Distribution TS 3/4.3 — Instrumentation TS 3/4.4 — Reactor Coolant System TS 3/4.5 — ECCS TS 3/4.6 — Containment TS 3/4.7 — Plant Systems TS 3/4.8 — Electrical TS 3/4.9 — Refueling Operations TS 3/4.10 — Special Test Exceptions TS 3/4.11 — Radioactive Effluents TS 6.0 — Administrative Controls

2018 NRC Operating Exam 2018 NRC Written Exam 2019 NRC Operating Exam 2019 NRC Written Exam 2020 NRC Operating Exam 2020 NRC Written Exam 2022 NRC Operating Exam 2022 NRC Written Exam 2023 NRC Operating Exam 2023 NRC Written Exam

EOP-APPX-1 — Component Cooling Water Restoration EOP-APPX-7 — Containment Sump Blockage EOP-CFST-1 — Critical Safety Function Status Trees EOP-FRCC-1 — Response to Inadequate Core Cooling EOP-FRCC-2 — Response to Degraded Core Cooling EOP-FRCE-1 — Response to Excessive Containment Pressure EOP-FRCE-2 — Response to Containment Flooding EOP-FRCE-3 — Response to High Containment Radiation Levels EOP-FRCI-3 — Response to Void in Reactor Vessel EOP-FRHS-1 — Response to Loss of Secondary Heat Sink EOP-FRHS-2 — Response to Steam Generator Overpressure EOP-FRSM-1 — Response to Nuclear Power Generation EOP-FRTS-1 — Response to Imminent Pressurized Thermal Shock EOP-LOCA-1 — Loss of Reactor or Secondary Coolant EOP-LOCA-2 — Post LOCA Cooldown and Depressurization EOP-LOCA-3 — Transfer to Cold Leg Recirculation EOP-LOCA-4 — Transfer to Hot Leg Recirculation EOP-LOCA-5 — Loss of Emergency Coolant Recirculation EOP-LOCA-6 — LOCA Outside Containment EOP-LOPA-1 — Loss of All AC Power EOP-LOPA-4 — Extended Loss of All AC Power EOP-LOSC-1 — Loss of Secondary Coolant EOP-LOSC-2 — Uncontrolled Depressurization of All Steam Generators EOP-SGTR-1 — Steam Generator Tube Rupture EOP-SGTR-2 — Post SGTR Cooldown EOP-SGTR-3 — SGTR with LOCA Subcooled Recovery EOP-SGTR-4 — SGTR with LOCA Saturated Recovery EOP-TRIP-1 — Reactor Trip or Safety Injection EOP-TRIP-2 — Reactor Trip Response EOP-TRIP-3 — SI Termination EOP-TRIP-4 — Natural Circulation EOP-TRIP-5 — Natural Circulation Cooldown With RVLIS EOP-TRIP-6 — Natural Circulation Cooldown Without RVLIS EOP-TRIP-7 — Rediagnosis

AD-AA-101-101 — OTSC Process CC-AA-112 — Temporary Configuration Changes EP-SA-111 — Emergency Classification and Protective Action EP-SA-111-101 — Emergency Classification and ICMF EP-SA-325 — Emergency Plan Implementing Procedures FP-AA-012 — Fire Brigade Staffing HU-AA-101 — Human Performance Tools and Verification Practices LS-AA-119-1003 — Calculating Work Hours MA-AA-716-004 — Conduct of Troubleshooting NC.EP-EP.ZZ-0102 — Emergency Coordinator Response NC.EP-EP.ZZ-0304 — OSC Radiation Protection Response OP-AA-101-111 — Roles and Responsibilities of On-Shift Personnel OP-AA-101-111-1003 — Use of Procedures OP-AA-102-103-1001 — Operator Burdens Program OP-AA-102-104 — Pertinent Information Program OP-AA-104-101 — Communications OP-AA-105-101 — Administrative Process for NRC License and Medical Requirements OP-AA-105-102 — NRC Active License Maintenance OP-AA-108-101-1001 — Equipment Lineup Verification OP-AA-108-101-1002 — Independent/Concurrent Verification OP-AA-108-107-1001 — Electric System Emergency Operations OP-AA-108-107-1002 — Salem and Hope Creek 500 KV Switchyard Operations Interface OP-AA-108-110 — Evaluation of Special Tests or Evolutions OP-AA-108-116 — Protected Equipment Program OP-AA-109-115 — Equipment Tagging OP-AA-112-101 — Shift Turnover and Relief OP-AA-300 — Reactivity Management OP-AP-300-1001 — PWR Control Rod Movement Requirements OP-SA-108-101-2000 — Emergency/Abnormal Operating Procedure Program OP-SA-108-106-1001 — Equipment Control and Large Motor Starting Criteria RP-AA-203 — Exposure Control and Authorization RP-AA-300 — Radiological Survey Program RP-AA-460 — Controls for High and Very High Radiation Areas RP-AA-463 — High Radiation Area Key Controls RP-AA-4000 — Personnel Conduct in Radiologically Controlled Areas RP-SA-102 — Containment Entries at Power S2.OP-IO.ZZ-0007 — Cold Shutdown to Refueling S2.OP-ST.CVC-0010 — Borated Water Sources S2.OP-ST.NIS-0001 — Power Distribution AFD Surveillance S2.OP-ST.NIS-0002 — Power Distribution QPTR Surveillance S2.OP-TM.ZZ-0002 — Tank Capacity Data SA-AA-111 — Heat Stress Control SA-AA-114 — Confined Space Program SC.RE-ST.ZZ-0002 — Shutdown Margin Calculation SECG — Reportable Action Levels (RAL) SY-AA-102-201 — Fitness for Duty WC-AA-101 — On-Line Work Management Process

AB.4KV-0001 — Loss of 4KV Vital Bus AB.4KV-0002 — Loss of 2B 4KV Vital Bus AB.4KV-0003 — Loss of 2C 4KV Bus AB.115-0001 — Loss of 115V Vital Instrument Bus AB.115-0002 — Loss of 2B 115V Vital Instrument Bus AB.460-0001 — Loss of 2A 460V Bus AB.CA-0001 — Loss of Control Air AB.CC-0001 — Loss of Component Cooling Water AB.CHEM-0001 — Secondary Chemistry Abnormality AB.CN-0001 — Condensate System Abnormality AB.COND-0001 — Loss of Condenser Vacuum AB.CONT-0001 — Containment Closure AB.CR-0001 — Control Room Evacuation AB.CVC-0001 — Loss of Charging AB.CW-0001 — Circulating Water Malfunction AB.FIRE-0001 — Control Room Fire Response AB.FP-0001 — Fire Protection System Malfunction AB.FUEL-0001 — Fuel Handling Incident AB.FUEL-0002 — Loss of Refueling Cavity or SFP Level AB.GRID-0001 — Grid Disturbance AB.LOAD-0001 — Rapid Load Reduction AB.LOCA-0001 — Shutdown LOCA AB.LOOP-0001 — Loss of All Offsite Power AB.LOOP-0003 — Partial Loss of Offsite Power AB.NIS-0001 — Nuclear Instrumentation System Malfunction AB.PZR-0001 — Pressurizer Pressure Control Malfunction AB.RAD-0001 — Radiation Monitor Abnormality AB.RC-0001 — Reactor Coolant System Leak AB.RC-0002 — High Activity in the RCS AB.RC-0004 — Natural Circulation AB.RCP-0001 — RCP Abnormality AB.RHR-0001 — Loss of RHR AB.RHR-0002 — Loss of RHR at Reduced Inventory AB.ROD-0001 — Immovable/Misaligned Control Rods AB.ROD-0002 — Dropped Rod AB.ROD-0003 — Continuous Rod Motion AB.SF-0001 — Loss of Spent Fuel Pool Cooling AB.SG-0001 — Steam Generator Tube Leak AB.SSP-0001 — Station Shutdown Power AB.STM-0001 — Excessive Steam Flow AB.SW-0001 — Loss of SW Header Pressure AB.SW-0003 — Service Water Bay Leak AB.SW-0004 — Loss of SW During SW Header Outage AB.SW-0005 — Loss of All Service Water AB.TRB-0001 — Main Turbine Abnormality

S1.OP-PT.CA-0001 — Emergency Control Air Compressor Test S1.OP-SO.CAV-0001 — Control Room Ventilation Operation S1.OP-SO.DG-0005 — EDG Operability Determination S1.OP-SO.RCS-0001 — Rod Control System Operation S1.OP-SO.SF-0001 — Fill and Transfer of Spent Fuel Pool S1.OP-SO.WG-0005 — VCT Purge to the Plant Vent S1.OP-SO.WG-0010 — Discharge of 13 Gas Decay Tank to Plant Vent S1.OP-SO.WG-0011 — Discharge of 14 Gas Decay Tank S1.OP-SO.WL-0001 — Release of Radioactive Liquid Waste S1.OP-SO.WL-0002 — Release of Radioactive Liquid Waste (Unit 1 CCHX Path) S1.OP-ST.RM-0001 — Radiation Monitors Check Source S2-RE-RA.ZZ-0016 — Curve Book (Salem Unit 2 Cycle 23) S2.OP-AR.DG-0001 — EDG Alarm Response S2.OP-AR.ZZ-0001 — Overhead Annunciators Window A S2.OP-AR.ZZ-0002 — Overhead Annunciators Window B S2.OP-AR.ZZ-0004 — Alarm Response Procedure S2.OP-AR.ZZ-0005 — Overhead Annunciators Window E S2.OP-AR.ZZ-0008 — Overhead Annunciators Window H S2.OP-AR.ZZ-0009 — Overhead Annunciators Window J S2.OP-AR.ZZ-0011 — Alarm Response (2CC1) S2.OP-AR.ZZ-0012 — Console Alarm Response S2.OP-DL.ZZ-0003 — Control Room Logs S2.OP-IO.ZZ-0002 — Cold Shutdown to Hot Standby S2.OP-IO.ZZ-0003 — Hot Standby to Minimum Load S2.OP-IO.ZZ-0004 — Power Operation S2.OP-IO.ZZ-0006 — Hot Standby to Cold Shutdown S2.OP-IO.ZZ-0010 — Spent Fuel Pool Manipulations S2.OP-PT.AF-0002 — AFW Backleakage Testing S2.OP-PT.TRB-0003 — Main Turbine Valve Stroke Testing S2.OP-SO.4KV-0008 — 4KV Group Buses Power Supply Transfer S2.OP-SO.125-0004 — 125VDC Ground Detection S2.OP-SO.AR-0001 — Condenser Air Removal System Operation S2.OP-SO.CAN-0001 — Hydrogen Recombiner Operation S2.OP-SO.CBV-0001 — Containment Ventilation Operation S2.OP-SO.CBV-0002 — Containment Pressure Vacuum Relief System Operation S2.OP-SO.CH-0001 — Chilled Water System Operation S2.OP-SO.CN-0002 — Steam Generator Feed Pump Operation S2.OP-SO.CVC-0001 — CVCS Normal Operations S2.OP-SO.CVC-0003 — Excess Letdown Flow S2.OP-SO.CVC-0006 — Boron Concentration Control S2.OP-SO.CVC-0008 — Rapid Boration S2.OP-SO.CVC-0012 — Letdown HX Temperature Control S2.OP-SO.MS-0001 — Main Steam Warmup S2.OP-SO.PZR-0003 — PRT Operation S2.OP-SO.PZR-0010 — Pressurizer Backup Heaters Power Supply Transfer S2.OP-SO.RC-0001 — Reactor Coolant Pump Operation S2.OP-SO.RC-0002 — Vacuum Refill of the RCS S2.OP-SO.RHR-0001 — Initiating RHR S2.OP-SO.RM-0001 — Radiation Monitoring System Operation S2.OP-SO.RPS-0001 — Nuclear Instrumentation Channel Trip / Restoration S2.OP-SO.RPS-0005 — RPS Surveillance S2.OP-SO.SF-0001 — Fill and Transfer of Spent Fuel Pool S2.OP-SO.SF-0006 — Spent Fuel Pool Emergency Fill S2.OP-SO.SJ-0002 — Accumulator Operations S2.OP-SO.SW-0005 — Service Water System Operation S2.OP-SO.TRB-0001 — Turbine-Generator Startup Operations S2.OP-SO.WG-0006 — Containment Purge to Plant Vent S2.OP-SO.WG-0008 — 21 Gas Decay Tank to Plant Vent S2.OP-SO.WG-0009 — Discharge of 22 Gas Decay Tank to Plant Vent S2.OP-SO.WG-0011 — Discharge of 24 Gas Decay Tank to Plant Vent S2.OP-SO.WL-0001 — Release of Radioactive Liquid Waste S2.OP-ST.CBV-0001 — Inservice Testing Containment Ventilation Valves S2.OP-ST.CBV-0003 — Containment Cooling Systems Surveillance S2.OP-ST.DG-0001 — Emergency Diesel Generator Surveillance Test S2.OP-ST.RCS-0001 — Rod Control Assemblies Surveillance SC.OP-SO.CA-0001 — SBO Diesel Control Air Compressor SC.RE-ST.ZZ-0002 — Shutdown Margin Calculation

SALEM STUDY SYSTEM

⌂ Home ◇ Plant overview

4KV 13KV 115V AC 460/230V AC 500KV ABV AFW AMSAC Annunciators CAV CCW CFCUs Chill Water Circ Water Condenser Air Removal Containment Containment Spray Control Air Control Rod Drive CVCS DC Power Demin Water ECCS EDGs ESF & Design Excore NIs Feed & Condensate FHV Fire Protection Incores Main Steam Main Turbine MTLO Pressurizer & PRT Pressurizer Level & Press Control Radiation Monitoring RCPs RCS Refueling RHR RPS/SSPS RVLIS Rx Vessel & Internals SECs Service Water SPAV Spent Fuel Pool Stator Cooling Water Steam Dumps Steam Generator & Blowdown TAC TGA Ventilation Waste Gas Waste Liquid

Technical Specifications Overview TS 1.0 — Definitions TS 2.0 — Safety Limits and LSSS TS 3/4.0 — Applicability TS 3/4.1.1 — Boration Control TS 3/4.1.2 — Boration Systems TS 3/4.1.3 — Movable Control Assemblies TS 3/4.2 — Power Distribution TS 3/4.3 — Instrumentation TS 3/4.4 — Reactor Coolant System TS 3/4.5 — ECCS TS 3/4.6 — Containment TS 3/4.7 — Plant Systems TS 3/4.8 — Electrical TS 3/4.9 — Refueling Operations TS 3/4.10 — Special Test Exceptions TS 3/4.11 — Radioactive Effluents TS 6.0 — Administrative Controls

2018 NRC Operating Exam 2018 NRC Written Exam 2019 NRC Operating Exam 2019 NRC Written Exam 2020 NRC Operating Exam 2020 NRC Written Exam 2022 NRC Operating Exam 2022 NRC Written Exam 2023 NRC Operating Exam 2023 NRC Written Exam

EOP-APPX-1 — Component Cooling Water Restoration EOP-APPX-7 — Containment Sump Blockage EOP-CFST-1 — Critical Safety Function Status Trees EOP-FRCC-1 — Response to Inadequate Core Cooling EOP-FRCC-2 — Response to Degraded Core Cooling EOP-FRCE-1 — Response to Excessive Containment Pressure EOP-FRCE-2 — Response to Containment Flooding EOP-FRCE-3 — Response to High Containment Radiation Levels EOP-FRCI-3 — Response to Void in Reactor Vessel EOP-FRHS-1 — Response to Loss of Secondary Heat Sink EOP-FRHS-2 — Response to Steam Generator Overpressure EOP-FRSM-1 — Response to Nuclear Power Generation EOP-FRTS-1 — Response to Imminent Pressurized Thermal Shock EOP-LOCA-1 — Loss of Reactor or Secondary Coolant EOP-LOCA-2 — Post LOCA Cooldown and Depressurization EOP-LOCA-3 — Transfer to Cold Leg Recirculation EOP-LOCA-4 — Transfer to Hot Leg Recirculation EOP-LOCA-5 — Loss of Emergency Coolant Recirculation EOP-LOCA-6 — LOCA Outside Containment EOP-LOPA-1 — Loss of All AC Power EOP-LOPA-4 — Extended Loss of All AC Power EOP-LOSC-1 — Loss of Secondary Coolant EOP-LOSC-2 — Uncontrolled Depressurization of All Steam Generators EOP-SGTR-1 — Steam Generator Tube Rupture EOP-SGTR-2 — Post SGTR Cooldown EOP-SGTR-3 — SGTR with LOCA Subcooled Recovery EOP-SGTR-4 — SGTR with LOCA Saturated Recovery EOP-TRIP-1 — Reactor Trip or Safety Injection EOP-TRIP-2 — Reactor Trip Response EOP-TRIP-3 — SI Termination EOP-TRIP-4 — Natural Circulation EOP-TRIP-5 — Natural Circulation Cooldown With RVLIS EOP-TRIP-6 — Natural Circulation Cooldown Without RVLIS EOP-TRIP-7 — Rediagnosis

AD-AA-101-101 — OTSC Process CC-AA-112 — Temporary Configuration Changes EP-SA-111 — Emergency Classification and Protective Action EP-SA-111-101 — Emergency Classification and ICMF EP-SA-325 — Emergency Plan Implementing Procedures FP-AA-012 — Fire Brigade Staffing HU-AA-101 — Human Performance Tools and Verification Practices LS-AA-119-1003 — Calculating Work Hours MA-AA-716-004 — Conduct of Troubleshooting NC.EP-EP.ZZ-0102 — Emergency Coordinator Response NC.EP-EP.ZZ-0304 — OSC Radiation Protection Response OP-AA-101-111 — Roles and Responsibilities of On-Shift Personnel OP-AA-101-111-1003 — Use of Procedures OP-AA-102-103-1001 — Operator Burdens Program OP-AA-102-104 — Pertinent Information Program OP-AA-104-101 — Communications OP-AA-105-101 — Administrative Process for NRC License and Medical Requirements OP-AA-105-102 — NRC Active License Maintenance OP-AA-108-101-1001 — Equipment Lineup Verification OP-AA-108-101-1002 — Independent/Concurrent Verification OP-AA-108-107-1001 — Electric System Emergency Operations OP-AA-108-107-1002 — Salem and Hope Creek 500 KV Switchyard Operations Interface OP-AA-108-110 — Evaluation of Special Tests or Evolutions OP-AA-108-116 — Protected Equipment Program OP-AA-109-115 — Equipment Tagging OP-AA-112-101 — Shift Turnover and Relief OP-AA-300 — Reactivity Management OP-AP-300-1001 — PWR Control Rod Movement Requirements OP-SA-108-101-2000 — Emergency/Abnormal Operating Procedure Program OP-SA-108-106-1001 — Equipment Control and Large Motor Starting Criteria RP-AA-203 — Exposure Control and Authorization RP-AA-300 — Radiological Survey Program RP-AA-460 — Controls for High and Very High Radiation Areas RP-AA-463 — High Radiation Area Key Controls RP-AA-4000 — Personnel Conduct in Radiologically Controlled Areas RP-SA-102 — Containment Entries at Power S2.OP-IO.ZZ-0007 — Cold Shutdown to Refueling S2.OP-ST.CVC-0010 — Borated Water Sources S2.OP-ST.NIS-0001 — Power Distribution AFD Surveillance S2.OP-ST.NIS-0002 — Power Distribution QPTR Surveillance S2.OP-TM.ZZ-0002 — Tank Capacity Data SA-AA-111 — Heat Stress Control SA-AA-114 — Confined Space Program SC.RE-ST.ZZ-0002 — Shutdown Margin Calculation SECG — Reportable Action Levels (RAL) SY-AA-102-201 — Fitness for Duty WC-AA-101 — On-Line Work Management Process

AB.4KV-0001 — Loss of 4KV Vital Bus AB.4KV-0002 — Loss of 2B 4KV Vital Bus AB.4KV-0003 — Loss of 2C 4KV Bus AB.115-0001 — Loss of 115V Vital Instrument Bus AB.115-0002 — Loss of 2B 115V Vital Instrument Bus AB.460-0001 — Loss of 2A 460V Bus AB.CA-0001 — Loss of Control Air AB.CC-0001 — Loss of Component Cooling Water AB.CHEM-0001 — Secondary Chemistry Abnormality AB.CN-0001 — Condensate System Abnormality AB.COND-0001 — Loss of Condenser Vacuum AB.CONT-0001 — Containment Closure AB.CR-0001 — Control Room Evacuation AB.CVC-0001 — Loss of Charging AB.CW-0001 — Circulating Water Malfunction AB.FIRE-0001 — Control Room Fire Response AB.FP-0001 — Fire Protection System Malfunction AB.FUEL-0001 — Fuel Handling Incident AB.FUEL-0002 — Loss of Refueling Cavity or SFP Level AB.GRID-0001 — Grid Disturbance AB.LOAD-0001 — Rapid Load Reduction AB.LOCA-0001 — Shutdown LOCA AB.LOOP-0001 — Loss of All Offsite Power AB.LOOP-0003 — Partial Loss of Offsite Power AB.NIS-0001 — Nuclear Instrumentation System Malfunction AB.PZR-0001 — Pressurizer Pressure Control Malfunction AB.RAD-0001 — Radiation Monitor Abnormality AB.RC-0001 — Reactor Coolant System Leak AB.RC-0002 — High Activity in the RCS AB.RC-0004 — Natural Circulation AB.RCP-0001 — RCP Abnormality AB.RHR-0001 — Loss of RHR AB.RHR-0002 — Loss of RHR at Reduced Inventory AB.ROD-0001 — Immovable/Misaligned Control Rods AB.ROD-0002 — Dropped Rod AB.ROD-0003 — Continuous Rod Motion AB.SF-0001 — Loss of Spent Fuel Pool Cooling AB.SG-0001 — Steam Generator Tube Leak AB.SSP-0001 — Station Shutdown Power AB.STM-0001 — Excessive Steam Flow AB.SW-0001 — Loss of SW Header Pressure AB.SW-0003 — Service Water Bay Leak AB.SW-0004 — Loss of SW During SW Header Outage AB.SW-0005 — Loss of All Service Water AB.TRB-0001 — Main Turbine Abnormality

S1.OP-PT.CA-0001 — Emergency Control Air Compressor Test S1.OP-SO.CAV-0001 — Control Room Ventilation Operation S1.OP-SO.DG-0005 — EDG Operability Determination S1.OP-SO.RCS-0001 — Rod Control System Operation S1.OP-SO.SF-0001 — Fill and Transfer of Spent Fuel Pool S1.OP-SO.WG-0005 — VCT Purge to the Plant Vent S1.OP-SO.WG-0010 — Discharge of 13 Gas Decay Tank to Plant Vent S1.OP-SO.WG-0011 — Discharge of 14 Gas Decay Tank S1.OP-SO.WL-0001 — Release of Radioactive Liquid Waste S1.OP-SO.WL-0002 — Release of Radioactive Liquid Waste (Unit 1 CCHX Path) S1.OP-ST.RM-0001 — Radiation Monitors Check Source S2-RE-RA.ZZ-0016 — Curve Book (Salem Unit 2 Cycle 23) S2.OP-AR.DG-0001 — EDG Alarm Response S2.OP-AR.ZZ-0001 — Overhead Annunciators Window A S2.OP-AR.ZZ-0002 — Overhead Annunciators Window B S2.OP-AR.ZZ-0004 — Alarm Response Procedure S2.OP-AR.ZZ-0005 — Overhead Annunciators Window E S2.OP-AR.ZZ-0008 — Overhead Annunciators Window H S2.OP-AR.ZZ-0009 — Overhead Annunciators Window J S2.OP-AR.ZZ-0011 — Alarm Response (2CC1) S2.OP-AR.ZZ-0012 — Console Alarm Response S2.OP-DL.ZZ-0003 — Control Room Logs S2.OP-IO.ZZ-0002 — Cold Shutdown to Hot Standby S2.OP-IO.ZZ-0003 — Hot Standby to Minimum Load S2.OP-IO.ZZ-0004 — Power Operation S2.OP-IO.ZZ-0006 — Hot Standby to Cold Shutdown S2.OP-IO.ZZ-0010 — Spent Fuel Pool Manipulations S2.OP-PT.AF-0002 — AFW Backleakage Testing S2.OP-PT.TRB-0003 — Main Turbine Valve Stroke Testing S2.OP-SO.4KV-0008 — 4KV Group Buses Power Supply Transfer S2.OP-SO.125-0004 — 125VDC Ground Detection S2.OP-SO.AR-0001 — Condenser Air Removal System Operation S2.OP-SO.CAN-0001 — Hydrogen Recombiner Operation S2.OP-SO.CBV-0001 — Containment Ventilation Operation S2.OP-SO.CBV-0002 — Containment Pressure Vacuum Relief System Operation S2.OP-SO.CH-0001 — Chilled Water System Operation S2.OP-SO.CN-0002 — Steam Generator Feed Pump Operation S2.OP-SO.CVC-0001 — CVCS Normal Operations S2.OP-SO.CVC-0003 — Excess Letdown Flow S2.OP-SO.CVC-0006 — Boron Concentration Control S2.OP-SO.CVC-0008 — Rapid Boration S2.OP-SO.CVC-0012 — Letdown HX Temperature Control S2.OP-SO.MS-0001 — Main Steam Warmup S2.OP-SO.PZR-0003 — PRT Operation S2.OP-SO.PZR-0010 — Pressurizer Backup Heaters Power Supply Transfer S2.OP-SO.RC-0001 — Reactor Coolant Pump Operation S2.OP-SO.RC-0002 — Vacuum Refill of the RCS S2.OP-SO.RHR-0001 — Initiating RHR S2.OP-SO.RM-0001 — Radiation Monitoring System Operation S2.OP-SO.RPS-0001 — Nuclear Instrumentation Channel Trip / Restoration S2.OP-SO.RPS-0005 — RPS Surveillance S2.OP-SO.SF-0001 — Fill and Transfer of Spent Fuel Pool S2.OP-SO.SF-0006 — Spent Fuel Pool Emergency Fill S2.OP-SO.SJ-0002 — Accumulator Operations S2.OP-SO.SW-0005 — Service Water System Operation S2.OP-SO.TRB-0001 — Turbine-Generator Startup Operations S2.OP-SO.WG-0006 — Containment Purge to Plant Vent S2.OP-SO.WG-0008 — 21 Gas Decay Tank to Plant Vent S2.OP-SO.WG-0009 — Discharge of 22 Gas Decay Tank to Plant Vent S2.OP-SO.WG-0011 — Discharge of 24 Gas Decay Tank to Plant Vent S2.OP-SO.WL-0001 — Release of Radioactive Liquid Waste S2.OP-ST.CBV-0001 — Inservice Testing Containment Ventilation Valves S2.OP-ST.CBV-0003 — Containment Cooling Systems Surveillance S2.OP-ST.DG-0001 — Emergency Diesel Generator Surveillance Test S2.OP-ST.RCS-0001 — Rod Control Assemblies Surveillance SC.OP-SO.CA-0001 — SBO Diesel Control Air Compressor SC.RE-ST.ZZ-0002 — Shutdown Margin Calculation

Systems > MTLO

MTLO

⚠️ DRAFT

MTLO

Function

Main turbine lube oil system provides lubrication and cooling for main turbine bearings.

Connections

Related systems: Main Turbine

Connections

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