ML17250A871: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:TABLE OF CONTENTS                                                                                                   Page Number 1.0       USE AND APPLICATION 1.1         Definitions ............................................................................................................1.1-1 1.2         Logical Connectors ..............................................................................................1.2-1 1.3         Completion Times ................................................................................................1.3-1 1.4         Frequency ...........................................................................................................1.4-1 2.0       SAFETY LIMITS (SLs) ..............................................................................................2.0-1 2.1         Safety Limits 2.2         SL Violations 3.0       LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ..........................3.0-1 3.0       SURVEILLANCE REQUIREMENT (SR) APPLICABILITY .........................................3.0-4 3.1           REACTIVITY CONTROL SYSTEMS 3.1.1           SHUTDOWN MARGIN (SDM) ....................................................................3.1.1-1 3.1.2           Reactivity Anomalies ...................................................................................3.1.2-1 3.1.3           Control Rod OPERABILITY ........................................................................3.1.3-1 3.1.4           Control Rod Scram Times ...........................................................................3.1.4-1 3.1.5 3.1.6 3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 ra Control Rod Scram Accumulators ...............................................................3.1.5-1 Rod Pattern Control ....................................................................................3.1.6-1 Standby Liquid Control (SLC) System .........................................................3.1.7-1 ft Scram Discharge Volume (SDV) Vent and Drain Valves .............................3.1.8-1 POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) .............................................................................................3.2.1-1 MINIMUM CRITICAL POWER RATIO (MCPR) ...........................................3.2.2-1 LINEAR HEAT GENERATION RATE (LHGR) (Optional) ............................3.2.3-1 3.3 3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.2 3.3.3.1 3.3.3.2 3.3.4.1 D      INSTRUMENTATION Reactor Protection System (RPS) Instrumentation................................... 3.3.1.1-1 Source Range Monitor (SRM) Instrumentation ......................................... 3.3.1.2-1 Control Rod Block Instrumentation ...........................................................3.3.2.1-1 Feedwater Pump and Main Turbine High Water Level Trip Instrumentation ..................................................................................3.3.2.2-1 Post Accident Monitoring (PAM) Instrumentation ..................................... 3.3.3.1-1 Alternate Shutdown System .....................................................................3.3.3.2-1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation.............................................................3.3.4.1-1 3.3.5.1           Emergency Core Cooling System (ECCS) Instrumentation ...................... 3.3.5.1-1 3.3.5.2           Reactor Core Isolation Cooling (RCIC) System Instrumentation .............. 3.3.5.2-1 3.3.5.3           Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation3.3.5.3-1 3.3.6.1           Primary Containment Isolation Instrumentation ........................................ 3.3.6.1-1 3.3.6.2           Secondary Containment Isolation Instrumentation ................................... 3.3.6.2-1 3.3.6.3           Low-Low Set (LLS) Instrumentation .........................................................3.3.6.3-1 3.3.7.1           Control Room Emergency Filtration (CREF) System Instrumentation ..................................................................................3.3.7.1-1 3.3.7.2           Mechanical Vacuum Pump Isolation Instrumentation ............................... 3.3.7.2-1 Monticello                                                        i                                                    Revision 0
{{#Wiki_filter:Monticello i
Revision 0 TABLE OF CONTENTS Page Number 1.0 USE AND APPLICATION 1.1 Definitions............................................................................................................ 1.1-1 1.2 Logical Connectors.............................................................................................. 1.2-1 1.3 Completion Times................................................................................................ 1.3-1 1.4 Frequency........................................................................................................... 1.4-1 2.0 SAFETY LIMITS (SLs).............................................................................................. 2.0-1 2.1 Safety Limits 2.2 SL Violations 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.......................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY......................................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM).................................................................... 3.1.1-1 3.1.2 Reactivity Anomalies................................................................................... 3.1.2-1 3.1.3 Control Rod OPERABILITY........................................................................ 3.1.3-1 3.1.4 Control Rod Scram Times........................................................................... 3.1.4-1 3.1.5 Control Rod Scram Accumulators............................................................... 3.1.5-1 3.1.6 Rod Pattern Control.................................................................................... 3.1.6-1 3.1.7 Standby Liquid Control (SLC) System......................................................... 3.1.7-1 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves............................. 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)............................................................................................. 3.2.1-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)........................................... 3.2.2-1 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) (Optional)............................ 3.2.3-1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation................................... 3.3.1.1-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation......................................... 3.3.1.2-1 3.3.2.1 Control Rod Block Instrumentation........................................................... 3.3.2.1-1 3.3.2.2 Feedwater Pump and Main Turbine High Water Level Trip Instrumentation.................................................................................. 3.3.2.2-1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation..................................... 3.3.3.1-1 3.3.3.2 Alternate Shutdown System..................................................................... 3.3.3.2-1 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation............................................................. 3.3.4.1-1 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation...................... 3.3.5.1-1 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation.............. 3.3.5.2-1 3.3.5.3 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation3.3.5.3-1 3.3.6.1 Primary Containment Isolation Instrumentation........................................ 3.3.6.1-1 3.3.6.2 Secondary Containment Isolation Instrumentation................................... 3.3.6.2-1 3.3.6.3 Low-Low Set (LLS) Instrumentation......................................................... 3.3.6.3-1 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation.................................................................................. 3.3.7.1-1 3.3.7.2 Mechanical Vacuum Pump Isolation Instrumentation............................... 3.3.7.2-1 Draft


3.3.8.1   Loss of Power (LOP) Instrumentation ......................................................3.3.8.1-1 3.3.8.2   Reactor Protection System (RPS) Electric Power Monitoring ................... 3.3.8.2-1 raft D
3.3.8.1 Loss of Power (LOP) Instrumentation...................................................... 3.3.8.1-1 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring................... 3.3.8.2-1 Draft


TABLE OF CONTENTS                                                                                             Page Number 3.3.8.1           Loss of Power (LOP) Instrumentation ......................................................3.3.8.1-1 3.3.8.2           Reactor Protection System (RPS) Electric Power Monitoring ................... 3.3.8.2-1 TABLE OF CONTENTS                                                                                             Page Number 3.4         REACTOR COOLANT SYSTEM (RCS) 3.4.1         Recirculation Loops Operating ....................................................................3.4.1-1 3.4.2         Jet Pumps ...................................................................................................3.4.2-1 3.4.3         Safety/Relief Valves (S/RVs) ......................................................................3.4.3-1 3.4.4         RCS Operational LEAKAGE .......................................................................3.4.4-1 3.4.5         RCS Leakage Detection Instrumentation ....................................................3.4.5-1 3.4.6         RCS Specific Activity ..................................................................................3.4.6-1 3.4.7         Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..............................................................................................3.4.7-1 3.4.8         Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ..............................................................................................3.4.8-1 3.4.9         RCS Pressure and Temperature (P/T) Limits ..............................................3.4.9-1 3.4.10         Reactor Steam Dome Pressure ................................................................3.4.10-1 3.5         EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY 3.5.1 3.5.2 3.5.3 3.6 3.6.1.1 3.6.1.2 3.6.1.3 ra CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM ECCS - Operating .......................................................................................3.5.1-1 ft RPV Water Inventory ControlECCS - Shutdown .........................................3.5.2-1 RCIC System ..............................................................................................3.5.3-1 CONTAINMENT SYSTEMS Primary Containment ...............................................................................3.6.1.1-1 Primary Containment Air Lock..................................................................3.6.1.2-1 Primary Containment Isolation Valves (PCIVs) ........................................ 3.6.1.3-1 3.6.1.4       Drywell Air Temperature ..........................................................................3.6.1.4-1 3.6.1.5 3.6.1.6 3.6.1.7 3.6.1.8 3.6.2.1 3.6.2.2 3.6.2.3 3.6.3.1 3.6.4.1 D    Low-Low Set (LLS) Valves .......................................................................3.6.1.5-1 Reactor Building-to-Suppression Chamber Vacuum Breakers ................. 3.6.1.6-1 Suppression Chamber-to-Drywell Vacuum Breakers ............................... 3.6.1.7-1 Residual Heat Removal (RHR) Drywell Spray .......................................... 3.6.1.8-1 Suppression Pool Average Temperature .................................................3.6.2.1-1 Suppression Pool Water Level .................................................................3.6.2.2-1 Residual Heat Removal (RHR) Suppression Pool Cooling ....................... 3.6.2.3-1 Primary Containment Oxygen Concentration ........................................... 3.6.3.1-1 Secondary Containment...........................................................................3.6.4.1-1 3.6.4.2       Secondary Containment Isolation Valves (SCIVs).................................... 3.6.4.2-1 3.6.4.3       Standby Gas Treatment (SGT) System....................................................3.6.4.3-1 3.7         PLANT SYSTEMS 3.7.1           Residual Heat Removal Service Water (RHRSW) System ..........................3.7.1-1 3.7.2           Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS) ............................................................................................3.7.2-1 3.7.3           Emergency Diesel Generator Emergency Service Water (EDG-ESW) System ..............................................................................3.7.3-1 3.7.4           Control Room Emergency Filtration (CREF) System...................................3.7.4-1 3.7.5           Control Room Ventilation System ...............................................................3.7.5-1 Monticello                                                    ii                                                Revision 01
Monticello ii Revision 01 TABLE OF CONTENTS Page Number 3.3.8.1 Loss of Power (LOP) Instrumentation...................................................... 3.3.8.1-1 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring................... 3.3.8.2-1 TABLE OF CONTENTS Page Number 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating.................................................................... 3.4.1-1 3.4.2 Jet Pumps................................................................................................... 3.4.2-1 3.4.3 Safety/Relief Valves (S/RVs)...................................................................... 3.4.3-1 3.4.4 RCS Operational LEAKAGE....................................................................... 3.4.4-1 3.4.5 RCS Leakage Detection Instrumentation.................................................... 3.4.5-1 3.4.6 RCS Specific Activity.................................................................................. 3.4.6-1 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown.............................................................................................. 3.4.7-1 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.............................................................................................. 3.4.8-1 3.4.9 RCS Pressure and Temperature (P/T) Limits.............................................. 3.4.9-1 3.4.10 Reactor Steam Dome Pressure................................................................ 3.4.10-1 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating....................................................................................... 3.5.1-1 3.5.2 RPV Water Inventory ControlECCS - Shutdown......................................... 3.5.2-1 3.5.3 RCIC System.............................................................................................. 3.5.3-1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment............................................................................... 3.6.1.1-1 3.6.1.2 Primary Containment Air Lock.................................................................. 3.6.1.2-1 3.6.1.3 Primary Containment Isolation Valves (PCIVs)........................................ 3.6.1.3-1 3.6.1.4 Drywell Air Temperature.......................................................................... 3.6.1.4-1 3.6.1.5 Low-Low Set (LLS) Valves....................................................................... 3.6.1.5-1 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers................. 3.6.1.6-1 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers............................... 3.6.1.7-1 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray.......................................... 3.6.1.8-1 3.6.2.1 Suppression Pool Average Temperature................................................. 3.6.2.1-1 3.6.2.2 Suppression Pool Water Level................................................................. 3.6.2.2-1 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling....................... 3.6.2.3-1 3.6.3.1 Primary Containment Oxygen Concentration........................................... 3.6.3.1-1 3.6.4.1 Secondary Containment........................................................................... 3.6.4.1-1 3.6.4.2 Secondary Containment Isolation Valves (SCIVs).................................... 3.6.4.2-1 3.6.4.3 Standby Gas Treatment (SGT) System.................................................... 3.6.4.3-1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System.......................... 3.7.1-1 3.7.2 Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS)............................................................................................ 3.7.2-1 3.7.3 Emergency Diesel Generator Emergency Service Water (EDG-ESW) System.............................................................................. 3.7.3-1 3.7.4 Control Room Emergency Filtration (CREF) System................................... 3.7.4-1 3.7.5 Control Room Ventilation System............................................................... 3.7.5-1 Draft


3.7.6       Main Condenser Offgas ..............................................................................3.7.6-1 3.7.7       Main Turbine Bypass System .....................................................................3.7.7-1 3.7.8       Spent Fuel Storage Pool Water Level .........................................................3.7.8-1 raft D
Monticello ii Revision 1 3.7.6 Main Condenser Offgas.............................................................................. 3.7.6-1 3.7.7 Main Turbine Bypass System..................................................................... 3.7.7-1 3.7.8 Spent Fuel Storage Pool Water Level......................................................... 3.7.8-1 Draft
Monticello                                              ii                                                Revision 1


TABLE OF CONTENTS                                                                                               Page Number 3.8           ELECTRICAL POWER SYSTEMS 3.8.1           AC Sources - Operating ..............................................................................3.8.1-1 3.8.2           AC Sources - Shutdown ..............................................................................3.8.2-1 3.8.3           Diesel Fuel Oil, Lube Oil, and Starting Air ...................................................3.8.3-1 3.8.4           DC Sources - Operating ..............................................................................3.8.4-1 3.8.5           DC Sources - Shutdown..............................................................................3.8.5-1 3.8.6           Battery Parameters .....................................................................................3.8.6-1 3.8.7           Distribution Systems - Operating .................................................................3.8.7-1 3.8.8           Distribution Systems - Shutdown ................................................................3.8.8-1 3.9           REFUELING OPERATIONS 3.9.1           Refueling Equipment Interlocks...................................................................3.9.1-1 3.9.2           Refuel Position One-Rod-Out Interlock .......................................................3.9.2-1 3.9.3           Control Rod Position ...................................................................................3.9.3-1 3.9.4           Control Rod Position Indication ...................................................................3.9.4-1 3.9.5           Control Rod OPERABILITY - Refueling ......................................................3.9.5-1 3.9.6           Reactor Pressure Vessel (RPV) Water Level ..............................................3.9.6-1 3.9.7           Residual Heat Removal (RHR) - High Water Level .....................................3.9.7-1 3.9.8           Residual Heat Removal (RHR) - Low Water Level ......................................3.9.8-1 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 ra SPECIAL OPERATIONS Inservice Leak and Hydrostatic Testing Operation .................................... 3.10.1-1 ft Reactor Mode Switch Interlock Testing .....................................................3.10.2-1 Single Control Rod Withdrawal - Hot Shutdown ........................................ 3.10.3-1 Single Control Rod Withdrawal - Cold Shutdown ...................................... 3.10.4-1 Single Control Rod Drive (CRD) Removal - Refueling ............................... 3.10.5-1 Multiple Control Rod Withdrawal - Refueling ............................................. 3.10.6-1 Control Rod Testing - Operating ...............................................................3.10.7-1 SHUTDOWN MARGIN (SDM) Test - Refueling ........................................ 3.10.8-1 4.0 4.1 4.2 4.3 5.0 5.1 5.2 5.3 D
Monticello iii Revision 0 TABLE OF CONTENTS Page Number 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating.............................................................................. 3.8.1-1 3.8.2 AC Sources - Shutdown.............................................................................. 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air................................................... 3.8.3-1 3.8.4 DC Sources - Operating.............................................................................. 3.8.4-1 3.8.5 DC Sources - Shutdown.............................................................................. 3.8.5-1 3.8.6 Battery Parameters..................................................................................... 3.8.6-1 3.8.7 Distribution Systems - Operating................................................................. 3.8.7-1 3.8.8 Distribution Systems - Shutdown................................................................ 3.8.8-1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks................................................................... 3.9.1-1 3.9.2 Refuel Position One-Rod-Out Interlock....................................................... 3.9.2-1 3.9.3 Control Rod Position................................................................................... 3.9.3-1 3.9.4 Control Rod Position Indication................................................................... 3.9.4-1 3.9.5 Control Rod OPERABILITY - Refueling...................................................... 3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water Level.............................................. 3.9.6-1 3.9.7 Residual Heat Removal (RHR) - High Water Level..................................... 3.9.7-1 3.9.8 Residual Heat Removal (RHR) - Low Water Level...................................... 3.9.8-1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation.................................... 3.10.1-1 3.10.2 Reactor Mode Switch Interlock Testing..................................................... 3.10.2-1 3.10.3 Single Control Rod Withdrawal - Hot Shutdown........................................ 3.10.3-1 3.10.4 Single Control Rod Withdrawal - Cold Shutdown...................................... 3.10.4-1 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling............................... 3.10.5-1 3.10.6 Multiple Control Rod Withdrawal - Refueling............................................. 3.10.6-1 3.10.7 Control Rod Testing - Operating............................................................... 3.10.7-1 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling........................................ 3.10.8-1 4.0 DESIGN FEATURES................................................................................................. 4.0-1 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility...................................................................................................... 5.1-1 5.2 Organization........................................................................................................ 5.2-1 5.3 Unit Staff Qualifications....................................................................................... 5.3-1 5.4 Procedures.......................................................................................................... 5.4-1 5.5 Programs and Manuals........................................................................................ 5.5-1 5.6 Reporting Requirements...................................................................................... 5.6-1 5.7 High Radiation Area............................................................................................. 5.7-1 Draft
DESIGN FEATURES.................................................................................................4.0-1 Site Location Reactor Core Fuel Storage ADMINISTRATIVE CONTROLS Responsibility ......................................................................................................5.1-1 Organization ........................................................................................................5.2-1 Unit Staff Qualifications .......................................................................................5.3-1 5.4       Procedures ..........................................................................................................5.4-1 5.5       Programs and Manuals ........................................................................................5.5-1 5.6       Reporting Requirements ......................................................................................5.6-1 5.7       High Radiation Area.............................................................................................5.7-1 Monticello                                                      iii                                                  Revision 0


Definitions 1.1 1.0   USE AND APPLICATION 1.1   Definitions
Definitions 1.1 Monticello 1.1-1 Amendment No. 146 1.0 USE AND APPLICATION 1.1 Definitions  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term                                       Definition ACTIONS                                     ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
AVERAGE PLANAR LINEAR                       The APLHGR shall be applicable to a specific planar height HEAT GENERATION RATE                       and is equal to the sum of the LHGRs for all the fuel rods in (APLHGR)                                   the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific planar height HEAT GENERATION RATE and is equal to the sum of the LHGRs for all the fuel rods in (APLHGR) the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
CHANNEL CALIBRATION raft A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining D
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.
CHANNEL CHECK adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST shall be the injection of a TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.
CHANNEL FUNCTIONAL                         A CHANNEL FUNCTIONAL TEST shall be the injection of a TEST                                       simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.
Draft
Monticello                                                  1.1-1                                  Amendment No. 146


Definitions 1.1 1.1   Definitions CORE ALTERATION         CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.
Definitions 1.1 Monticello 1.1-2 Amendment No. 146 148, XXX 1.1 Definitions CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered to be CORE ALTERATIONS:
The following exceptions are not considered to be CORE ALTERATIONS:
: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
: a.
: b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
: b.
Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
REPORT (COLR) ra CORE OPERATING LIMITS DOSE EQUIVALENT I-131 ft The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Plant operation within these limits is addressed in individual Specifications.
CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal D
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR)-11, "Limiting Values of Radionuclide Intake and Air Concentration Factors for Inhalation, Submersion and Ingestion," September 1988, and FGR-12, "External Exposure to Radionuclides in Air, Water and Soil,"
DRAIN TIME Guidance Report (FGR)-11, "Limiting Values of Radionuclide Intake and Air Concentration Factors for Inhalation, Submersion and Ingestion," September 1988, and FGR-12, "External Exposure to Radionuclides in Air, Water and Soil,"
September 1993.
September 1993.
The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
a)   The water inventory above the TAF is divided by the limiting drain rate; b)   The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single Monticello                          1.1-2              Amendment No. 146 148, XXX
a)
The water inventory above the TAF is divided by the limiting drain rate; b)
The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single Draft


Definitions 1.1 human error), for all penetration flow paths below the TAF except:
Definitions 1.1 Monticello 1.1-3 Amendment No. 146 148, XXX human error), for all penetration flow paths below the TAF except:
: 1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
: 1.
: 2. Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or
Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
: 3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in ra c) ft the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power.
: 2.
The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory; d)   No additional draining events occur; and D
Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or
LEAKAGE e)   Realistic cross-sectional areas and drain rates are used.
: 3.
Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power.
c)
The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory; d)
No additional draining events occur; and e)
Realistic cross-sectional areas and drain rates are used.
A bounding DRAIN TIME may be used in lieu of a calculated value.
A bounding DRAIN TIME may be used in lieu of a calculated value.
LEAKAGE shall be:
LEAKAGE LEAKAGE shall be:
: a. Identified LEAKAGE
: a.
: 1. LEAKAGE into the drywell, such as that from pump seals or valve packing that is captured and conducted to a sump or collecting tank; or
Identified LEAKAGE
: 2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; Monticello              1.1-3              Amendment No. 146 148, XXX
: 1.
LEAKAGE into the drywell, such as that from pump seals or valve packing that is captured and conducted to a sump or collecting tank; or
: 2.
LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; Draft


Definitions 1.1 1.1   Definitions LEAKAGE (continued)
Definitions 1.1 Monticello 1.1-4 Amendment No. 146 1.1 Definitions LEAKAGE (continued)
: b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;
: b.
: c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE; and
Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;
: d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.
: c.
RATE (LHGR)
Total LEAKAGE Sum of the identified and unidentified LEAKAGE; and
LOGIC SYSTEM FUNCTIONAL TEST ra LINEAR HEAT GENERATION ft The LHGR shall be the heat generation rate per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
: d.
A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.
MODE D
LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per unit length of RATE (LHGR) fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.
MINIMUM CRITICAL POWER RATIO (MCPR)
LOGIC SYSTEM A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all FUNCTIONAL TEST logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.
The MCPR shall be the smallest critical power ratio (CPR) that exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power ratio (CPR) that RATIO (MCPR) exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.
A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.
Monticello                            1.1-4                          Amendment No. 146
Draft


Definitions 1.1 1.1   Definitions OPERABLE - OPERABILITY   A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
Definitions 1.1 Monticello 1.1-5 Amendment No. 146, 172, 175, 176, 179 1.1 Definitions OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
PRESSURE AND             The PTLR is the unit specific document that provides the TEMPERATURE LIMITS       reactor vessel pressure and temperature limits, including REPORT (PTLR)           heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.5.
PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.5.
RATED THERMAL POWER (RTP)
RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2004 MWt.
REACTOR PROTECTION ra SYSTEM (RPS) RESPONSE TIME SHUTDOWN MARGIN (SDM) ft RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2004 MWt.
REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval from SYSTEM (RPS) RESPONSE initiation of any RPS channel trip to the de-energization of the TIME scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
The RPS RESPONSE TIME shall be that time interval from initiation of any RPS channel trip to the de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
SHUTDOWN MARGIN (SDM)
SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating D                  cycle assuming that:
SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:
a.
: a.
b.
The reactor is xenon free;
c.
: b.
The reactor is xenon free; The moderator temperature is 68°F corresponding to the most reactive state; and All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn. With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
The moderator temperature is 68°F corresponding to the most reactive state; and
Monticello                          1.1-5    Amendment No. 146, 172, 175, 176, 179
: c.
All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn. With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
Draft


Definitions 1.1 1.1   Definitions STAGGERED TEST BASIS   A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
Definitions 1.1 Monticello 1.1-6 Amendment No. 146, 175 1.1 Definitions STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER           THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
TURBINE BYPASS SYSTEM   The TURBINE BYPASS SYSTEM RESPONSE TIME shall be RESPONSE TIME           that time interval from when the main turbine trip solenoid is activated until 80% of the turbine bypass capacity is established. The response time may be measured by means of any series of sequential, overlapping, or total steps so that raft the entire response time is measured.
TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME shall be RESPONSE TIME that time interval from when the main turbine trip solenoid is activated until 80% of the turbine bypass capacity is established. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
D Monticello                          1.1-6                    Amendment No. 146, 175
Draft


Definitions 1.1 Table 1.1-1 (page 1 of 1)
Definitions 1.1 Monticello 1.1-7 Amendment No. 146 Table 1.1-1 (page 1 of 1)
MODES AVERAGE REACTOR COOLANT REACTOR MODE                TEMPERATURE MODE                  TITLE              SWITCH POSITION                  (°F) 1       Power Operation       Run                                         NA 2       Startup               Refuel(a) or Startup/Hot Standby           NA 3       Hot Shutdown(a)       Shutdown                                   > 212 4       Cold Shutdown(a)       Shutdown                                   212 5
MODES MODE TITLE REACTOR MODE SWITCH POSITION AVERAGE REACTOR COOLANT TEMPERATURE
ra Refueling(b) ft Shutdown or Refuel (a) All reactor vessel head closure bolts fully tensioned.
(°F) 1 Power Operation Run NA 2
Startup Refuel(a) or Startup/Hot Standby NA 3
Hot Shutdown(a)
Shutdown  
> 212 4
Cold Shutdown(a)
Shutdown 212 5
Refueling(b)
Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensioned.
NA D
Draft
Monticello                                    1.1-7                      Amendment No. 146


ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1       Emergency Core Cooling System (ECCS) Instrumentation LCO 3.3.5.1                 The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-1 Amendment No. 146, XXX 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation LCO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.
APPLICABILITY:               According to Table 3.3.5.1-1.
APPLICABILITY:
ACTIONS
According to Table 3.3.5.1-1.
ACTIONS  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION A. One or more channels inoperable.           ra B. As required by Required ft              A.1 B.1 REQUIRED ACTION Enter the Condition referenced in Table 3.3.5.1-1 for the channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
                                                      --------------NOTES-------------
A.1 Enter the Condition referenced in Table 3.3.5.1-1 for the channel.
COMPLETION TIME Immediately Action A.1 and                                    1. Only applicable in D
Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
referenced in Table 3.3.5.1-1.
B.1
MODES 1, 2, and 3.
--------------NOTES-------------
: 1. Only applicable in MODES 1, 2, and 3.
: 2. Only applicable for Functions 1.a, 1.b, 2.a, 2.b, 2.f, 2.h, and 2.k.
: 2. Only applicable for Functions 1.a, 1.b, 2.a, 2.b, 2.f, 2.h, and 2.k.
Declare supported                         1 hour from discovery feature(s) inoperable when               of loss of initiation its redundant feature ECCS               capability for initiation capability is                  feature(s) in both inoperable.                              divisions AND Monticello                                              3.3.5.1-1                            Amendment No. 146, XXX
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
AND 1 hour from discovery of loss of initiation capability for feature(s) in both divisions Draft


ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-2 Amendment No. 146, XXX ACTIONS (continued)
CONDITION                 REQUIRED ACTION                           COMPLETION TIME B.2   ---------------NOTE--------------
CONDITION REQUIRED ACTION COMPLETION TIME B.2  
---------------NOTE--------------
Only applicable for Functions 3.a and 3.b.
Only applicable for Functions 3.a and 3.b.
Declare High Pressure                     1 hour from discovery Coolant Injection (HPCI)                 of loss of HPCI System inoperable.                       initiation capability AND B.3   Place channel in trip.                   24 hours Action A.1 and referenced in ra C. As required by Required Table 3.3.5.1-1.
Declare High Pressure Coolant Injection (HPCI)
ft C.1   --------------NOTES-------------
System inoperable.
AND B.3 Place channel in trip.
1 hour from discovery of loss of HPCI initiation capability 24 hours C. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
C.1  
--------------NOTES-------------
: 1. Only applicable in MODES 1, 2, and 3.
: 1. Only applicable in MODES 1, 2, and 3.
: 2. Only applicable for Functions 1.c, 1.d, 1.e, 1.f, 2.c, 2.d, 2.e, 2.i, 2.j, 2.l, and 2.m.
: 2. Only applicable for Functions 1.c, 1.d, 1.e, 1.f, 2.c, 2.d, 2.e, 2.i, 2.j, 2.l, and 2.m.
Declare supported                         1 hour from discovery D                      AND C.2 feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
Restore channel to of loss of initiation capability for feature(s) in both divisions 24 hours OPERABLE status.
AND C.2 Restore channel to OPERABLE status.
Monticello                            3.3.5.1-2                            Amendment No. 146, XXX
1 hour from discovery of loss of initiation capability for feature(s) in both divisions 24 hours Draft


ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-3 Amendment No. 146, XXX ACTIONS (continued)
CONDITION                       REQUIRED ACTION                           COMPLETION TIME D. As required by Required   D.1       ---------------NOTE--------------
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
Action A.1 and                      Only applicable if HPCI referenced in                        pump suction is not aligned Table 3.3.5.1-1.                    to the suppression pool.
D.1  
Declare HPCI System                       1 hour from discovery inoperable.                               of loss of HPCI initiation capability AND D.2.1     Place channel in trip.                   24 hours raft E. As required by Required Action A.1 and referenced in D.2.2 E.1 OR Align the HPCI pump suction to the suppression pool.
---------------NOTE--------------
                                        --------------NOTES-------------
Only applicable if HPCI pump suction is not aligned to the suppression pool.
Declare HPCI System inoperable.
AND D.2.1 Place channel in trip.
OR D.2.2 Align the HPCI pump suction to the suppression pool.
1 hour from discovery of loss of HPCI initiation capability 24 hours 24 hours E. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
E.1  
--------------NOTES-------------
: 1. Only applicable in MODES 1, 2, and 3.
: 1. Only applicable in MODES 1, 2, and 3.
24 hours Table 3.3.5.1-1.
: 2. Only applicable for Function 2.g.
D                                  2. Only applicable for Function 2.g.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is 1 hour from discovery of loss of initiation capability for inoperable.                              subsystems in both divisions AND E.2        Restore channel to OPERABLE status.                          7 days Monticello                                3.3.5.1-3                            Amendment No. 146, XXX
AND E.2 Restore channel to OPERABLE status.
1 hour from discovery of loss of initiation capability for subsystems in both divisions 7 days Draft


ECCS Instrumentation 3.3.5.1 CTIONS (continued)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-4 Amendment No. 146 CTIONS (continued)
CONDITION                 REQUIRED ACTION           COMPLETION TIME F. As required by Required   F.1  Declare Automatic          1 hour from discovery Action A.1 and                 Depressurization System    of loss of ADS referenced in                  (ADS) valves inoperable. initiation capability in Table 3.3.5.1-1.                                           both trip systems AND F.2   Place channel in trip.
CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
96 hours from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling Action A.1 and referenced in raft G. As required by Required  G.1   Declare ADS valves inoperable.
F.1 Declare Automatic Depressurization System (ADS) valves inoperable.
(RCIC) inoperable AND 8 days 1 hour from discovery of loss of ADS initiation capability in Table 3.3.5.1-1.                                          both trip systems D                      AND G.2  Restore channel to OPERABLE status.
AND F.2 Place channel in trip.
96 hours from discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days H. Required Action and       H.1  Declare associated        Immediately associated Completion           supported feature(s)
1 hour from discovery of loss of ADS initiation capability in both trip systems 96 hours from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days G. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
Time of Condition B, C,         inoperable.
G.1 Declare ADS valves inoperable.
D, E, F, or G not met.
AND G.2 Restore channel to OPERABLE status.
Monticello                            3.3.5.1-4                  Amendment No. 146
1 hour from discovery of loss of ADS initiation capability in both trip systems 96 hours from discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days H. Required Action and associated Completion Time of Condition B, C, D, E, F, or G not met.
H.1 Declare associated supported feature(s) inoperable.
Immediately Draft


ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-5 Amendment No. 146, 151 SURVEILLANCE REQUIREMENTS  
-----------------------------------------------------------NOTES----------------------------------------------------------
-----------------------------------------------------------NOTES----------------------------------------------------------
: 1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
: 1.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability.
Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
SURVEILLANCE                                                     FREQUENCY SR 3.3.5.1.1             Perform CHANNEL CHECK.                                                   12 hours SR 3.3.5.1.2             Perform CHANNEL FUNCTIONAL TEST.                                         92 days SR 3.3.5.1.3 SR 3.3.5.1.4 SR 3.3.5.1.5 ra Calibrate the trip unit.
: 2.
ft Perform CHANNEL CALIBRATION.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability.
Perform CHANNEL FUNCTIONAL TEST.
SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.
92 days 92 days 12 months D
12 hours SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.
SR 3.3.5.1.6 SR 3.3.5.1.7 SR 3.3.5.1.8 Perform CHANNEL CALIBRATION.
92 days SR 3.3.5.1.3 Calibrate the trip unit.
Perform CHANNEL CALIBRATION.
92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.
Perform LOGIC SYSTEM FUNCTIONAL TEST.
92 days SR 3.3.5.1.5 Perform CHANNEL FUNCTIONAL TEST.
12 months 24 months 24 months SR 3.3.5.1.9             Perform CHANNEL FUNCTIONAL TEST.                                         24 months Monticello                                              3.3.5.1-5                          Amendment No. 146, 151
12 months SR 3.3.5.1.6 Perform CHANNEL CALIBRATION.
12 months SR 3.3.5.1.7 Perform CHANNEL CALIBRATION.
24 months SR 3.3.5.1.8 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months SR 3.3.5.1.9 Perform CHANNEL FUNCTIONAL TEST.
24 months Draft


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-6 Amendment No. 146, 151, 170, 176, XXX Table 3.3.5.1-1 (page 1 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE                   CONDITIONS MODES         REQUIRED      REFERENCED OR OTHER       CHANNELS         FROM SPECIFIED        PER         REQUIRED        SURVEILLANCE          ALLOWABLE FUNCTION             CONDITIONS     FUNCTION      ACTION A.1     REQUIREMENTS           VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Core Spray System (ab)
: 1. Core Spray System
: a. Reactor Vessel           1, 2, 3,       4               B         SR   3.3.5.1.1         -48 inches (a)  (a)
: a.
Water Level - Low        4 ,5                                        SR   3.3.5.1.2 Low                                                                  SR   3.3.5.1.3 SR   3.3.5.1.7 SR   3.3.5.1.8 (ab)
Reactor Vessel Water Level - Low Low 1, 2, 3, 4(a), 5(a) 4(ab)
: b. Drywell Pressure -       1, 2, 3         4               B         SR 3.3.5.1.2             2 psig High                                                                SR 3.3.5.1.4 SR 3.3.5.1.8 c.
B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8  
d.
-48 inches
Reactor Steam Reactor Steam Dome Pressure ra Dome Pressure -
: b.
Low (Injection Permissive) ft 1, 2, 3 (a) 4 ,5 1, 2, 3 (a) 2 2
Drywell Pressure -
2 C
High 1, 2, 3 4(ab)
B C
B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig
SR 3.3.5.1.2 SR 3.3.5.1.4 d)
: c.
SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c (c)(d)
Reactor Steam Dome Pressure -
(bc)(c 397 psig and 440 psig 397 psig and 440 psig 397 psig d)
Low (Injection Permissive) 1, 2, 3 2
Permissive - Low D
C SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)
e.
SR 3.3.5.1.8 397 psig and 440 psig 4(a), 5(a) 2 B
(Pump Permissive)
SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)
Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive)
SR 3.3.5.1.8 397 psig and 440 psig
(a) 4 ,5 1, 2, 3 (a) 4 ,5 (a)
: d.
(a) 2 2
Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2
2 B
C B
C B
SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 (c)(d) 397 psig 18 minutes 18 minutes SR 3.3.5.1.8 (a)   When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown."
SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)
(ab)   Also required to initiate the associated emergency diesel generator (EDG).
SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)
SR 3.3.5.1.8 397 psig 397 psig
: e.
Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2
C B
SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes 18 minutes (a)
When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown."
(ab) Also required to initiate the associated emergency diesel generator (EDG).
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the Technical Requirements Manual (TRM).
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the Technical Requirements Manual (TRM).
Monticello                                            3.3.5.1-6 Amendment No. 146, 151, 170, 176, XXX
Draft


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-7 Amendment No. 146, XXX Table 3.3.5.1-1 (page 2 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE                   CONDITIONS MODES         REQUIRED      REFERENCED OR OTHER       CHANNELS         FROM SPECIFIED        PER         REQUIRED        SURVEILLANCE            ALLOWABLE FUNCTION               CONDITIONS     FUNCTION      ACTION A.1     REQUIREMENTS             VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Core Spray System
: 1. Core Spray System
: f. Core Spray Pump         1, 2, 3       1 per pump         C         SR 3.3.5.1.7               15.86 (a)  (a)
: f.
Start - Time Delay      4 ,5                                        SR 3.3.5.1.8             seconds Relay
Core Spray Pump Start - Time Delay Relay 1, 2, 3 4(a), 5(a) 1 per pump C
SR 3.3.5.1.7 SR 3.3.5.1.8 15.86 seconds
: 2. Low Pressure Coolant Injection (LPCI) System
: 2. Low Pressure Coolant Injection (LPCI) System
: a. Reactor Vessel           1, 2, 3,           4             B         SR   3.3.5.1.1           -48 inches (a)  (a)
: a.
Water Level - Low        4 ,5                                        SR   3.3.5.1.2 b.
Reactor Vessel Water Level - Low Low 1, 2, 3, 4(a), 5(a) 4 B
c.
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8  
Low High Reactor Steam ra Dome Pressure -
-48 inches
Low (Injection Permissive) ft Drywell Pressure -        1, 2, 3 1, 2, 3 4
: b.
2 B
Drywell Pressure -
C SR SR SR 3.3.5.1.3 3.3.5.1.7 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 d)
High 1, 2, 3 4
SR 3.3.5.1.8 (bc)(c 2 psig 397 psig and 440 psig (a)  (a)
B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig
D
: c.
: d. Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 4 ,5 1, 2, 3 (a) 4 ,5 (a) 2 2
Reactor Steam Dome Pressure -
2 B
Low (Injection Permissive) 1, 2, 3 2
C B
C SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 d)
SR 3.3.5.1.8 397 psig and 440 psig 4(a), 5(a) 2 B
SR SR SR SR (c)(d)
SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)
(bc)(c 3.3.5.1.8 3.3.5.1.2 3.3.5.1.4 3.3.5.1.8 (c)(d) 397 psig and 440 psig 397 psig 397 psig (a)   When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
SR 3.3.5.1.8 397 psig and 440 psig
: d.
Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 1, 2, 3 2
C SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)
SR 3.3.5.1.8 397 psig 4(a), 5(a) 2 B
SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)
SR 3.3.5.1.8 397 psig (a)
When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.
Monticello                                            3.3.5.1-7                        Amendment No. 146, XXX
Draft


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 6)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-8 Correction letter of 10/12/06 Amendment No. 146, 149, 151, 161, 170 176, XXX Table 3.3.5.1-1 (page 3 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE                   CONDITIONS MODES       REQUIRED      REFERENCED OR OTHER     CHANNELS         FROM SPECIFIED      PER         REQUIRED        SURVEILLANCE          ALLOWABLE FUNCTION               CONDITIONS     FUNCTION      ACTION A.1     REQUIREMENTS           VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 2. LPCI System
: 2. LPCI System
: e. Reactor Steam             1, 2, 3           2             C         SR 3.3.5.1.7           18 minutes Dome Pressure                                                        SR 3.3.5.1.8 Permissive - Bypass Timer (Pump (a)  (a)
: e.
Permissive)              4 ,5              2              B          SR 3.3.5.1.7           18 minutes SR 3.3.5.1.8
Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2
: f. Low Pressure             1, 2, 3,     4 per pump         B         SR 3.3.5.1.7 (a)  (a)
C B
Coolant Injection        4 ,5                                        SR 3.3.5.1.8 g.
SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes 18 minutes
Pumps A, B Pumps C, D Low Pressure ra Pump Start - Time Delay Relay ft Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2, 3, (a) 4 ,5 (a) 1 per pump         E         SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 5.33 seconds 10.59 seconds 360 gpm and 745 gpm
: f.
: h. Reactor Steam             1, 2, 3           4             B         SR 3.3.5.1.2           873.6 psig D
Low Pressure Coolant Injection Pump Start - Time Delay Relay 1, 2, 3, 4(a), 5(a) 4 per pump B
i.
SR 3.3.5.1.7 SR 3.3.5.1.8 Pumps A, B 5.33 seconds Pumps C, D 10.59 seconds
j.
: g.
Dome Pressure -
Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2, 3, 4(a), 5(a) 1 per pump E
Low (Break Detection)
SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 360 gpm and 745 gpm
Recirculation Pump Differential Pressure
: h.
            - High (Break Detection)
Reactor Steam Dome Pressure -
Recirculation Riser Differential Pressure 1, 2, 3 1, 2, 3 4 per pump 4
Low (Break Detection) 1, 2, 3 4
C C
B SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 873.6 psig and 923.4 psig
SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.2 SR and 923.4 psig 63.5 inches wc 100.0 inches wc (bc)(cd)
: i.
            - High (Break                                                        3.3.5.1.7 Detection)                                                            SR 3.3.5.1.8 (a)   When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
Recirculation Pump Differential Pressure  
- High (Break Detection) 1, 2, 3 4 per pump C
SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 63.5 inches wc
: j.
Recirculation Riser Differential Pressure
- High (Break Detection) 1, 2, 3 4
C SR 3.3.5.1.2 SR 3.3.5.1.7(bc)(cd)
SR 3.3.5.1.8 100.0 inches wc (a)
When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.
Monticello                                            3.3.5.1-8                Correction letter of 10/12/06 Amendment No. 146, 149, 151, 161, 170 176, XXX
Draft


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 6)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-9 Amendment No. 146, 149, 151, 161, XXX Table 3.3.5.1-1 (page 4 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE                           CONDITIONS MODES                   REQUIRED  REFERENCED OR OTHER                 CHANNELS     FROM SPECIFIED                  PER       REQUIRED    SURVEILLANCE      ALLOWABLE FUNCTION               CONDITIONS               FUNCTION    ACTION A.1   REQUIREMENTS       VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 2. LPCI System
: 2. LPCI System
: k. Recirculation Steam       1, 2, 3                   2           B         SR 3.3.5.1.7     2.97 seconds Dome Pressure -                                                            SR 3.3.5.1.8 Time Delay Relay                                                          SR 3.3.5.1.9 (Break Detection)
: k.
: l. Recirculation Pump       1, 2, 3                   2           C         SR 3.3.5.1.7     0.75 seconds Differential Pressure                                                      SR 3.3.5.1.8
Recirculation Steam Dome Pressure -
            - Time Delay Relay                                                        SR 3.3.5.1.9 (Break Detection) 3.
Time Delay Relay (Break Detection) 1, 2, 3 2
a.
B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 2.97 seconds
ra
: l.
: m. Recirculation Riser Differential Pressure
Recirculation Pump Differential Pressure
          - Time Delay Relay Reactor Vesselft (Break Detection)
- Time Delay Relay (Break Detection) 1, 2, 3 2
High Pressure Coolant Injection (HPCI) System Water Level - Low Low 1, 2, 3 1, 2 (de)
C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds
                                                  ,3 (de) 2 4
: m. Recirculation Riser Differential Pressure  
C B
- Time Delay Relay (Break Detection) 1, 2, 3 2
SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.3 0.75 seconds
C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds
                                                                                                          -48 inches SR  3.3.5.1.7 D
: 3. High Pressure Coolant Injection (HPCI) System
b.
: a.
c.
Reactor Vessel Water Level - Low Low 1, 2(de), 3(de) 4 B
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8
-48 inches
: b.
Drywell Pressure -
Drywell Pressure -
High Reactor Vessel Water Level - High 1, 2 1, 2 (de)
High 1, 2(de), 3(de) 4 B
(de)
SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig
                                                  ,3
: c.
                                                  ,3 (de)
Reactor Vessel Water Level - High 1, 2(de), 3(de) 2 C
(de) 4 2
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 48 inches
B C
: d.
SR SR SR SR SR SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 3.3.5.1.1 3.3.5.1.2 3.3.5.1.3 3.3.5.1.7 3.3.5.1.8 2 psig 48 inches (de)        (de)
Condensate Storage Tank Level - Low 1, 2(de), 3(de) 2 D
: d. Condensate Storage     1, 2         ,3             2           D         SR 3.3.5.1.7     29.3 inches Tank Level - Low                                                          SR 3.3.5.1.8 (de)        (de)
SR 3.3.5.1.7 SR 3.3.5.1.8 29.3 inches
: e. Suppression Pool       1, 2         ,3             2           D         SR 3.3.5.1.5       3.0 inches Water Level - High                                                        SR 3.3.5.1.6 SR 3.3.5.1.8 (de)        (de)
: e.
: f. High Pressure           1, 2         ,3             1           E         SR 3.3.5.1.5     362 gpm and Coolant Injection                                                          SR 3.3.5.1.6       849 gpm Pump Discharge                                                            SR 3.3.5.1.8 Flow - Low (Bypass)
Suppression Pool Water Level - High 1, 2(de), 3(de) 2 D
(de) With reactor steam dome pressure > 150 psig.
SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 3.0 inches
Monticello                                                      3.3.5.1-9 Amendment No. 146, 149, 151, 161, XXX
: f.
High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2(de), 3(de) 1 E
SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 362 gpm and 849 gpm (de) With reactor steam dome pressure > 150 psig.
Draft


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 6)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-10 Amendment No. 146, XXX Table 3.3.5.1-1 (page 5 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE                           CONDITIONS MODES                   REQUIRED  REFERENCED OR OTHER                 CHANNELS     FROM SPECIFIED                  PER       REQUIRED    SURVEILLANCE          ALLOWABLE FUNCTION               CONDITIONS                 FUNCTION    ACTION A.1   REQUIREMENTS           VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 4. Automatic Depressurization System (ADS) Trip System A (de)        (de)
: 4. Automatic Depressurization System (ADS) Trip System A
: a. Reactor Vessel         1, 2         ,3             2           F         SR   3.3.5.1.1         -48 inches Water Level - Low                                                          SR   3.3.5.1.2 Low                                                                        SR   3.3.5.1.3 SR   3.3.5.1.7 SR   3.3.5.1.8 (de)        (de)
: a.
: b. Automatic               1, 2         ,3             1           G         SR 3.3.5.1.7         120 seconds c.
Reactor Vessel Water Level - Low Low 1, 2(de), 3(de) 2 F
d.
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8  
Timer
-48 inches
            - High Low Pressure ra Depressurization System Initiation ft Core Spray Pump Discharge Pressure Coolant Injection Pump Discharge 1, 2 1, 2 (de)
: b.
(de)
Automatic Depressurization System Initiation Timer 1, 2(de), 3(de) 1 G
                                                  ,3
SR 3.3.5.1.7 SR 3.3.5.1.8 120 seconds
                                                  ,3 (de)
: c.
(de) 2 4
Core Spray Pump Discharge Pressure  
G G
- High 1, 2(de), 3(de) 2 G
SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 d)
SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)
SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 d)
SR 3.3.5.1.8 75 psig and 125 psig
(bc)(c (bc)(c 75 psig and 125 psig 75 psig and 125 psig Pressure - High                                                            SR 3.3.5.1.8 5.
: d.
D ADS Trip System B a.
Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(de), 3(de) 4 G
b.
SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)
Reactor Vessel Water Level - Low Low Automatic Depressurization 1, 2 1, 2 (de)
SR 3.3.5.1.8 75 psig and 125 psig
(de)
: 5. ADS Trip System B
                                                  ,3
: a.
                                                  ,3 (de)
Reactor Vessel Water Level - Low Low 1, 2(de), 3(de) 2 F
(de) 2 1
SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8  
F G
-48 inches
SR SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.3 3.3.5.1.7 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8
: b.
                                                                                                              -48 inches 120 seconds System Initiation Timer (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
Automatic Depressurization System Initiation Timer 1, 2(de), 3(de) 1 G
SR 3.3.5.1.7 SR 3.3.5.1.8 120 seconds (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.
(de) With reactor steam dome pressure > 150 psig.
(de) With reactor steam dome pressure > 150 psig.
Monticello                                                      3.3.5.1-10                  Amendment No. 146, XXX
Draft


ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 6 of 6)
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-11 Amendment No. 146, XXX Table 3.3.5.1-1 (page 6 of 6)
Emergency Core Cooling System Instrumentation APPLICABLE                           CONDITIONS MODES                   REQUIRED  REFERENCED OR OTHER                 CHANNELS     FROM SPECIFIED                  PER       REQUIRED    SURVEILLANCE        ALLOWABLE FUNCTION               CONDITIONS                 FUNCTION    ACTION A.1   REQUIREMENTS           VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 5. ADS Trip System B (de)        (de)
: 5. ADS Trip System B
: c. Core Spray Pump         1, 2         ,3             2           G         SR 3.3.5.1.2         75 psig and (bc)(c Discharge Pressure                                                        SR 3.3.5.1.4           125 psig d)
: c.
            - High SR 3.3.5.1.8 (de)        (de)
Core Spray Pump Discharge Pressure
: d. Low Pressure           1, 2         ,3             4           G         SR 3.3.5.1.2         75 psig and (bc)(c Coolant Injection                                                          SR 3.3.5.1.4           125 psig d)
- High 1, 2(de), 3(de) 2 G
Pump Discharge Pressure - High                                                            SR 3.3.5.1.8 ra (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before ft returning the channel to service.
SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)
SR 3.3.5.1.8 75 psig and 125 psig
: d.
Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(de), 3(de) 4 G
SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)
SR 3.3.5.1.8 75 psig and 125 psig (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.
(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.
(de) With reactor steam dome pressure > 150 psig.
(de) With reactor steam dome pressure > 150 psig.
D Monticello                                                      3.3.5.1-11                  Amendment No. 146, XXX
Draft


RPV Water Inventory Control Instrumentation 3.3.5.3 3.3 INSTRUMENTATION 3.3.5.3       Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.3                 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.3-1 shall be OPERABLE.
RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-1 Amendment No. XXX 3.3 INSTRUMENTATION 3.3.5.3 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.3 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.3-1 shall be OPERABLE.
APPLICABILITY:               According to Table 3.3.5.3-1.
APPLICABILITY:
ACTIONS
According to Table 3.3.5.3-1.
ACTIONS  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION A. One or more channels inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
raft              A.1 REQUIRED ACTION Enter the Condition referenced in Table 3.3.5.3-1 for the channel.
A.1 Enter the Condition referenced in Table 3.3.5.3-1 for the channel.
COMPLETION TIME Immediately B. As required by Required                 B.1      Declare associated                        Immediately D
Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.3-1.
Action A.1 and referenced in Table 3.3.5.3-1.
B.1 Declare associated penetration flow path(s) incapable of automatic isolation.
AND B.2 penetration flow path(s) incapable of automatic isolation.
AND B.2 Calculate DRAIN TIME.
Calculate DRAIN TIME.                     Immediately C. As required by Required                 C.1      Place channel in trip.                    1 hour Action A.1 and referenced in Table 3.3.5.3-1.
Immediately Immediately C. As required by Required Action A.1 and referenced in Table 3.3.5.3-1.
D. As required by Required                 D.1      Restore channel to                        24 hours Action A.1 and                                   OPERABLE status.
C.1 Place channel in trip.
referenced in Table 3.3.5.3-1.
1 hour D. As required by Required Action A.1 and referenced in Table 3.3.5.3-1.
Monticello                                              3.3.5.3-1                               Amendment No. XXX
D.1 Restore channel to OPERABLE status.
24 hours Draft


RPV Water Inventory Control Instrumentation 3.3.5.3 ACTIONS (continued)
RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-2 Amendment No. XXX ACTIONS (continued)
CONDITION                                 REQUIRED ACTION                           COMPLETION TIME E. Required Action and                     E.1       Declare associated low                   Immediately associated Completion                            pressure ECCS Time of Condition C or D                          injection/spray subsystem not met.                                          inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met.
SURVEILLANCE REQUIREMENTS
E.1 Declare associated low pressure ECCS injection/spray subsystem inoperable.
Immediately SURVEILLANCE REQUIREMENTS  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
Refer to Table 3.3.5.3-1 to determine which SRs apply for each ECCS Function.
Refer to Table 3.3.5.3-1 to determine which SRs apply for each ECCS Function.
SURVEILLANCE                                                     FREQUENCY SR 3.3.5.3.1 SR 3.3.5.3.2 ra Perform CHANNEL CHECK.
SURVEILLANCE FREQUENCY SR 3.3.5.3.1 Perform CHANNEL CHECK.
ft Perform CHANNEL FUNCTIONAL TEST.
12 hours SR 3.3.5.3.2 Perform CHANNEL FUNCTIONAL TEST.
12 hours 92 days D
92 days Draft
Monticello                                              3.3.5.3-2                                Amendment No. XXX


RPV Water Inventory Control Instrumentation 3.3.5.3 Table 3.3.5.3-1 (page 1 of 1)
RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-3 Amendment No. XXX Table 3.3.5.3-1 (page 1 of 1)
RPV Water Inventory Control Instrumentation APPLICABLE                 CONDITIONS MODES       REQUIRED    REFERENCED OR OTHER     CHANNELS       FROM SPECIFIED      PER         REQUIRED        SURVEILLANCE        ALLOWABLE FUNCTION             CONDITIONS   FUNCTION      ACTION A.1     REQUIREMENTS           VALUE
RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Core Spray System
: 1. Core Spray System
: a. Reactor                   4, 5         2             C         SR 3.3.5.3.2       397 psig and Steam Dome                                                                              440psig Pressure - Low (Injection Permissive)
: a.
Reactor Steam Dome Pressure - Low (Injection Permissive) 4, 5 2
C SR 3.3.5.3.2 397 psig and 440psig
: 2. Low Pressure Coolant Injection (LPCI)
: 2. Low Pressure Coolant Injection (LPCI)
System a.
System
b.
: a.
Permissive)
Reactor Steam Dome Pressure -
Low Pressure ra Reactor Steam Dome Pressure -
Low (Injection Permissive) 4, 5 2
Low (Injection ft Coolant Injection Pump Discharge Flow - Low (Bypass) 4, 5 4, 5 2
C SR 3.3.5.3.2 397 psig and 440 psig
1 per pump(a)
: b.
C D
Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 4, 5 1 per pump(a)
SR 3.3.5.3.2 SR 3.3.5.3.2 397 psig and 440 psig 360 gpm and 745 gpm
D SR 3.3.5.3.2 360 gpm and 745 gpm
: 3. RHR System Isolation 4.
: 3. RHR System Isolation
D
: a.
: a. Reactor Vessel Water Level - Low Reactor Water Cleanup (RWCU) System Isolation
Reactor Vessel Water Level - Low (b) 2 B
: a. Reactor Vessel Water Level - Low (b)
SR 3.3.5.3.1 SR 3.3.5.3.2 7 inches
(b) 2 2
: 4. Reactor Water Cleanup (RWCU) System Isolation
B B
: a.
SR 3.3.5.3.1 SR 3.3.5.3.2 SR 3.3.5.3.1 SR 3.3.5.3.2 7 inches
Reactor Vessel Water Level - Low Low (b) 2 B
                                                                                                  -48 inches Low (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control."
SR 3.3.5.3.1 SR 3.3.5.3.2  
-48 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control."
(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
Monticello                                        3.3.5.3-3                          Amendment No. XXX
Draft


Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1       Primary Containment Isolation Instrumentation LCO 3.3.6.1                 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-1 Amendment No. 146 XXX 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
APPLICABILITY:               According to Table 3.3.6.1-1.
APPLICABILITY:
ACTIONS
According to Table 3.3.6.1-1.
ACTIONS  
-----------------------------------------------------------NOTES----------------------------------------------------------
-----------------------------------------------------------NOTES----------------------------------------------------------
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 1.
: 2. Separate Condition entry is allowed for each channel.
Penetration flow paths may be unisolated intermittently under administrative controls.
CONDITION A. One or more required channels inoperable.
: 2.
raft              A.1 REQUIRED ACTION Place channel in trip.
Separate Condition entry is allowed for each channel.
COMPLETION TIME 12 hours for Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND D
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required channels inoperable.
B. One or more Functions with primary B.1        Restore primary containment isolation 24 hours for Functions other than Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b 1 hour containment isolation                             capability.
A.1 Place channel in trip.
capability not maintained.
12 hours for Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND 24 hours for Functions other than Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b B. One or more Functions with primary containment isolation capability not maintained.
C. Required Action and                     C.1       Enter the Condition                     Immediately associated Completion                              referenced in Time of Condition A or B                          Table 3.3.6.1-1 for the not met.                                          channel.
B.1 Restore primary containment isolation capability.
Monticello                                              3.3.6.1-1                          Amendment No. 146 XXX
1 hour C. Required Action and associated Completion Time of Condition A or B not met.
C.1 Enter the Condition referenced in Table 3.3.6.1-1 for the channel.
Immediately Draft


Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-2 Amendment No. 146 XXX ACTIONS (continued)
CONDITION                   REQUIRED ACTION                 COMPLETION TIME D. As required by Required   D.1    Isolate associated main        12 hours Action C.1 and                   steam line (MSL).
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
referenced in Table 3.3.6.1-1.         OR D.2.1   Be in MODE 3.                   12 hours AND D.2.2   Be in MODE 4.                   36 hours E. As required by Required   E.1     Be in MODE 2.                   6 hours Action C.1 and referenced in Action C.1 and referenced in ra Table 3.3.6.1-1.
D.1 Isolate associated main steam line (MSL).
Table 3.3.6.1-1.ft F. As required by Required  F.1     Isolate the affected penetration flow path(s).
OR D.2.1 Be in MODE 3.
1 hour G. As required by Required   G.1    Isolate the affected            24 hours D
AND D.2.2 Be in MODE 4.
Action C.1 and referenced in Table 3.3.6.1-1.
12 hours 12 hours 36 hours E. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
H. As required by Required Action C.1 and referenced in H.1 penetration flow path(s).
E.1 Be in MODE 2.
Declare associated standby liquid control (SLC) subsystem inoperable.
6 hours F. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
1 hour Table 3.3.6.1-1.
F.1 Isolate the affected penetration flow path(s).
OR H.2     Isolate the Reactor Water       1 hour Cleanup System.
1 hour G. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
Monticello                                3.3.6.1-2                Amendment No. 146 XXX
G.1 Isolate the affected penetration flow path(s).
24 hours H. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
H.1 Declare associated standby liquid control (SLC) subsystem inoperable.
OR H.2 Isolate the Reactor Water Cleanup System.
1 hour 1 hour Draft


Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-3 Amendment No. 146 XXX ACTIONS (continued)
CONDITION                                 REQUIRED ACTION                           COMPLETION TIME I. As required by Required             I.1        Initiate action to restore              Immediately Action C.1 and                                 channel to OPERABLE referenced in                                   status.
CONDITION REQUIRED ACTION COMPLETION TIME I.
Table 3.3.6.1-1.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
OR I.2       Initiate action to isolate the           Immediately Residual Heat Removal (RHR) Shutdown Cooling System.
I.1 Initiate action to restore channel to OPERABLE status.
SURVEILLANCE REQUIREMENTS 2.
OR I.2 Initiate action to isolate the Residual Heat Removal (RHR) Shutdown Cooling System.
ra
Immediately Immediately SURVEILLANCE REQUIREMENTS  
-----------------------------------------------------------NOTES----------------------------------------------------------
-----------------------------------------------------------NOTES----------------------------------------------------------
: 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
: 1.
ft When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains primary containment isolation capability.
Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
D SR 3.3.6.1.1 SR 3.3.6.1.2 SURVEILLANCE Perform CHANNEL CHECK.
: 2.
Perform CHANNEL FUNCTIONAL TEST.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains primary containment isolation capability.
FREQUENCY 12 hours 92 days SR 3.3.6.1.3             Calibrate the trip unit.                                                 92 days SR 3.3.6.1.4             Perform CHANNEL CALIBRATION.                                             92 days Monticello                                              3.3.6.1-3                          Amendment No. 146 XXX
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.
12 hours SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.6.1.3 Calibrate the trip unit.
92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.
92 days Draft


Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-4 Amendment No. 146 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                                 FREQUENCY SR 3.3.6.1.5   Perform CHANNEL CALIBRATION.                     24 months SR 3.3.6.1.6   Perform LOGIC SYSTEM FUNCTIONAL TEST.           24 months raft D
SURVEILLANCE FREQUENCY SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
Monticello                      3.3.6.1-4                      Amendment No. 146
24 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months Draft


Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 3)
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-5 Amendment No. 146, 176 Table 3.3.6.1-1 (page 1 of 3)
Primary Containment Isolation Instrumentation APPLICABLE               CONDITIONS MODES OR   REQUIRED     REFERENCED OTHER      CHANNELS       FROM SPECIFIED    PER TRIP     REQUIRED     SURVEILLANCE      ALLOWABLE FUNCTION              CONDITIONS    SYSTEM      ACTION C.1   REQUIREMENTS         VALUE
Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Main Steam Line Isolation
: 1. Main Steam Line Isolation
: a. Reactor Vessel         1, 2, 3       2             D         SR   3.3.6.1.1     -48 inches Water Level - Low                                              SR   3.3.6.1.2 Low                                                            SR   3.3.6.1.3 SR   3.3.6.1.5 SR   3.3.6.1.6
: a.
: b. Main Steam Line           1           2             E         SR 3.3.6.1.2       815 psig Pressure - Low                                                SR 3.3.6.1.4 2.
Reactor Vessel Water Level - Low Low 1, 2, 3 2
c.
D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6  
d.
-48 inches
Flow - High ra Main Steam Line Main Steam Line Tunnel ft Temperature - High Primary Containment 1, 2, 3 1, 2, 3 2 per MSL 2 per trip string D
: b.
D SR 3.3.6.1.6 SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.6 SR 3.3.6.1.5 SR 3.3.6.1.6 116.9% rated steam flow 209°F Isolation D
Main Steam Line Pressure - Low 1
a.
2 E
b.
SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 815 psig
Reactor Vessel Water Level - Low Drywell Pressure -
: c.
High 1, 2, 3 1, 2, 3 2
Main Steam Line Flow - High 1, 2, 3 2 per MSL D
2 F
SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 116.9% rated steam flow
F SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.5 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 7 inches 2.0 psig
: d.
Main Steam Line Tunnel Temperature - High 1, 2, 3 2 per trip string D
SR 3.3.6.1.5 SR 3.3.6.1.6 209°F
: 2. Primary Containment Isolation
: a.
Reactor Vessel Water Level - Low 1, 2, 3 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches
: b.
Drywell Pressure -
High 1, 2, 3 2
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig
: 3. High Pressure Coolant Injection (HPCI) System Isolation
: 3. High Pressure Coolant Injection (HPCI) System Isolation
: a. HPCI Steam Line         1, 2, 3       2             F         SR 3.3.6.1.2       300,000 Flow - High                                                    SR 3.3.6.1.4     lb/hour with SR 3.3.6.1.6     5.58 second time delay Monticello                                      3.3.6.1-5                    Amendment No. 146, 176
: a.
HPCI Steam Line Flow - High 1, 2, 3 2
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 300,000 lb/hour with 5.58 second time delay Draft


Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 3)
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-6 Amendment No. 146 Table 3.3.6.1-1 (page 2 of 3)
Primary Containment Isolation Instrumentation APPLICABLE               CONDITIONS MODES OR   REQUIRED   REFERENCED OTHER      CHANNELS       FROM SPECIFIED    PER TRIP   REQUIRED     SURVEILLANCE        ALLOWABLE FUNCTION                CONDITIONS    SYSTEM      ACTION C.1   REQUIREMENTS         VALUE
Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 3. HPCI System Isolation
: 3. HPCI System Isolation
: b. HPCI Steam Supply         1, 2, 3       4           F         SR 3.3.6.1.2       95.5 psig Line Pressure - Low                                            SR 3.3.6.1.4 SR 3.3.6.1.6
: b.
: c. HPCI Steam Line           1, 2, 3       16           F         SR 3.3.6.1.2         196°F Area Temperature -                                              SR 3.3.6.1.4 High                                                            SR 3.3.6.1.6
HPCI Steam Supply Line Pressure - Low 1, 2, 3 4
: 4. Reactor Core Isolation a.
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 95.5 psig
b.
: c.
Flow - High ra Cooling (RCIC) System Isolation RCIC Steam Line ft RCIC Steam Supply Line Pressure - Low 1, 2, 3 1, 2, 3 2
HPCI Steam Line Area Temperature -
4 F
High 1, 2, 3 16 F
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 45,903 lb/hour with 7.16 second time delay 54 psig
SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196°F
: c. RCIC Steam Line           1, 2, 3       16           F         SR 3.3.6.1.2         196°F 5.
: 4.
D  Area Temperature -
Reactor Core Isolation Cooling (RCIC) System Isolation
High Reactor Water Cleanup (RWCU) System Isolation
: a.
: a. RWCU Flow - High         1, 2, 3       2           F SR 3.3.6.1.4 SR 3.3.6.1.6 SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.5 500 gpm with 11.4 second time delay SR  3.3.6.1.6
RCIC Steam Line Flow - High 1, 2, 3 2
: b. RWCU Room                 1, 2, 3       2           F         SR   3.3.6.1.1       188°F Temperature - High                                              SR   3.3.6.1.2 SR   3.3.6.1.3 SR   3.3.6.1.5 SR   3.3.6.1.6
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 45,903 lb/hour with 7.16 second time delay
: c. Drywell Pressure -       1, 2, 3       2           F         SR 3.3.6.1.2         2.0 psig High                                                            SR 3.3.6.1.4 SR 3.3.6.1.6 Monticello                                        3.3.6.1-6                          Amendment No. 146
: b.
RCIC Steam Supply Line Pressure - Low 1, 2, 3 4
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 54 psig
: c.
RCIC Steam Line Area Temperature -
High 1, 2, 3 16 F
SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196°F
: 5.
Reactor Water Cleanup (RWCU) System Isolation
: a.
RWCU Flow - High 1, 2, 3 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 500 gpm with 11.4 second time delay
: b.
RWCU Room Temperature - High 1, 2, 3 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188°F
: c.
Drywell Pressure -
High 1, 2, 3 2
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig Draft


Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-7 Amendment No. 146, 164, XXX Table 3.3.6.1-1 (page 3 of 3)
Primary Containment Isolation Instrumentation APPLICABLE                     CONDITIONS MODES OR     REQUIRED       REFERENCED OTHER        CHANNELS           FROM SPECIFIED      PER TRIP       REQUIRED     SURVEILLANCE        ALLOWABLE FUNCTION                CONDITIONS      SYSTEM          ACTION C.1   REQUIREMENTS           VALUE
Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 5. RWCU System Isolation
: 5. RWCU System Isolation
: d. SLC System               1, 2, 3           1               H         SR 3.3.6.1.6           NA Initiation
: d.
: e. Reactor Vessel           1, 2, 3           2               F         SR   3.3.6.1.1       -48 inches Water Level - Low                                                      SR   3.3.6.1.2 Low                                                                    SR   3.3.6.1.3 SR   3.3.6.1.5 SR   3.3.6.1.6
SLC System Initiation 1, 2, 3 1
: 6. Shutdown Cooling System Isolation a.
H SR 3.3.6.1.6 NA
b.
: e.
Reactor Steam ra Dome Pressure -
Reactor Vessel Water Level - Low Low 1, 2, 3 2
High Reactor Vessel ft Water Level - Low 1, 2, 3 3, 4, 5          2 2
F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6  
(a)
-48 inches
F I
: 6. Shutdown Cooling System Isolation
SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.5 3.3.6.1.6 81.8 psig 7 inches 7.
: a.
D Traversing Incore Probe System Isolation a.
Reactor Steam Dome Pressure -
b.
High 1, 2, 3 2
Reactor Vessel Water Level - Low Drywell Pressure -
F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 81.8 psig
High 1, 2, 3 1, 2, 3 2
: b.
2 G
Reactor Vessel Water Level - Low 3, 4, 5 2(a)
G SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.3 3.3.6.1.5 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 7 inches 2.0 psig SR 3.3.6.1.6 (a)   Only one channel per trip system, with an isolation signal available to one shutdown cooling supply isolation valve, is required in MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained.
I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches
Monticello                                            3.3.6.1-7                  Amendment No. 146, 164, XXX
: 7. Traversing Incore Probe System Isolation
: a.
Reactor Vessel Water Level - Low 1, 2, 3 2
G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches
: b.
Drywell Pressure -
High 1, 2, 3 2
G SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig (a)
Only one channel per trip system, with an isolation signal available to one shutdown cooling supply isolation valve, is required in MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained.
Draft


Secondary Containment Isolation Instrumentation 3.3.6.2 3.3 INSTRUMENTATION 3.3.6.2       Secondary Containment Isolation Instrumentation LCO 3.3.6.2                 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.
Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-1 Amendment No. 146 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.
APPLICABILITY:               According to Table 3.3.6.2-1.
APPLICABILITY:
ACTIONS
According to Table 3.3.6.2-1.
ACTIONS  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION A. One or more channels inoperable.           raft              A.1 REQUIRED ACTION Place channel in trip.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
COMPLETION TIME 12 hours for Functions 1 and 2 AND 24 hours for Functions other than Functions 1 and 2 D
A.1 Place channel in trip.
B. One or more Functions with secondary containment isolation capability not maintained.
12 hours for Functions 1 and 2 AND 24 hours for Functions other than Functions 1 and 2 B. One or more Functions with secondary containment isolation capability not maintained.
B.1       Restore secondary containment isolation capability.
B.1 Restore secondary containment isolation capability.
1 hour C. Required Action and                     C.1.1     Isolate the associated                   1 hour associated Completion                              penetration flow path(s).
1 hour C. Required Action and associated Completion Time not met.
Time not met.
C.1.1 Isolate the associated penetration flow path(s).
OR C.1.2     Declare associated                       1 hour secondary containment isolation valves inoperable.
OR C.1.2 Declare associated secondary containment isolation valves inoperable.
AND Monticello                                              3.3.6.2-1                                 Amendment No. 146
AND 1 hour 1 hour Draft


Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS (continued)
Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-2 Amendment No. 146 ACTIONS (continued)
CONDITION                                 REQUIRED ACTION                           COMPLETION TIME C.2.1     Place the associated                     1 hour standby gas treatment (SGT) subsystem in operation.
CONDITION REQUIRED ACTION COMPLETION TIME C.2.1 Place the associated standby gas treatment (SGT) subsystem in operation.
OR C.2.2     Declare associated SGT                   1 hour subsystem inoperable.
OR C.2.2 Declare associated SGT subsystem inoperable.
SURVEILLANCE REQUIREMENTS
1 hour 1 hour SURVEILLANCE REQUIREMENTS  
: 2.                        ra
-----------------------------------------------------------NOTES----------------------------------------------------------
-----------------------------------------------------------NOTES----------------------------------------------------------
: 1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.
: 1.
ft When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains secondary containment isolation capability.
Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.
D SR 3.3.6.2.1 SR 3.3.6.2.2 SURVEILLANCE Perform CHANNEL CHECK.
: 2.
Perform CHANNEL FUNCTIONAL TEST.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains secondary containment isolation capability.
FREQUENCY 12 hours 92 days SR 3.3.6.2.3             Calibrate the trip unit.                                                 92 days SR 3.3.6.2.4             Perform CHANNEL CALIBRATION.                                             92 days SR 3.3.6.2.5             Perform CHANNEL CALIBRATION.                                             24 months SR 3.3.6.2.6             Perform LOGIC SYSTEM FUNCTIONAL TEST.                                     24 months Monticello                                              3.3.6.2-2                                  Amendment No. 146
SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK.
12 hours SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.6.2.3 Calibrate the trip unit.
92 days SR 3.3.6.2.4 Perform CHANNEL CALIBRATION.
92 days SR 3.3.6.2.5 Perform CHANNEL CALIBRATION.
24 months SR 3.3.6.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months Draft


Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)
Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-3 Amendment No. 146, XXX Table 3.3.6.2-1 (page 1 of 1)
Secondary Containment Isolation Instrumentation APPLICABLE       REQUIRED MODES OR       CHANNELS OTHER            PER SPECIFIED        TRIP     SURVEILLANCE     ALLOWABLE FUNCTION                      CONDITIONS        SYSTEM    REQUIREMENTS      VALUE
Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE
: 1. Reactor Vessel Water Level - Low           1, 2, 3, (a)       2     SR   3.3.6.2.1     -48 inches Low                                                                  SR   3.3.6.2.2 SR   3.3.6.2.3 SR   3.3.6.2.5 SR   3.3.6.2.6
: 1. Reactor Vessel Water Level - Low Low 1, 2, 3, (a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6  
: 2. Drywell Pressure - High                     1, 2, 3         2     SR 3.3.6.2.2         2 psig SR 3.3.6.2.4 SR 3.3.6.2.6
-48 inches
: 3. Reactor Building Ventilation Exhaust       1, 2, 3,          2      SR  3.3.6.2.1    100 mR/hr (a) 4.
: 2. Drywell Pressure - High 1, 2, 3 2
Radiation - High raft Refueling Floor Radiation - High (a), (b) 1, 2, 3, (a), (b) 2 During operations with a potential for draining the reactor vessel.
SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 2 psig
SR SR SR SR SR SR SR 3.3.6.2.2 3.3.6.2.4 3.3.6.2.6 3.3.6.2.1 3.3.6.2.2 3.3.6.2.4 3.3.6.2.6 100 mR/hr (ab) During movement of recently irradiated fuel assemblies in secondary containment.
: 3. Reactor Building Ventilation Exhaust Radiation - High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr
D Monticello                                                  3.3.6.2-3                    Amendment No. 146, XXX
: 4. Refueling Floor Radiation - High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr (a)
During operations with a potential for draining the reactor vessel.
(ab) During movement of recently irradiated fuel assemblies in secondary containment.
Draft


CREF System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1       Control Room Emergency Filtration (CREF) System Instrumentation LCO 3.3.7.1                 The CREF System instrumentation for each Function in Table 3.3.7.1-1 shall be OPERABLE.
CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-1 Amendment No. 146 148 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation LCO 3.3.7.1 The CREF System instrumentation for each Function in Table 3.3.7.1-1 shall be OPERABLE.
APPLICABILITY:               According to Table 3.3.7.1-1 ACTIONS
APPLICABILITY:
According to Table 3.3.7.1-1 ACTIONS  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
Separate Condition entry is allowed for each channel.
CONDITION A. One or more channels inoperable.           raft              A.1 AND A.2 REQUIRED ACTION Declare associated CREF subsystem inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
Place channel in trip.
COMPLETION TIME 1 hour from discovery of loss of CREF initiation capability in both trip systems 12 hours D
B. Required Action and associated Completion Time not met.
B. Required Action and associated Completion Time not met.
B.1 OR B.2 Place the associated CREF subsystem in the pressurization mode of operation.
A.1 Declare associated CREF subsystem inoperable.
Declare associated CREF 1 hour 1 hour subsystem inoperable.
AND A.2 Place channel in trip.
Monticello                                              3.3.7.1-1                           Amendment No. 146 148
B.1 Place the associated CREF subsystem in the pressurization mode of operation.
OR B.2 Declare associated CREF subsystem inoperable.
1 hour from discovery of loss of CREF initiation capability in both trip systems 12 hours 1 hour 1 hour Draft


CREF System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS
CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-2 Amendment No. 146 148 SURVEILLANCE REQUIREMENTS  
-----------------------------------------------------------NOTES----------------------------------------------------------
-----------------------------------------------------------NOTES----------------------------------------------------------
: 1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREF System Function.
: 1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREF System Function.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREF System initiation capability.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREF System initiation capability.
SURVEILLANCE                                                     FREQUENCY SR 3.3.7.1.1             Perform CHANNEL CHECK.                                                   12 hours SR 3.3.7.1.2             Perform CHANNEL FUNCTIONAL TEST.                                         92 days SR 3.3.7.1.3 SR 3.3.7.1.4 SR 3.3.7.1.5 ra Calibrate the trip unit.
SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK.
ft Perform CHANNEL CALIBRATION.
12 hours SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST.
Perform CHANNEL CALIBRATION.
92 days SR 3.3.7.1.3 Calibrate the trip unit.
92 days 92 days 24 months D
92 days SR 3.3.7.1.4 Perform CHANNEL CALIBRATION.
SR 3.3.7.1.6             Perform LOGIC SYSTEM FUNCTIONAL TEST.                                     24 months Monticello                                              3.3.7.1-2                          Amendment No. 146 148
92 days SR 3.3.7.1.5 Perform CHANNEL CALIBRATION.
24 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months Draft


CREF System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (Page 1 of 1)
CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-3 Amendment No. 146, 148, XXX Table 3.3.7.1-1 (Page 1 of 1)
Control Room Emergency Filtration System Instrumentation APPLICABLE MODES OR               REQUIRED OTHER                   CHANNELS SPECIFIED               PER TRIP       SURVEILLANCE ALLOWABLE FUNCTION                               CONDITIONS             SYSTEM         REQUIREMENTS     VALUE
Control Room Emergency Filtration System Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE
: 1. Reactor Vessel Water               1, 2, 3, (a)               2           SR 3.3.7.1.1       - 48 inches Level - Low Low                                                             SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.5 SR 3.3.7.1.6
: 1. Reactor Vessel Water 1, 2, 3, (a) 2 SR 3.3.7.1.1  
: 2. Drywell Pressure -                 1, 2, 3                   2           SR 3.3.7.1.2       2 psig High                                                                       SR 3.3.7.1.4 SR 3.3.7.1.6
- 48 inches Level - Low Low SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.5 SR 3.3.7.1.6
: 3. Reactor Building Ventilation Exhaust Radiation - High
: 2. Drywell Pressure -
: 4. Refueling Floor Radiation - High raft 1, 2, 3, (a), (b) 1, 2, 3, (a), (b) 2 2
1, 2, 3 2
SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.4 SR 3.3.7.1.6 SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.4 SR 3.3.7.1.6 100 mR/hr 100 mR/hr (a)
SR 3.3.7.1.2 2 psig High SR 3.3.7.1.4 SR 3.3.7.1.6
(b)(a)  D During operations with a potential for draining the reactor vessel.
: 3. Reactor Building 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Ventilation Exhaust SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.6
: 4. Refueling Floor 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Radiation - High SR 3.3.7.1.2 SR 3.3.7.1.4 SR 3.3.7.1.6 (a)
During operations with a potential for draining the reactor vessel.
(b)(a)
During movement of recently irradiated fuel assemblies in the secondary containment.
During movement of recently irradiated fuel assemblies in the secondary containment.
Monticello                                                3.3.7.1-3          Amendment No. 146, 148, XXX
Draft


ECCS - Operating 3.5.1 3.5     EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.1         ECCS - Operating LCO 3.5.1                   Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of three safety/relief valves shall be OPERABLE.
ECCS - Operating 3.5.1 Monticello 3.5.1-1 Amendment No. 146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of three safety/relief valves shall be OPERABLE.  
                            ---------------------------------------------NOTE--------------------------------------------
---------------------------------------------NOTE--------------------------------------------
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) shutdown cooling supply isolation interlock in MODE 3, if capable of being manually realigned and not otherwise inoperable.
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) shutdown cooling supply isolation interlock in MODE 3, if capable of being manually realigned and not otherwise inoperable.
APPLICABILITY:
APPLICABILITY:
ACTIONS ra MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS ft  valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.
ACTIONS
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
LCO 3.0.4.b is not applicable to HPCI.
LCO 3.0.4.b is not applicable to HPCI.
D  CONDITION A. One LPCI pump inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One LPCI pump inoperable.
A.1 REQUIRED ACTION Restore LPCI pump to OPERABLE status.
A.1 Restore LPCI pump to OPERABLE status.
COMPLETION TIME 30 days B. One LPCI subsystem                     B.1      Restore low pressure                    7 days inoperable for reasons                           ECCS injection/spray other than Condition A.                          subsystem to OPERABLE status.
30 days B. One LPCI subsystem inoperable for reasons other than Condition A.
OR One Core Spray subsystem inoperable.
OR One Core Spray subsystem inoperable.
Monticello                                                3.5.1-1                         Amendment No. 146, XXX
B.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.
7 days Draft


ECCS - Operating 3.5.1 ACTIONS (continued)
ECCS - Operating 3.5.1 Monticello 3.5.1-2 Amendment No. 146, 162, 184 ACTIONS (continued)
CONDITION                   REQUIRED ACTION                 COMPLETION TIME C. One LPCI pump in both     C.1   Restore one LPCI pump to         7 days LPCI subsystems                  OPERABLE status.
CONDITION REQUIRED ACTION COMPLETION TIME C. One LPCI pump in both LPCI subsystems inoperable.
inoperable.
C.1 Restore one LPCI pump to OPERABLE status.
D. Two LPCI subsystems       D.1   Restore one LPCI                 72 hours inoperable for reasons          subsystem to OPERABLE other than Condition C          status.
7 days D. Two LPCI subsystems inoperable for reasons other than Condition C or G.
or G.
D.1 Restore one LPCI subsystem to OPERABLE status.
E. One Core Spray             E.1  Restore Core Spray              72 hours subsystem inoperable.           subsystem to OPERABLE status.
72 hours E. One Core Spray subsystem inoperable.
AND OR ra One or two LPCI ft One LPCI subsystem inoperable.
AND One LPCI subsystem inoperable.
pump(s) inoperable.
OR One or two LPCI pump(s) inoperable.
OR E.2 OR E.3 Restore LPCI subsystem to OPERABLE status.
E.1 Restore Core Spray subsystem to OPERABLE status.
Restore LPCI pump(s) to OPERABLE status.
OR E.2 Restore LPCI subsystem to OPERABLE status.
72 hours 72 hours D
OR E.3 Restore LPCI pump(s) to OPERABLE status.
F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met.
72 hours 72 hours 72 hours F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met.
F.1 AND F.2 Be in MODE 3.
F.1 Be in MODE 3.
Be in MODE 4.
AND F.2 Be in MODE 4.
12 hours 36 hours G. Two LPCI subsystems       G.1  Isolate the RHR intertie        18 hours inoperable due to open           line.
12 hours 36 hours G. Two LPCI subsystems inoperable due to open RHR intertie return line isolation valve(s).
RHR intertie return line isolation valve(s).
G.1 Isolate the RHR intertie line.
Monticello                              3.5.1-2                Amendment No. 146, 162, 184
18 hours Draft


ECCS - Operating 3.5.1 ACTIONS (continued)
ECCS - Operating 3.5.1 Monticello 3.5.1-3 Amendment No. 146, 162, 176, 184 ACTIONS (continued)
CONDITION                 REQUIRED ACTION               COMPLETION TIME H. Required Action and       H.1   Be in MODE 2.               6 hours associated Completion Time of Condition G not met.
CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and associated Completion Time of Condition G not met.
I. HPCI System             I.1   Verify by administrative     Immediately inoperable.                  means RCIC System is OPERABLE.
H.1 Be in MODE 2.
AND I.2   Restore HPCI System to       14 days OPERABLE status.
6 hours I.
J. HPCI System inoperable.
HPCI System inoperable.
AND raft Condition A, B, or C entered.
I.1 Verify by administrative means RCIC System is OPERABLE.
J.1 OR J.2 Restore HPCI System to OPERABLE status.
AND I.2 Restore HPCI System to OPERABLE status.
Restore low pressure ECCS injection/spray subsystem(s) to 72 hours 72 hours OPERABLE status.
Immediately 14 days J.
D K. One ADS valve inoperable.
HPCI System inoperable.
K.1   Restore ADS valve to OPERABLE status.
AND Condition A, B, or C entered.
14 days Monticello                            3.5.1-3        Amendment No. 146, 162, 176, 184
J.1 Restore HPCI System to OPERABLE status.
OR J.2 Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.
72 hours 72 hours K. One ADS valve inoperable.
K.1 Restore ADS valve to OPERABLE status.
14 days Draft


ECCS - Operating 3.5.1 ACTIONS (continued)
ECCS - Operating 3.5.1 Monticello 3.5.1-4 Amendment No. 146, 162, 176, 184 ACTIONS (continued)
CONDITION                   REQUIRED ACTION               COMPLETION TIME L. Required Action and         L.1  Be in MODE 3.                12 hours associated Completion Time of Condition I, J,     AND or K not met.
CONDITION REQUIRED ACTION COMPLETION TIME L. Required Action and associated Completion Time of Condition I, J, or K not met.
L.2  Reduce reactor steam        36 hours OR                               dome pressure to 150 psig.
OR One ADS valve inoperable and Condition A, B, C, D, or G entered.
One ADS valve inoperable and Condition A, B, C, D, or G entered.
OR Two or more ADS valves inoperable.
OR inoperable.
OR HPCI System inoperable and Condition D, E, or G entered.
OR ra Two or more ADS valves ft HPCI System inoperable and Condition D, E, or G entered.
L.1 Be in MODE 3.
M. Two or more low            M.1   Enter LCO 3.0.3.             Immediately D
AND L.2 Reduce reactor steam dome pressure to 150 psig.
pressure ECCS injection/spray subsystems inoperable for reasons other than Condition C, D, E, or G.
12 hours 36 hours M. Two or more low pressure ECCS injection/spray subsystems inoperable for reasons other than Condition C, D, E, or G.
OR HPCI System and one or more ADS valves inoperable.
OR HPCI System and one or more ADS valves inoperable.
Monticello                              3.5.1-4          Amendment No. 146, 162, 176, 184
M.1 Enter LCO 3.0.3.
Immediately Draft


ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                                   FREQUENCY SR 3.5.1.1   Verify, for each ECCS injection/spray subsystem,                       31 days locations susceptible to gas accumulation are sufficiently filled with water.
ECCS - Operating 3.5.1 Monticello 3.5.1-5 Amendment No. 146, 155, 162, 189, 190 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
SR 3.5.1.2   -------------------------------NOTE------------------------------
31 days SR 3.5.1.2  
-------------------------------NOTE------------------------------
Not required to be met for system vent flow paths opened under administrative control.
Not required to be met for system vent flow paths opened under administrative control.
Verify each ECCS injection/spray subsystem                             31 days manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.1.3 ra Verify ADS pneumatic pressure is as follows for a.
31 days SR 3.5.1.3 Verify ADS pneumatic pressure is as follows for each required ADS pneumatic supply:
b.
: a. S/RV Accumulator Bank header pressure 88.3 psig; and
ft each required ADS pneumatic supply:
: b. Alternate Nitrogen System pressure is 1060 psig.
S/RV Accumulator Bank header pressure 88.3 psig; and Alternate Nitrogen System pressure is 1060 psig.
31 days SR 3.5.1.4  
31 days D
-------------------------------NOTE------------------------------
SR 3.5.1.4   -------------------------------NOTE------------------------------
Only required to be met in MODE 1.
Only required to be met in MODE 1.
Verify the RHR System intertie return line isolation valves are closed.
Verify the RHR System intertie return line isolation valves are closed.
31 days SR 3.5.1.5   Verify correct breaker alignment to the LPCI swing                     31 days bus.
31 days SR 3.5.1.5 Verify correct breaker alignment to the LPCI swing bus.
SR 3.5.1.6   Verify each recirculation pump discharge valve                         In accordance cycles through one complete cycle of full travel or is                 with the Inservice de-energized in the closed position.                                   Testing Program Monticello                                  3.5.1-5      Amendment No. 146, 155, 162, 189, 190
31 days SR 3.5.1.6 Verify each recirculation pump discharge valve cycles through one complete cycle of full travel or is de-energized in the closed position.
In accordance with the Inservice Testing Program Draft


ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
ECCS - Operating 3.5.1 Monticello 3.5.1-6 Amendment No. 146, 162, 167 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                                                   FREQUENCY SR 3.5.1.7   Verify the following ECCS pumps develop the                             In accordance specified flow rate against a system head                               with the Inservice corresponding to the specified reactor to                               Testing Program containment pressure.
SURVEILLANCE FREQUENCY SR 3.5.1.7 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor to containment pressure.
System Head Corresponding to a Reactor to No. of         Containment System       Flow Rate         Pumps         Pressure of Core Spray         2835 gpm             1           130 psi SR 3.5.1.8 ra LPCI ft 3870 gpm            1          20 psi
System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of Core Spray 2835 gpm 1 130 psi LPCI 3870 gpm 1 20 psi In accordance with the Inservice Testing Program SR 3.5.1.8  
              -------------------------------NOTE------------------------------
-------------------------------NOTE------------------------------
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor steam dome pressure                               In accordance 1025.3 psig and 950 psig, the HPCI pump can                         with the Inservice D
Verify, with reactor steam dome pressure 1025.3 psig and 950 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.
SR 3.5.1.9 develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.
In accordance with the Inservice Testing Program SR 3.5.1.9
              -------------------------------NOTE------------------------------
-------------------------------NOTE------------------------------
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Testing Program Verify, with reactor pressure 165 psig, the HPCI                     24 months pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.
Verify, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.
Monticello                                    3.5.1-6                    Amendment No. 146, 162, 167
24 months Draft


ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)
ECCS - Operating 3.5.1 Monticello 3.5.1-7 Amendment No. 146, 162, 168 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                                                   FREQUENCY SR 3.5.1.10   -------------------------------NOTE------------------------------
SURVEILLANCE FREQUENCY SR 3.5.1.10  
-------------------------------NOTE------------------------------
Vessel injection/spray may be excluded.
Vessel injection/spray may be excluded.
Verify each ECCS injection/spray subsystem                             24 months actuates on an actual or simulated automatic initiation signal.
Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.
SR 3.5.1.11   -------------------------------NOTE------------------------------
24 months SR 3.5.1.11  
-------------------------------NOTE------------------------------
Valve actuation may be excluded.
Valve actuation may be excluded.
Verify the ADS actuates on an actual or simulated                       24 months SR 3.5.1.12 ra automatic initiation signal.
Verify the ADS actuates on an actual or simulated automatic initiation signal.
ft
24 months SR 3.5.1.12  
              -------------------------------NOTE------------------------------
-------------------------------NOTE------------------------------
Not required to be performed until 12 hours after reactor steam flow is adequate to perform the test.
Not required to be performed until 12 hours after reactor steam flow is adequate to perform the test.
Verify each ADS valve is capable of being opened.                       In accordance with the Inservice Testing Program D
Verify each ADS valve is capable of being opened.
SR 3.5.1.13   Verify automatic transfer capability of the LPCI swing bus power supply from the normal source to the backup source.
In accordance with the Inservice Testing Program SR 3.5.1.13 Verify automatic transfer capability of the LPCI swing bus power supply from the normal source to the backup source.
24 months Monticello                                    3.5.1-7                    Amendment No. 146, 162, 168
24 months Draft


ECCS - Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.2       RPV Water Inventory Control ECCS - Shutdown LCO 3.5.2             DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours.
ECCS - Shutdown 3.5.2 Monticello 3.5.2-1 Amendment No. 146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.2 RPV Water Inventory Control ECCS - Shutdown LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours.
AND OneTwo low pressure ECCS injection/spray subsystems shall be OPERABLE.
AND OneTwo low pressure ECCS injection/spray subsystems shall be OPERABLE.  
                      ---------------------------------------------NOTE--------------------------------------------
---------------------------------------------NOTE--------------------------------------------
A One Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
A One Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
APPLICABILITY:     ra--------------------------------------------------------------------------------------------------
APPLICABILITY:
ft MODE 4 ,
MODE 4,
MODE and 5
MODE and 5
, except with the spent fuel storage pool gates removed and water level 21 ft 11 inches over the top of the reactor pressure vessel flange.
, except with the spent fuel storage pool gates removed and water level 21 ft 11 inches over the top of the reactor pressure vessel flange.
ACTIONS DCONDITION A. One rRequired ECCS injection/spray subsystem inoperable.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rRequired ECCS injection/spray subsystem inoperable.
A.1 REQUIRED ACTION Restore required ECCS injection/spray subsystem to OPERABLE status.
A.1 Restore required ECCS injection/spray subsystem to OPERABLE status.
COMPLETION TIME 4 hours B. Required Action and             B.1       Initiate action to establish a           Immediately associated Completion                      method of water injection Time of Condition A not                    capable of operating met.                                      without offsite electrical power.
4 hours B. Required Action and associated Completion Time of Condition A not met.
B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power.
Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
C. DRAIN TIME < 36 hours           C.1       Verify secondary                         4 hours Monticello                                        3.5.2-1                          Amendment No. 146, XXX
Immediately C. DRAIN TIME < 36 hours C.1 Verify secondary 4 hours Draft


ECCS - Shutdown 3.5.2 ACTIONS (continued) and 8 hours.                 containment boundary is capable of being C. Two required ECCS              established in less than the injection/spray                DRAIN TIME.
ECCS - Shutdown 3.5.2 ACTIONS (continued)
subsystems inoperable.
Monticello 3.5.2-2 Amendment No. 146, XXX and 8 hours.
AND C.2   Verify each secondary                   4 hours containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
C. Two required ECCS injection/spray subsystems inoperable.
AND C.3   Verify one standby gas                   4 hours raft      C.1 AND treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
containment boundary is capable of being established in less than the DRAIN TIME.
Initiate action to suspend OPDRVs.
AND C.2 Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
Immediately 4 hours C.2   Restore one required D
AND C.3 Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.
D. DRAIN TIME < 8 hours. D.1 ECCS injection/spray subsystem to OPERABLE status.
C.1 Initiate action to suspend OPDRVs.
                                  ----------- NOTE ---------------
AND C.2 Restore one required ECCS injection/spray subsystem to OPERABLE status.
Required ECCS injection/spray subsystem or additional method of Immediately water injection shall be capable of operating without offsite electrical power.
4 hours 4 hours Immediately 4 hours D. DRAIN TIME < 8 hours.
Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours.
D.1  
Monticello                            3.5.2-2                            Amendment No. 146, XXX
----------- NOTE ---------------
Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.
Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours.
Immediately Draft


ECCS - Shutdown 3.5.2 ACTIONS (continued)
ECCS - Shutdown 3.5.2 ACTIONS (continued)
AND D.2   Initiate action to establish     Immediately secondary containment boundary.
Monticello 3.5.2-3 Amendment No. 146, XXX AND D.2 Initiate action to establish secondary containment boundary.
AND D.3   Initiate action to isolate       Immediately each secondary containment penetration flow path or verify it can be manually isolated from the control room.
AND D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.
AND raft E. Required Action and associated Completion Time of Condition C or D D.4 E.1 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.
AND D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.
Initiate action to restore DRAIN TIME to  36 hours.
Immediately Immediately Immediately E. Required Action and associated Completion Time of Condition C or D not met.
Immediately Immediately not met.
OR DRAIN TIME < 1 hour.
D OR DRAIN TIME < 1 hour.
E.1 Initiate action to restore DRAIN TIME to 36 hours.
Monticello                              3.5.2-3                      Amendment No. 146, XXX
Immediately Draft


ECCS - Shutdown 3.5.2 ACTIONS (continued)
ECCS - Shutdown 3.5.2 ACTIONS (continued)
ACTIONS (continued)
Monticello 3.5.2-4 Amendment No. 146, XXX ACTIONS (continued)
CONDITION                         REQUIRED ACTION                           COMPLETION TIME D. Required Action C.2 and         D.1Initiate action to restore               Immediately associated Completion                secondary containment to Time not met.                        OPERABLE status.
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and associated Completion Time not met.
AND D.2       Initiate action to restore one         Immediately standby gas treatment subsystem to OPERABLE status.
D.1Initiate action to restore secondary containment to OPERABLE status.
AND D.3       Initiate action to restore             Immediately raft SURVEILLANCE REQUIREMENTS isolation capability in each required secondary containment penetration flow path not isolated.
AND D.2 Initiate action to restore one standby gas treatment subsystem to OPERABLE status.
SURVEILLANCE                                                 FREQUENCY D
AND D.3 Initiate action to restore isolation capability in each required secondary containment penetration flow path not isolated.
SR 3.5.2.1 SR 3.5.2.21 Verify DRAIN TIME  36 hours.
Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours.
Verify, for each a required ECCS injection/spray subsystem, the:
12 hours SR 3.5.2.21 Verify, for each a required ECCS injection/spray subsystem, the:
12 hours 12 hours
: a. Suppression pool water level is -3 ft; or
: a. Suppression pool water level is -3 ft; or
: b.  
: b.           ---------------------------NOTE--------------------
---------------------------NOTE--------------------
Only one required ECCS injection/spray subsystem may take credit for this option during OPDRVs.
Only one required ECCS injection/spray subsystem may take credit for this option during OPDRVs.
Condensate storage tank(s) water level is 7 ft for one tank operation and 4 ft for two tank operation.
Condensate storage tank(s) water level is 7 ft for one tank operation and 4 ft for two tank operation.
Monticello                                    3.5.2-4                        Amendment No. 146, XXX
12 hours Draft


ECCS - Shutdown 3.5.2 ACTIONS (continued)
ECCS - Shutdown 3.5.2 ACTIONS (continued)
SURVEILLANCE                                     FREQUENCY SR 3.5.2.3     Verify, for the required ECCS injection/spray           31 days subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
Monticello 3.5.2-5 Amendment No. 146, XXX SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
raft D
31 days Draft
Monticello                                3.5.2-5                  Amendment No. 146, XXX


ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
ECCS - Shutdown 3.5.2 Monticello 3.5.2-6 Amendment No. 146, 167, 189, 194, XXX SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                                                   FREQUENCY SR 3.5.2.2       Verify, for each required ECCS injection/spray                         31 days subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
SR 3.5.2.43       -------------------------------NOTE------------------------------
31 days SR 3.5.2.43  
-------------------------------NOTE------------------------------
Not required to be met for system vent flow paths opened under administrative control.
Not required to be met for system vent flow paths opened under administrative control.
Verify for each the required ECCS injection/spray                       31 days subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the SR 3.5.2.54 ra correct position.
Verify for each the required ECCS injection/spray subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
ft Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes.
31 days SR 3.5.2.54 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes.
Verify each required ECCS pump develops the specified flow rate against a system head corresponding to the specified reactor to containment pressure.
Verify each required ECCS pump develops the specified flow rate against a system head corresponding to the specified reactor to containment pressure.
In accordance with the INSERVICE TESTING PROGRAM 92 days System Head D            System Core Spray Corresponding to a Reactor to No. of Containment Flow Rate 2835 gpm Pumps Pressure of 1     130 psi LPCI         3870 gpm             1     20 psi SR 3.5.2.6       Verify each valve credited for automatically isolating                 24 months a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.
System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of Core Spray 2835 gpm 1
SR 3.5.2.75       -------------------------------NOTE------------------------------
130 psi LPCI 3870 gpm 1
20 psi In accordance with the INSERVICE TESTING PROGRAM 92 days SR 3.5.2.6 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.
24 months SR 3.5.2.75  
-------------------------------NOTE------------------------------
Vessel injection/spray may be excluded.
Vessel injection/spray may be excluded.
Verify the each required ECCS injection/spray Monticello                                        3.5.2-6      Amendment No. 146, 167, 189, 194, XXX
Verify the each required ECCS injection/spray Draft


ECCS - Shutdown 3.5.2 SURVEILLANCE                                  FREQUENCY subsystem operates actuates on a manual an actual  24 months or simulated automatic initiation signal.
ECCS - Shutdown 3.5.2 Monticello 3.5.2-7 Amendment No. 146, 167, 189, 194, XXX SURVEILLANCE FREQUENCY subsystem operates actuates on a manual an actual or simulated automatic initiation signal.
raft D
24 months Draft
Monticello                         3.5.2-7   Amendment No. 146, 167, 189, 194, XXX


RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.3         RCIC System LCO 3.5.3                   The RCIC System shall be OPERABLE.
RCIC System 3.5.3 Monticello 3.5.3-1 Amendment No. 146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.
APPLICABILITY:               MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
APPLICABILITY:
ACTIONS
MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
ACTIONS  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
LCO 3.0.4.b is not applicable to the RCIC System.
LCO 3.0.4.b is not applicable to the RCIC System.
CONDITION A. RCIC System inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.
raft              A.1 AND REQUIRED ACTION Verify by administrative means High Pressure Coolant Injection System is OPERABLE.
A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE.
COMPLETION TIME Immediately D
AND A.2 Restore RCIC System to OPERABLE status.
B. Required Action and associated Completion Time not met.
Immediately 14 days B. Required Action and associated Completion Time not met.
A.2 B.1 AND Restore RCIC System to OPERABLE status.
B.1 Be in MODE 3.
Be in MODE 3.
AND B.2 Reduce reactor steam dome pressure to 150 psig.
14 days 12 hours B.2       Reduce reactor steam                     36 hours dome pressure to 150 psig.
12 hours 36 hours Draft
Monticello                                                3.5.3-1                          Amendment No. 146, XXX


RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                                   FREQUENCY SR 3.5.3.1   -------------------------------NOTE------------------------------
RCIC System 3.5.3 Monticello 3.5.3-2 Amendment No. 146, 189 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1  
-------------------------------NOTE------------------------------
Not required to be met for system vent flow paths opened under administrative control.
Not required to be met for system vent flow paths opened under administrative control.
Verify each RCIC System manual, power operated,                         31 days and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
SR 3.5.3.2   -------------------------------NOTE------------------------------
31 days SR 3.5.3.2  
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to ra perform the test.
-------------------------------NOTE------------------------------
ft Verify, with reactor pressure 1025.3 psig and 950 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
In accordance with the Inservice Testing Program SR 3.5.3.3   -------------------------------NOTE------------------------------
Verify, with reactor pressure 1025.3 psig and 950 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.
Not required to be performed until 12 hours after D      reactor steam pressure and flow are adequate to perform the test.
In accordance with the Inservice Testing Program SR 3.5.3.3  
Verify, with reactor pressure 165 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.
-------------------------------NOTE------------------------------
24 months SR 3.5.3.4   -------------------------------NOTE------------------------------
Not required to be performed until 12 hours after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure 165 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.
24 months SR 3.5.3.4  
-------------------------------NOTE------------------------------
Vessel injection may be excluded.
Vessel injection may be excluded.
Verify the RCIC System actuates on an actual or                         24 months simulated automatic initiation signal.
Verify the RCIC System actuates on an actual or simulated automatic initiation signal.
SR 3.5.3.5   Verify the RCIC System locations susceptible to gas                     31 days accumulation are sufficiently filled with water.
24 months SR 3.5.3.5 Verify the RCIC System locations susceptible to gas accumulation are sufficiently filled with water.
Monticello                                  3.5.3-2                          Amendment No. 146, 189
31 days Draft


PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3       Primary Containment Isolation Valves (PCIVs)
PCIVs 3.6.1.3 Monticello 3.6.1.3-1 Amendment No. 146 148 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
LCO 3.6.1.3                 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.
LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.
APPLICABILITY:               MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."
APPLICABILITY:
ACTIONS
MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."
ACTIONS  
-----------------------------------------------------------NOTES----------------------------------------------------------
-----------------------------------------------------------NOTES----------------------------------------------------------
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 1.
2.
Penetration flow paths may be unisolated intermittently under administrative controls.
3.
: 2.
: 4.                        ra Separate Condition entry is allowed for each penetration flow path.
Separate Condition entry is allowed for each penetration flow path.
: 3.
Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
ft Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment,"
: 4.
Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment,"
when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.
when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.
CONDITION                                 REQUIRED ACTION                           COMPLETION TIME D
CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------
A. ------------NOTE------------
Only applicable to penetration flow paths with two PCIVs.
Only applicable to penetration flow paths with two PCIVs.
A.1       Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve 4 hours except for main steam line AND 8 hours for main One or more penetration                        with flow through the valve              steam line flow paths with one                            secured.
One or more penetration flow paths with one PCIV inoperable for reasons other than Condition D or E.
PCIV inoperable for reasons other than                  AND Condition D or E.
A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.
Monticello                                              3.6.1.3-1                            Amendment No. 146 148
AND 4 hours except for main steam line AND 8 hours for main steam line Draft


PCIVs 3.6.1.3 ACTIONS (continued)
PCIVs 3.6.1.3 Monticello 3.6.1.3-2 Amendment No. 146 ACTIONS (continued)
CONDITION         REQUIRED ACTION                         COMPLETION TIME A.2   --------------NOTES-------------
CONDITION REQUIRED ACTION COMPLETION TIME A.2  
--------------NOTES-------------
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected                     Once per 31 days for raft penetration flow path is isolated.
Verify the affected penetration flow path is isolated.
isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in D                                                            MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Monticello                    3.6.1.3-2                              Amendment No. 146
Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Draft


PCIVs 3.6.1.3 ACTIONS (continued)
PCIVs 3.6.1.3 Monticello 3.6.1.3-3 Amendment No. 146 148 ACTIONS (continued)
CONDITION                         REQUIRED ACTION               COMPLETION TIME B. ------------NOTE------------       B.1  Isolate the affected          1 hour Only applicable to                       penetration flow path by penetration flow paths                   use of at least one closed with two PCIVs.                          and de-activated automatic
CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------
    ---------------------------------        valve, closed manual valve, or blind flange.
Only applicable to penetration flow paths with two PCIVs.
One or more penetration flow paths with two PCIVs inoperable for reasons other than Condition D or E.
One or more penetration flow paths with two PCIVs inoperable for reasons other than Condition D or E.
C. ------------NOTE------------       C.1  Isolate the affected          4 hours except for Only applicable to with only one PCIV.
B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
ra penetration flow paths ft One or more penetration flow paths with one PCIV inoperable.
1 hour C. ------------NOTE------------
penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
Only applicable to penetration flow paths with only one PCIV.
excess flow check valves (EFCVs) and penetrations with a closed system AND 72 hours for EFCVs and penetrations with a closed system D                                AND Monticello                                      3.6.1.3-3                  Amendment No. 146 148
One or more penetration flow paths with one PCIV inoperable.
C.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND 4 hours except for excess flow check valves (EFCVs) and penetrations with a closed system AND 72 hours for EFCVs and penetrations with a closed system Draft


PCIVs 3.6.1.3 ACTIONS (continued)
PCIVs 3.6.1.3 Monticello 3.6.1.3-4 Amendment No. 146 ACTIONS (continued)
CONDITION         REQUIRED ACTION                         COMPLETION TIME C.2   --------------NOTES-------------
CONDITION REQUIRED ACTION COMPLETION TIME C.2  
--------------NOTES-------------
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected                     Once per 31 days for raft penetration flow path is isolated.
Verify the affected penetration flow path is isolated.
isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in D                                                            MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Monticello                    3.6.1.3-4                              Amendment No. 146
Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Draft


PCIVs 3.6.1.3 ACTIONS (continued)
PCIVs 3.6.1.3 Monticello 3.6.1.3-5 Amendment No. 146 148 ACTIONS (continued)
CONDITION                   REQUIRED ACTION                         COMPLETION TIME D. One or more penetration   D.1   Isolate the affected                     24 hours flow paths with one or          penetration flow path by more 18 inch primary            use of at least one closed containment purge and            and de-activated automatic vent valves not within          valve, closed manual valve, purge and vent valve            or blind flange.
CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration flow paths with one or more 18 inch primary containment purge and vent valves not within purge and vent valve leakage limits.
leakage limits.
D.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND D.2   --------------NOTES-------------
AND D.2  
--------------NOTES-------------
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
raft
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected penetration flow path is Once per 31 days for isolation devices isolated.                                outside containment D
Verify the affected penetration flow path is isolated.
E. One or more MSIVs with leakage rate not within limits.
24 hours Once per 31 days for isolation devices outside containment E. One or more MSIVs with leakage rate not within limits.
E.1 Restore leakage rate to within limits.
E.1 Restore leakage rate to within limits.
8 hours F. Required Action and       F.1    Be in MODE 3.                            12 hours associated Completion Time of Condition A, B,   AND C, or D not met in MODE 1, 2, or 3.         F.2   Be in MODE 4.                           36 hours Monticello                            3.6.1.3-5                            Amendment No. 146 148
8 hours F. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3.
F.1 Be in MODE 3.
AND F.2 Be in MODE 4.
12 hours 36 hours Draft


PCIVs 3.6.1.3 ACTIONS (continued)
PCIVs 3.6.1.3 Monticello 3.6.1.3-6 Amendment No. 146, 148, XXX ACTIONS (continued)
CONDITION                           REQUIRED ACTION                               COMPLETION TIME G. Required Action and           G.1        Initiate action to suspend              Immediately associated Completion                     operations with a potential Time of Condition A or B                 for draining the reactor not met for PCIV(s)                       vessel (OPDRVs).
CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and associated Completion Time of Condition A or B not met for PCIV(s) required to be OPERABLE during MODE 4 or 5.
required to be OPERABLE during               OR MODE 4 or 5.
G.1 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
G.12       Initiate action to restore               Immediately valve(s) to OPERABLE status.
OR G.12 Initiate action to restore valve(s) to OPERABLE status.
SR 3.6.1.3.1 ra SURVEILLANCE REQUIREMENTS ft      SURVEILLANCE
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1  
                  ------------------------------NOTE------------------------------
------------------------------NOTE------------------------------
Not required to be met when the 18 inch primary containment purge and vent valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or FREQUENCY Surveillances that require the valves to be open.
Not required to be met when the 18 inch primary containment purge and vent valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.
D            ---------------------------------------------------------------------
Verify each 18 inch primary containment purge and vent valve is closed.
Verify each 18 inch primary containment purge and vent valve is closed.
31 days Monticello                                      3.6.1.3-6                  Amendment No. 146, 148, XXX
31 days Draft


PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
PCIVs 3.6.1.3 Monticello 3.6.1.3-7 Amendment No. 146 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                                                   FREQUENCY SR 3.6.1.3.2   ------------------------------NOTES-----------------------------
SURVEILLANCE FREQUENCY SR 3.6.1.3.2  
------------------------------NOTES-----------------------------
: 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
: 2. Not required to be met for PCIVs that are open under administrative controls.
Verify each primary containment isolation manual valve and blind flange that is located outside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.
31 days SR 3.6.1.3.3
------------------------------NOTES-----------------------------
: 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
: 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
: 2. Not required to be met for PCIVs that are open under administrative controls.
: 2. Not required to be met for PCIVs that are open under administrative controls.
Verify each primary containment isolation manual                        31 days valve and blind flange that is located outside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.
Verify each primary containment manual isolation valve and blind flange that is located inside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.
SR 3.6.1.3.3 ra
Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge.
                ------------------------------NOTES-----------------------------
31 days SR 3.6.1.3.5 Verify the isolation time of each power operated automatic PCIV, except for MSIVs, is within limits.
: 1. Valves and blind flanges in high radiation areas 2.
24 months Draft
ft  may be verified by use of administrative means.
Not required to be met for PCIVs that are open under administrative controls.
Verify each primary containment manual isolation                        Prior to entering valve and blind flange that is located inside primary                  MODE 2 or 3 from D        containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.
MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4   Verify continuity of the traversing incore probe (TIP)                 31 days shear isolation valve explosive charge.
SR 3.6.1.3.5   Verify the isolation time of each power operated                       24 months automatic PCIV, except for MSIVs, is within limits.
Monticello                                    3.6.1.3-7                                Amendment No. 146


PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)
PCIVs 3.6.1.3 Monticello 3.6.1.3-8 Amendment No. 146 148, 176 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE                                     FREQUENCY SR 3.6.1.3.6     Verify the isolation time of each MSIV is               24 months 3 seconds and 9.9 seconds.
SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is 3 seconds and 9.9 seconds.
SR 3.6.1.3.7     Verify each automatic PCIV actuates to the isolation   24 months position on an actual or simulated isolation signal.
24 months SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation position on an actual or simulated isolation signal.
SR 3.6.1.3.8     Verify each reactor instrumentation line EFCV           24 months actuates on a simulated instrument line break to restrict flow to 2 gpm.
24 months SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV actuates on a simulated instrument line break to restrict flow to 2 gpm.
SR 3.6.1.3.9     Verify each 18 inch primary containment purge and       24 months SR 3.6.1.3.10  ra vent valve is blocked to restrict the valve from opening > 40&deg;.
24 months SR 3.6.1.3.9 Verify each 18 inch primary containment purge and vent valve is blocked to restrict the valve from opening > 40&deg;.
ft Remove and test the explosive squib from each shear isolation valve of the TIP System.
24 months SR 3.6.1.3.10 Remove and test the explosive squib from each shear isolation valve of the TIP System.
24 months on a STAGGERED TEST BASIS SR 3.6.1.3.11   Perform leakage rate testing for each 18 inch primary   In accordance containment purge and vent valve with resilient seals. with the Primary D
24 months on a STAGGERED TEST BASIS SR 3.6.1.3.11 Perform leakage rate testing for each 18 inch primary containment purge and vent valve with resilient seals.
SR 3.6.1.3.12   Verify leakage rate through each MSIV is:
In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify leakage rate through each MSIV is:
(a) 100 scfh when tested at 44.1 psig (Pa); or Containment Leakage Rate Testing Program In accordance with the Primary Containment (b) 75.3 scfh when tested at 25 psig.               Leakage Rate Testing Program SR 3.6.1.3.13   Verify leakage rate through the main steam pathway       In accordance is:                                                     with the Primary (a) 200 scfh when tested at 44.1 psig (Pa); or       Containment (b) 150.6 scfh when tested at 25 psig.               Leakage Rate Testing Program Monticello                              3.6.1.3-8              Amendment No. 146 148, 176
(a) 100 scfh when tested at 44.1 psig (Pa); or (b) 75.3 scfh when tested at 25 psig.
In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.13 Verify leakage rate through the main steam pathway is:
(a) 200 scfh when tested at 44.1 psig (Pa); or (b) 150.6 scfh when tested at 25 psig.
In accordance with the Primary Containment Leakage Rate Testing Program Draft


Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1     Secondary Containment LCO 3.6.4.1           The secondary containment shall be OPERABLE.
Secondary Containment 3.6.4.1 Monticello 3.6.4.1-1 Amendment No. 146, XXX 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.
APPLICABILITY:       MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
APPLICABILITY:
ACTIONS CONDITION                     REQUIRED ACTION                           COMPLETION TIME 2, or 3.        ra A. Secondary containment ft inoperable in MODE 1, B. Required Action and associated Completion Time of Condition A not A.1 B.1 AND Restore secondary containment to OPERABLE status.
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
Be in MODE 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment inoperable in MODE 1, 2, or 3.
4 hours 12 hours met.
A.1 Restore secondary containment to OPERABLE status.
D C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the B.2 C.1 Be in MODE 4.
4 hours B. Required Action and associated Completion Time of Condition A not met.
                                        ---------------NOTE--------------
B.1 Be in MODE 3.
AND B.2 Be in MODE 4.
12 hours 36 hours C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
C.1  
---------------NOTE--------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
Suspend movement of 36 hours Immediately secondary containment              recently irradiated fuel or during OPDRVs.                  assemblies in the secondary containment.
Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND C.2     Initiate action to suspend               Immediately OPDRVs.
AND C.2 Initiate action to suspend OPDRVs.
Monticello                                3.6.4.1-1                            Amendment No. 146, XXX
Immediately Immediately Draft


Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                     FREQUENCY SR 3.6.4.1.1   Verify secondary containment vacuum is 0.25 inch   24 hours of vacuum water gauge.
Secondary Containment 3.6.4.1 Monticello 3.6.4.1-2 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge.
SR 3.6.4.1.2   Verify all secondary containment equipment hatches   31 days are closed and sealed.
24 hours SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.
SR 3.6.4.1.3   Verify one secondary containment access door in       31 days each access opening is closed.
31 days SR 3.6.4.1.3 Verify one secondary containment access door in each access opening is closed.
SR 3.6.4.1.4   Verify the secondary containment can be               24 months on a maintained 0.25 inch of vacuum water gauge for     STAGGERED ra 1 hour using one SGT subsystem at a flow rate 4000 cfm.
31 days SR 3.6.4.1.4 Verify the secondary containment can be maintained 0.25 inch of vacuum water gauge for 1 hour using one SGT subsystem at a flow rate 4000 cfm.
ft TEST BASIS for each SGT subsystem D
24 months on a STAGGERED TEST BASIS for each SGT subsystem Draft
Monticello                          3.6.4.1-2                        Amendment No. 146


SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2       Secondary Containment Isolation Valves (SCIVs)
SCIVs 3.6.4.2 Monticello 3.6.4.2-1 Amendment No. 146, XXX 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)
LCO 3.6.4.2                 Each SCIV shall be OPERABLE.
LCO 3.6.4.2 Each SCIV shall be OPERABLE.
APPLICABILITY:               MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
APPLICABILITY:
ACTIONS
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS  
-----------------------------------------------------------NOTES----------------------------------------------------------
-----------------------------------------------------------NOTES----------------------------------------------------------
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
: 1.
2.
Penetration flow paths may be unisolated intermittently under administrative controls.
ra Separate Condition entry is allowed for each penetration flow path.
: 2.
ft
Separate Condition entry is allowed for each penetration flow path.
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.
: 3.
CONDITION                                 REQUIRED ACTION                           COMPLETION TIME A. One or more penetration                 A.1        Isolate the affected                    8 hours D
Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.
flow paths with one SCIV inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration flow paths with one SCIV inoperable.
AND penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
Monticello                                              3.6.4.2-1                          Amendment No. 146, XXX
AND 8 hours Draft


SCIVs 3.6.4.2 ACTIONS (continued)
SCIVs 3.6.4.2 Monticello 3.6.4.2-2 Amendment No. 146 ACTIONS (continued)
CONDITION                         REQUIRED ACTION                         COMPLETION TIME A.2   --------------NOTES-------------
CONDITION REQUIRED ACTION COMPLETION TIME A.2  
--------------NOTES-------------
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected                     Once per 31 days Only applicable to ra penetration flow paths ft B. ------------NOTE------------
Verify the affected penetration flow path is isolated.
with two isolation valves.
Once per 31 days B. ------------NOTE------------
B.1 penetration flow path is isolated.
Only applicable to penetration flow paths with two isolation valves.
Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
One or more penetration flow paths with two SCIVs inoperable.
4 hours One or more penetration D
B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
flow paths with two SCIVs inoperable.
4 hours C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.
C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, C.1 AND Be in MODE 3.                           12 hours or 3.                              C.2   Be in MODE 4.                           36 hours Monticello                                      3.6.4.2-2                              Amendment No. 146
C.1 Be in MODE 3.
AND C.2 Be in MODE 4.
12 hours 36 hours Draft


SCIVs 3.6.4.2 ACTIONS (continued)
SCIVs 3.6.4.2 Monticello 3.6.4.2-3 Amendment No.146, XXX ACTIONS (continued)
CONDITION                           REQUIRED ACTION                               COMPLETION TIME D. Required Action and           D.1       ---------------NOTE--------------
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
associated Completion                    LCO 3.0.3 is not applicable.
D.1  
Time of Condition A or B                  -------------------------------------
---------------NOTE--------------
not met during movement of recently                      Suspend movement of                     Immediately irradiated fuel                          recently irradiated fuel assemblies in the                         assemblies in the secondary containment                    secondary containment.
LCO 3.0.3 is not applicable.
or during OPDRVs.
Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND D.2       Initiate action to suspend               Immediately OPDRVs.
AND D.2 Initiate action to suspend OPDRVs.
SR 3.6.4.2.1 raft SURVEILLANCE REQUIREMENTS SURVEILLANCE
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1  
                  ------------------------------NOTES-----------------------------
------------------------------NOTES-----------------------------
: 1. Valves and blind flanges in high radiation areas FREQUENCY may be verified by use of administrative means.
: 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
D            2. Not required to be met for SCIVs that are open under administrative controls.
: 2. Not required to be met for SCIVs that are open under administrative controls.
Verify each secondary containment isolation manual valve and blind flange that is not locked, sealed, or otherwise secured and is required to be closed 31 days during accident conditions is closed.
Verify each secondary containment isolation manual valve and blind flange that is not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.
SR 3.6.4.2.2     Verify the isolation time of each power operated,                         92 days automatic SCIV is within limits.
31 days SR 3.6.4.2.2 Verify the isolation time of each power operated, automatic SCIV is within limits.
SR 3.6.4.2.3     Verify each automatic SCIV actuates to the isolation                     24 months position on an actual or simulated actuation signal.
92 days SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation position on an actual or simulated actuation signal.
Monticello                                      3.6.4.2-3                            Amendment No.146, XXX
24 months Draft


SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3     Standby Gas Treatment (SGT) System LCO 3.6.4.3           Two SGT subsystems shall be OPERABLE.
SGT System 3.6.4.3 Monticello 3.6.4.3-1 Amendment No. 146, XXX 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.
APPLICABILITY:       MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
APPLICABILITY:
ACTIONS CONDITION                       REQUIRED ACTION                           COMPLETION TIME inoperable.
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
ra A. One SGT subsystem ft B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable.
A.1 B.1 AND Restore SGT subsystem to OPERABLE status.
A.1 Restore SGT subsystem to OPERABLE status.
Be in MODE 3.
7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.
7 days 12 hours B.2       Be in MODE 4.                             36 hours D
B.1 Be in MODE 3.
C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the
AND B.2 Be in MODE 4.
                                --------------------NOTE-------------------
12 hours 36 hours C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
--------------------NOTE-------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
C.1       Place OPERABLE SGT subsystem in operation.
C.1 Place OPERABLE SGT subsystem in operation.
Immediately secondary containment or during OPDRVs.          OR C.2.1     Suspend movement of                       Immediately recently irradiated fuel assemblies in secondary containment.
OR C.2.1 Suspend movement of recently irradiated fuel assemblies in secondary containment.
AND Monticello                                  3.6.4.3-1                            Amendment No. 146, XXX
AND Immediately Immediately Draft


SGT System 3.6.4.3 ACTIONS (continued)
SGT System 3.6.4.3 Monticello 3.6.4.3-2 Amendment No. 146, 181, XXX ACTIONS (continued)
CONDITION                     REQUIRED ACTION                         COMPLETION TIME C.2.2   Initiate action to suspend             Immediately OPDRVs.
CONDITION REQUIRED ACTION COMPLETION TIME C.2.2 Initiate action to suspend OPDRVs.
D. Two SGT subsystems         D.1     Enter LCO 3.0.3.                       Immediately inoperable in MODE 1, 2, or 3.
Immediately D. Two SGT subsystems inoperable in MODE 1, 2, or 3.
E. Two SGT subsystems        E.1     ---------------NOTE--------------
D.1 Enter LCO 3.0.3.
inoperable during                  LCO 3.0.3 is not applicable.
Immediately E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
movement of recently               -------------------------------------
E.1  
irradiated fuel assemblies in the                  Suspend movement of                    Immediately ra secondary containment or during OPDRVs.
---------------NOTE--------------
ft          AND E.2 recently irradiated fuel assemblies in secondary containment.
LCO 3.0.3 is not applicable.
Initiate action to suspend OPDRVs.
Suspend movement of recently irradiated fuel assemblies in secondary containment.
Immediately D
AND E.2 Initiate action to suspend OPDRVs.
SURVEILLANCE REQUIREMENTS SR 3.6.4.3.1 SURVEILLANCE Operate each SGT subsystem for 15 continuous minutes.
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes.
FREQUENCY 31 days SR 3.6.4.3.2     Perform required SGT filter testing in accordance              In accordance with the Ventilation Filter Testing Program (VFTP).             with the VFTP SR 3.6.4.3.3     Verify each SGT subsystem actuates on an actual                 24 months or simulated initiation signal.
31 days SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
Monticello                              3.6.4.3-2                  Amendment No. 146, 181, XXX
In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal.
24 months Draft


CREF System 3.7.4 3.7 PLANT SYSTEMS 3.7.4       Control Room Emergency Filtration (CREF) System LCO 3.7.4             Two CREF subsystems shall be OPERABLE.
CREF System 3.7.4 Monticello 3.7.4-1 Amendment No. 146, 160, 175, XXX 3.7 PLANT SYSTEMS 3.7.4 Control Room Emergency Filtration (CREF) System LCO 3.7.4 Two CREF subsystems shall be OPERABLE.  
                      ---------------------------------------------NOTE--------------------------------------------
---------------------------------------------NOTE--------------------------------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY:       MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.,
APPLICABILITY:
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.,
During operations with a potential for draining the reactor vessel (OPDRVs).
During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION ra A. One CREF subsystemft inoperable for reasons other than Condition B.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREF subsystem inoperable for reasons other than Condition B.
A.1 REQUIRED ACTION Restore CREF subsystem to OPERABLE status.
A.1 Restore CREF subsystem to OPERABLE status.
COMPLETION TIME 7 days D
7 days B. One or more CREF subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.
B. One or more CREF subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.
B.1 Initiate action to implement mitigating actions.
B.1 AND B.2 Initiate action to implement mitigating actions.
AND B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical and smoke hazards will not exceed limits.
Verify mitigating actions ensure CRE occupant Immediately 24 hours exposures to radiological, chemical and smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary to OPERABLE status.
AND B.3       Restore CRE boundary to OPERABLE status.                         90 days Monticello                                        3.7.4-1            Amendment No. 146, 160, 175, XXX
Immediately 24 hours 90 days Draft


CREF System 3.7.4 raft D
CREF System 3.7.4 Monticello 3.7.4-2 Amendment No. 146, 160, XXX Draft
Monticello   3.7.4-2   Amendment No. 146, 160, XXX


CREF System 3.7.4 ACTIONS (continued)
CREF System 3.7.4 Monticello 3.7.4-3 Amendment No. 146, 160, XXX ACTIONS (continued)
CONDITION                       REQUIRED ACTION                         COMPLETION TIME C. Required Action and         C.1      Be in MODE 3.                            12 hours associated Completion Time of Condition A or B   AND not met in MODE 1, 2, or 3.                       C.2       Be in MODE 4.                           36 hours D. Required Action and         --------------------NOTE-------------------
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.
associated Completion      LCO 3.0.3 is not applicable.
C.1 Be in MODE 3.
Time of Condition A not    ------------------------------------------------
AND C.2 Be in MODE 4.
met during movement of recently irradiated fuel    D.1       Place OPERABLE CREF                     Immediately assemblies in the                    subsystem in pressurization secondary containment                mode.
12 hours 36 hours D. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
ra or during OPDRVs.
--------------------NOTE-------------------
ft OR D.2.1 AND Suspend movement of recently irradiated fuel assemblies in the secondary containment.
LCO 3.0.3 is not applicable.
Immediately D.2.2     Initiate action to suspend               Immediately D
D.1 Place OPERABLE CREF subsystem in pressurization mode.
E. Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.
OR D.2.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
E.1 OPDRVs.
AND D.2.2 Initiate action to suspend OPDRVs.
Enter LCO 3.0.3.                         Immediately Monticello                                    3.7.4-3                    Amendment No. 146, 160, XXX
Immediately Immediately Immediately E. Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.
E.1 Enter LCO 3.0.3.
Immediately Draft


CREF System 3.7.4 ACTIONS (continued)
CREF System 3.7.4 Monticello 3.7.4-4 Amendment No. 146, 160, 175, 181, XXX ACTIONS (continued)
CONDITION                         REQUIRED ACTION                         COMPLETION TIME F. Two CREF subsystems         --------------------NOTE-------------------
CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREF subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
inoperable during            LCO 3.0.3 is not applicable.
OR One or more CREF subsystems inoperable due to an inoperable CRE boundary during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
movement of recently        ------------------------------------------------
--------------------NOTE-------------------
irradiated fuel assemblies in the            F.1       Suspend movement of                     Immediately secondary containment                  recently irradiated fuel or during OPDRVs.                      assemblies in the secondary containment.
LCO 3.0.3 is not applicable.
OR AND One or more CREF subsystems inoperable      F.2       Initiate action to suspend               Immediately due to an inoperable                OPDRVs.
F.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
CRE boundary during ra movement of recently irradiated fuel assemblies in the ft secondary containment or during OPDRVs.
AND F.2 Initiate action to suspend OPDRVs.
SURVEILLANCE REQUIREMENTS SURVEILLANCE                                               FREQUENCY D
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each CREF subsystem for 15 continuous minutes.
SR 3.7.4.1 SR 3.7.4.2 Operate each CREF subsystem for 15 continuous minutes.
31 days SR 3.7.4.2 Perform required CREF filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
Perform required CREF filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.4.3 Verify each CREF subsystem actuates on an actual or simulated initiation signal.
31 days In accordance with the VFTP SR 3.7.4.3       Verify each CREF subsystem actuates on an actual                   24 months or simulated initiation signal.
24 months SR 3.7.4.4 Perform required CRE unfiltered air in-leakage testing in accordance with the Control Room Envelope Habitability Program.
SR 3.7.4.4       Perform required CRE unfiltered air in-leakage                     In accordance testing in accordance with the Control Room                         with the Control Envelope Habitability Program.                                     Room Envelope Habitability Program Monticello                                    3.7.4-4      Amendment No. 146, 160, 175, 181, XXX
In accordance with the Control Room Envelope Habitability Program Draft


Control Room Ventilation System 3.7.5 3.7 PLANT SYSTEMS 3.7.5       Control Room Ventilation System LCO 3.7.5             Two control room ventilation subsystems shall be OPERABLE.
Control Room Ventilation System 3.7.5 Monticello 3.7.5-1 Amendment No. 146, 148, 154, XXX 3.7 PLANT SYSTEMS 3.7.5 Control Room Ventilation System LCO 3.7.5 Two control room ventilation subsystems shall be OPERABLE.
APPLICABILITY:       MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment,.
APPLICABILITY:
MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment,.
During operations with a potential for draining the reactor vessel (OPDRVs).
During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION                         REQUIRED ACTION                         COMPLETION TIME A. One control room B. Two control room ra ventilation subsystem inoperable.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room ventilation subsystem inoperable.
ft ventilation subsystems inoperable.
A.1 Restore control room ventilation subsystem to OPERABLE status.
A.1 B.1 AND Restore control room ventilation subsystem to OPERABLE status.
30 days B. Two control room ventilation subsystems inoperable.
Verify control room area temperature < 90&deg;F.
B.1 Verify control room area temperature < 90&deg;F.
30 days Once per 4 hours B.2       Restore one control room                 72 hours D
AND B.2 Restore one control room ventilation subsystem to OPERABLE status.
C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, C.1 AND ventilation subsystem to OPERABLE status.
Once per 4 hours 72 hours C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.
Be in MODE 3.                           12 hours or 3.                        C.2       Be in MODE 4.                           36 hours D. Required Action and         --------------------NOTE-------------------
C.1 Be in MODE 3.
associated Completion        LCO 3.0.3 is not applicable.
AND C.2 Be in MODE 4.
Time of Condition A not      ------------------------------------------------
12 hours 36 hours D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the secondary containment or during OPDRVs.
met during movement of irradiated fuel              D.1       Place OPERABLE control                   Immediately assemblies in the                      room ventilation subsystem secondary containment                  in operation.
--------------------NOTE-------------------
or during OPDRVs.
LCO 3.0.3 is not applicable.
OR Monticello                                    3.7.5-1            Amendment No. 146, 148, 154, XXX
D.1 Place OPERABLE control room ventilation subsystem in operation.
OR Immediately Draft


Control Room Ventilation System 3.7.5 ACTIONS (continued)
Control Room Ventilation System 3.7.5 Monticello 3.7.5-2 Amendment No. 146, 148, 154, XXX ACTIONS (continued)
CONDITION                       REQUIRED ACTION                         COMPLETION TIME D.2.1     Suspend movement of                     Immediately irradiated fuel assemblies in the secondary containment.
CONDITION REQUIRED ACTION COMPLETION TIME D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment.
AND D.2.2     Initiate action to suspend               Immediately OPDRVs.
AND D.2.2 Initiate action to suspend OPDRVs.
E. Required Action and       --------------------NOTE-------------------
Immediately Immediately E. Required Action and associated Completion Time of Condition B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
associated Completion      LCO 3.0.3 is not applicable.
--------------------NOTE-------------------
Time of Condition B not    ------------------------------------------------
LCO 3.0.3 is not applicable.
met during movement of ra recently irradiated fuel assemblies in the secondary containment ft or during OPDRVs.
E.1 Suspend movement of irradiated fuel assemblies in the secondary containment.
E.1 AND E.2 Suspend movement of irradiated fuel assemblies in the secondary containment.
AND E.2 Initiate actions to suspend OPDRVs.
Initiate actions to suspend OPDRVs.
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each control room ventilation subsystem has the capability to remove the assumed heat load.
Immediately Immediately D
24 months Draft
SURVEILLANCE REQUIREMENTS SR 3.7.5.1 SURVEILLANCE Verify each control room ventilation subsystem has the capability to remove the assumed heat load.
FREQUENCY 24 months Monticello                                  3.7.5-2            Amendment No. 146, 148, 154, XXX


AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2         AC Sources - Shutdown LCO 3.8.2                   The following AC electrical power sources shall be OPERABLE:
AC Sources - Shutdown 3.8.2 Monticello 3.8.2-1 Amendment No. 146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:
: a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown;" and
: a.
: b. One emergency diesel generator (EDG) capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.
One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown;" and
APPLICABILITY:               MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary ACTIONS ra LCO 3.0.3 is not applicable.
: b.
ft containment.
One emergency diesel generator (EDG) capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.
APPLICABILITY:
MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
ACTIONS
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
CONDITION                                 REQUIRED ACTION                           COMPLETION TIME D
LCO 3.0.3 is not applicable.
A. One required offsite circuit inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit inoperable.  
                                            --------------------NOTE-------------------
--------------------NOTE-------------------
Enter applicable Condition and Required Actions of LCO 3.8.8, with one required division de-energized as a result of Condition A.
Enter applicable Condition and Required Actions of LCO 3.8.8, with one required division de-energized as a result of Condition A.
A.1       Declare affected required                 Immediately feature(s), with no offsite power available, inoperable.
A.1 Declare affected required feature(s), with no offsite power available, inoperable.
OR Monticello                                                3.8.2-1                  Amendment No. 146, 148, XXX
OR Immediately Draft


AC Sources - Shutdown 3.8.2 ACTIONS (continued)
AC Sources - Shutdown 3.8.2 Monticello 3.8.2-2 Amendment No. 146, 148, XXX ACTIONS (continued)
CONDITION             REQUIRED ACTION                 COMPLETION TIME A.2.1   Suspend CORE                   Immediately ALTERATIONS.
CONDITION REQUIRED ACTION COMPLETION TIME A.2.1 Suspend CORE ALTERATIONS.
AND A.2.2   Suspend movement of           Immediately recently irradiated fuel assemblies in the secondary containment.
AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND Immediately A.2.3   Initiate action to suspend operations with a potential raft for draining the reactor vessel (OPDRVs).
AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
AND A.2.34 Initiate action to restore required offsite power circuit to OPERABLE status.
AND A.2.34 Initiate action to restore required offsite power circuit to OPERABLE status.
Immediately D
Immediately Immediately Immediately Immediately B. One required EDG inoperable.
B. One required EDG inoperable.
B.1 Suspend CORE ALTERATIONS.
B.1 AND B.2 Suspend CORE ALTERATIONS.
AND B.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
Suspend movement of recently irradiated fuel assemblies in the Immediately Immediately secondary containment.
AND B.3 Initiate action to suspend OPDRVs.
AND Immediately B.3     Initiate action to suspend OPDRVs.
AND B.34 Initiate action to restore required EDG to OPERABLE status.
AND Immediately B.34   Initiate action to restore required EDG to OPERABLE status.
Immediately Immediately Immediately Immediately Draft
Monticello                        3.8.2-2              Amendment No. 146, 148, XXX


AC Sources - Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                                   FREQUENCY SR 3.8.2.1   ------------------------------NOTES-----------------------------
AC Sources - Shutdown 3.8.2 Monticello 3.8.2-3 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1  
------------------------------NOTES-----------------------------
: 1. The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.7, and SR 3.8.1.8 through SR 3.8.1.13.
: 1. The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.7, and SR 3.8.1.8 through SR 3.8.1.13.
: 2. SR 3.8.1.8 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown."
: 2. SR 3.8.1.8 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown."
For AC sources required to be OPERABLE the SRs                         In accordance of Specification 3.8.1, except SR 3.8.1.6, are                         with applicable applicable.                                                            SRs raft D
For AC sources required to be OPERABLE the SRs of Specification 3.8.1, except SR 3.8.1.6, are applicable.
Monticello                                  3.8.2-3                                  Amendment No. 146
In accordance with applicable SRs Draft


DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5         DC Sources - Shutdown LCO 3.8.5                   Division 1 or Division 2 125 VDC electrical power subsystem shall be OPERABLE to support one division of the DC Electrical Power Distribution System required by LCO 3.8.8, "Distribution Systems -
DC Sources - Shutdown 3.8.5 Monticello 3.8.5-1 Amendment No. 146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 Division 1 or Division 2 125 VDC electrical power subsystem shall be OPERABLE to support one division of the DC Electrical Power Distribution System required by LCO 3.8.8, "Distribution Systems -
Shutdown."
Shutdown."
APPLICABILITY:               MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
APPLICABILITY:
ACTIONS
MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
ACTIONS  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
CONDITION A. Required DC electrical power subsystem inoperable.
LCO 3.0.3 is not applicable.
ra LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable.
ft              A.1 REQUIRED ACTION Suspend CORE ALTERATIONS.
A.1 Suspend CORE ALTERATIONS.
COMPLETION TIME Immediately AND D                                  A.2 AND Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND A.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
Immediately Immediately A.3       Initiate action to suspend operations with a potential for draining the reactor vessel.
AND A.3 Initiate action to suspend operations with a potential for draining the reactor vessel.
AND Immediately A.34     Initiate action to restore required DC electrical power subsystem to OPERABLE status.
AND A.34 Initiate action to restore required DC electrical power subsystem to OPERABLE status.
Monticello                                                3.8.5-1                  Amendment No. 146, 148, XXX
Immediately Immediately Immediately Immediately Draft


DC Sources - Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                                   FREQUENCY SR 3.8.5.1   -------------------------------NOTE------------------------------
DC Sources - Shutdown 3.8.5 Monticello 3.8.5-2 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1  
-------------------------------NOTE------------------------------
The following SR is not required to be performed:
The following SR is not required to be performed:
SR 3.8.4.3.
SR 3.8.4.3.
For DC sources required to be OPERABLE, the                             In accordance following SRs are applicable:                                           with applicable SRs SR 3.8.4.1, SR 3.8.4.2, and SR 3.8.4.3.
For DC sources required to be OPERABLE, the following SRs are applicable:
raft D
SR 3.8.4.1, SR 3.8.4.2, and SR 3.8.4.3.
Monticello                                  3.8.5-2                                  Amendment No. 146
In accordance with applicable SRs Draft


Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8         Distribution Systems - Shutdown LCO 3.8.8                   The necessary portions of the AC and DC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.
Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-1 Amendment No. 146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.
APPLICABILITY:               MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
APPLICABILITY:
ACTIONS
MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
ACTIONS  
------------------------------------------------------------NOTE-----------------------------------------------------------
------------------------------------------------------------NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
CONDITION A. One or more required AC or DC electrical power distribution subsystems inoperable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC or DC electrical power distribution subsystems inoperable.
ra ft              A.1 REQUIRED ACTION Declare associated supported required feature(s) inoperable.
A.1 Declare associated supported required feature(s) inoperable.
COMPLETION TIME Immediately OR D                                  A.2.1 A.2.2 AND Suspend CORE ALTERATIONS.
OR A.2.1 Suspend CORE ALTERATIONS.
Suspend handling of recently irradiated fuel Immediately Immediately assemblies in the secondary containment.
AND A.2.2 Suspend handling of recently irradiated fuel assemblies in the secondary containment.
AND Immediately A.2.3     Initiate action to suspend operations with a potential for draining the reactor vessel.
AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.
AND Monticello                                                3.8.8-1                  Amendment No. 146, 148, XXX
AND Immediately Immediately Immediately Immediately Draft


Distribution Systems - Shutdown 3.8.8 ACTIONS (continued)
Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-2 Amendment No. 146, XXX ACTIONS (continued)
CONDITION                   REQUIRED ACTION                 COMPLETION TIME A.2.34 Initiate actions to restore       Immediately required AC and DC electrical power distribution subsystems to OPERABLE status.
CONDITION REQUIRED ACTION COMPLETION TIME A.2.34 Initiate actions to restore required AC and DC electrical power distribution subsystems to OPERABLE status.
AND A.2.45 Declare associated               Immediately required shutdown cooling subsystem(s) inoperable and not in operation.
AND A.2.45 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.
SR 3.8.8.1 ra SURVEILLANCE REQUIREMENTS ft  SURVEILLANCE Verify correct breaker alignments and voltage to required AC and DC electrical power distribution subsystems.
Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage to required AC and DC electrical power distribution subsystems.
FREQUENCY 7 days D
7 days Draft}}
Monticello                              3.8.8-2                    Amendment No. 146, XXX}}

Latest revision as of 11:53, 8 January 2025

MNGP TSTF-542 TS Draft Markups
ML17250A871
Person / Time
Site: Monticello Xcel Energy icon.png
Issue date: 09/07/2017
From: Robert Kuntz
Plant Licensing Branch III
To:
Kuntz R, NRR/DORL/LPLIII,
References
Download: ML17250A871 (83)
v • d • e


Text

Monticello i

Revision 0 TABLE OF CONTENTS Page Number 1.0 USE AND APPLICATION 1.1 Definitions............................................................................................................ 1.1-1 1.2 Logical Connectors.............................................................................................. 1.2-1 1.3 Completion Times................................................................................................ 1.3-1 1.4 Frequency........................................................................................................... 1.4-1 2.0 SAFETY LIMITS (SLs).............................................................................................. 2.0-1 2.1 Safety Limits 2.2 SL Violations 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.......................... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY......................................... 3.0-4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM).................................................................... 3.1.1-1 3.1.2 Reactivity Anomalies................................................................................... 3.1.2-1 3.1.3 Control Rod OPERABILITY........................................................................ 3.1.3-1 3.1.4 Control Rod Scram Times........................................................................... 3.1.4-1 3.1.5 Control Rod Scram Accumulators............................................................... 3.1.5-1 3.1.6 Rod Pattern Control.................................................................................... 3.1.6-1 3.1.7 Standby Liquid Control (SLC) System......................................................... 3.1.7-1 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves............................. 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)............................................................................................. 3.2.1-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)........................................... 3.2.2-1 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) (Optional)............................ 3.2.3-1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation................................... 3.3.1.1-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation......................................... 3.3.1.2-1 3.3.2.1 Control Rod Block Instrumentation........................................................... 3.3.2.1-1 3.3.2.2 Feedwater Pump and Main Turbine High Water Level Trip Instrumentation.................................................................................. 3.3.2.2-1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation..................................... 3.3.3.1-1 3.3.3.2 Alternate Shutdown System..................................................................... 3.3.3.2-1 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation............................................................. 3.3.4.1-1 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation...................... 3.3.5.1-1 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation.............. 3.3.5.2-1 3.3.5.3 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation3.3.5.3-1 3.3.6.1 Primary Containment Isolation Instrumentation........................................ 3.3.6.1-1 3.3.6.2 Secondary Containment Isolation Instrumentation................................... 3.3.6.2-1 3.3.6.3 Low-Low Set (LLS) Instrumentation......................................................... 3.3.6.3-1 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation.................................................................................. 3.3.7.1-1 3.3.7.2 Mechanical Vacuum Pump Isolation Instrumentation............................... 3.3.7.2-1 Draft

3.3.8.1 Loss of Power (LOP) Instrumentation...................................................... 3.3.8.1-1 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring................... 3.3.8.2-1 Draft

Monticello ii Revision 01 TABLE OF CONTENTS Page Number 3.3.8.1 Loss of Power (LOP) Instrumentation...................................................... 3.3.8.1-1 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring................... 3.3.8.2-1 TABLE OF CONTENTS Page Number 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating.................................................................... 3.4.1-1 3.4.2 Jet Pumps................................................................................................... 3.4.2-1 3.4.3 Safety/Relief Valves (S/RVs)...................................................................... 3.4.3-1 3.4.4 RCS Operational LEAKAGE....................................................................... 3.4.4-1 3.4.5 RCS Leakage Detection Instrumentation.................................................... 3.4.5-1 3.4.6 RCS Specific Activity.................................................................................. 3.4.6-1 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown.............................................................................................. 3.4.7-1 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.............................................................................................. 3.4.8-1 3.4.9 RCS Pressure and Temperature (P/T) Limits.............................................. 3.4.9-1 3.4.10 Reactor Steam Dome Pressure................................................................ 3.4.10-1 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating....................................................................................... 3.5.1-1 3.5.2 RPV Water Inventory ControlECCS - Shutdown......................................... 3.5.2-1 3.5.3 RCIC System.............................................................................................. 3.5.3-1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment............................................................................... 3.6.1.1-1 3.6.1.2 Primary Containment Air Lock.................................................................. 3.6.1.2-1 3.6.1.3 Primary Containment Isolation Valves (PCIVs)........................................ 3.6.1.3-1 3.6.1.4 Drywell Air Temperature.......................................................................... 3.6.1.4-1 3.6.1.5 Low-Low Set (LLS) Valves....................................................................... 3.6.1.5-1 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers................. 3.6.1.6-1 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers............................... 3.6.1.7-1 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray.......................................... 3.6.1.8-1 3.6.2.1 Suppression Pool Average Temperature................................................. 3.6.2.1-1 3.6.2.2 Suppression Pool Water Level................................................................. 3.6.2.2-1 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling....................... 3.6.2.3-1 3.6.3.1 Primary Containment Oxygen Concentration........................................... 3.6.3.1-1 3.6.4.1 Secondary Containment........................................................................... 3.6.4.1-1 3.6.4.2 Secondary Containment Isolation Valves (SCIVs).................................... 3.6.4.2-1 3.6.4.3 Standby Gas Treatment (SGT) System.................................................... 3.6.4.3-1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System.......................... 3.7.1-1 3.7.2 Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS)............................................................................................ 3.7.2-1 3.7.3 Emergency Diesel Generator Emergency Service Water (EDG-ESW) System.............................................................................. 3.7.3-1 3.7.4 Control Room Emergency Filtration (CREF) System................................... 3.7.4-1 3.7.5 Control Room Ventilation System............................................................... 3.7.5-1 Draft

Monticello ii Revision 1 3.7.6 Main Condenser Offgas.............................................................................. 3.7.6-1 3.7.7 Main Turbine Bypass System..................................................................... 3.7.7-1 3.7.8 Spent Fuel Storage Pool Water Level......................................................... 3.7.8-1 Draft

Monticello iii Revision 0 TABLE OF CONTENTS Page Number 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating.............................................................................. 3.8.1-1 3.8.2 AC Sources - Shutdown.............................................................................. 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air................................................... 3.8.3-1 3.8.4 DC Sources - Operating.............................................................................. 3.8.4-1 3.8.5 DC Sources - Shutdown.............................................................................. 3.8.5-1 3.8.6 Battery Parameters..................................................................................... 3.8.6-1 3.8.7 Distribution Systems - Operating................................................................. 3.8.7-1 3.8.8 Distribution Systems - Shutdown................................................................ 3.8.8-1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks................................................................... 3.9.1-1 3.9.2 Refuel Position One-Rod-Out Interlock....................................................... 3.9.2-1 3.9.3 Control Rod Position................................................................................... 3.9.3-1 3.9.4 Control Rod Position Indication................................................................... 3.9.4-1 3.9.5 Control Rod OPERABILITY - Refueling...................................................... 3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water Level.............................................. 3.9.6-1 3.9.7 Residual Heat Removal (RHR) - High Water Level..................................... 3.9.7-1 3.9.8 Residual Heat Removal (RHR) - Low Water Level...................................... 3.9.8-1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation.................................... 3.10.1-1 3.10.2 Reactor Mode Switch Interlock Testing..................................................... 3.10.2-1 3.10.3 Single Control Rod Withdrawal - Hot Shutdown........................................ 3.10.3-1 3.10.4 Single Control Rod Withdrawal - Cold Shutdown...................................... 3.10.4-1 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling............................... 3.10.5-1 3.10.6 Multiple Control Rod Withdrawal - Refueling............................................. 3.10.6-1 3.10.7 Control Rod Testing - Operating............................................................... 3.10.7-1 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling........................................ 3.10.8-1 4.0 DESIGN FEATURES................................................................................................. 4.0-1 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility...................................................................................................... 5.1-1 5.2 Organization........................................................................................................ 5.2-1 5.3 Unit Staff Qualifications....................................................................................... 5.3-1 5.4 Procedures.......................................................................................................... 5.4-1 5.5 Programs and Manuals........................................................................................ 5.5-1 5.6 Reporting Requirements...................................................................................... 5.6-1 5.7 High Radiation Area............................................................................................. 5.7-1 Draft

Definitions 1.1 Monticello 1.1-1 Amendment No. 146 1.0 USE AND APPLICATION 1.1 Definitions

NOTE-----------------------------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific planar height HEAT GENERATION RATE and is equal to the sum of the LHGRs for all the fuel rods in (APLHGR) the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST shall be the injection of a TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.

Draft

Definitions 1.1 Monticello 1.1-2 Amendment No. 146 148, XXX 1.1 Definitions CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a.

Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and

b.

Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR)-11, "Limiting Values of Radionuclide Intake and Air Concentration Factors for Inhalation, Submersion and Ingestion," September 1988, and FGR-12, "External Exposure to Radionuclides in Air, Water and Soil,"

September 1993.

DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:

a)

The water inventory above the TAF is divided by the limiting drain rate; b)

The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single Draft

Definitions 1.1 Monticello 1.1-3 Amendment No. 146 148, XXX human error), for all penetration flow paths below the TAF except:

1.

Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed, or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;

2.

Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or

3.

Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power.

c)

The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory; d)

No additional draining events occur; and e)

Realistic cross-sectional areas and drain rates are used.

A bounding DRAIN TIME may be used in lieu of a calculated value.

LEAKAGE LEAKAGE shall be:

a.

Identified LEAKAGE

1.

LEAKAGE into the drywell, such as that from pump seals or valve packing that is captured and conducted to a sump or collecting tank; or

2.

LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; Draft

Definitions 1.1 Monticello 1.1-4 Amendment No. 146 1.1 Definitions LEAKAGE (continued)

b.

Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c.

Total LEAKAGE Sum of the identified and unidentified LEAKAGE; and

d.

Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

LINEAR HEAT GENERATION The LHGR shall be the heat generation rate per unit length of RATE (LHGR) fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all FUNCTIONAL TEST logic components required for OPERABILITY of a logic circuit, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY. The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

MINIMUM CRITICAL POWER The MCPR shall be the smallest critical power ratio (CPR) that RATIO (MCPR) exists in the core for each class of fuel. The CPR is that power in the assembly that is calculated by application of the appropriate correlation(s) to cause some point in the assembly to experience boiling transition, divided by the actual assembly operating power.

MODE A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.

Draft

Definitions 1.1 Monticello 1.1-5 Amendment No. 146, 172, 175, 176, 179 1.1 Definitions OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.5.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2004 MWt.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval from SYSTEM (RPS) RESPONSE initiation of any RPS channel trip to the de-energization of the TIME scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SHUTDOWN MARGIN (SDM)

SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:

a.

The reactor is xenon free;

b.

The moderator temperature is 68°F corresponding to the most reactive state; and

c.

All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn. With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

Draft

Definitions 1.1 Monticello 1.1-6 Amendment No. 146, 175 1.1 Definitions STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME shall be RESPONSE TIME that time interval from when the main turbine trip solenoid is activated until 80% of the turbine bypass capacity is established. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

Draft

Definitions 1.1 Monticello 1.1-7 Amendment No. 146 Table 1.1-1 (page 1 of 1)

MODES MODE TITLE REACTOR MODE SWITCH POSITION AVERAGE REACTOR COOLANT TEMPERATURE

(°F) 1 Power Operation Run NA 2

Startup Refuel(a) or Startup/Hot Standby NA 3

Hot Shutdown(a)

Shutdown

> 212 4

Cold Shutdown(a)

Shutdown 212 5

Refueling(b)

Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

(b) One or more reactor vessel head closure bolts less than fully tensioned.

Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-1 Amendment No. 146, XXX 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation LCO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.5.1-1.

ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.

A.1 Enter the Condition referenced in Table 3.3.5.1-1 for the channel.

Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

B.1

NOTES-------------

1. Only applicable in MODES 1, 2, and 3.
2. Only applicable for Functions 1.a, 1.b, 2.a, 2.b, 2.f, 2.h, and 2.k.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-2 Amendment No. 146, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2

NOTE--------------

Only applicable for Functions 3.a and 3.b.

Declare High Pressure Coolant Injection (HPCI)

System inoperable.

AND B.3 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCI initiation capability 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

C.1

NOTES-------------

1. Only applicable in MODES 1, 2, and 3.
2. Only applicable for Functions 1.c, 1.d, 1.e, 1.f, 2.c, 2.d, 2.e, 2.i, 2.j, 2.l, and 2.m.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND C.2 Restore channel to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-3 Amendment No. 146, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

D.1

NOTE--------------

Only applicable if HPCI pump suction is not aligned to the suppression pool.

Declare HPCI System inoperable.

AND D.2.1 Place channel in trip.

OR D.2.2 Align the HPCI pump suction to the suppression pool.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCI initiation capability 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours E. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

E.1

NOTES-------------

1. Only applicable in MODES 1, 2, and 3.
2. Only applicable for Function 2.g.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.

AND E.2 Restore channel to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for subsystems in both divisions 7 days Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-4 Amendment No. 146 CTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

F.1 Declare Automatic Depressurization System (ADS) valves inoperable.

AND F.2 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days G. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.

G.1 Declare ADS valves inoperable.

AND G.2 Restore channel to OPERABLE status.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days H. Required Action and associated Completion Time of Condition B, C, D, E, F, or G not met.

H.1 Declare associated supported feature(s) inoperable.

Immediately Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-5 Amendment No. 146, 151 SURVEILLANCE REQUIREMENTS

NOTES----------------------------------------------------------

1.

Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.5.1.3 Calibrate the trip unit.

92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.

92 days SR 3.3.5.1.5 Perform CHANNEL FUNCTIONAL TEST.

12 months SR 3.3.5.1.6 Perform CHANNEL CALIBRATION.

12 months SR 3.3.5.1.7 Perform CHANNEL CALIBRATION.

24 months SR 3.3.5.1.8 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months SR 3.3.5.1.9 Perform CHANNEL FUNCTIONAL TEST.

24 months Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-6 Amendment No. 146, 151, 170, 176, XXX Table 3.3.5.1-1 (page 1 of 6)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Core Spray System
a.

Reactor Vessel Water Level - Low Low 1, 2, 3, 4(a), 5(a) 4(ab)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

-48 inches

b.

Drywell Pressure -

High 1, 2, 3 4(ab)

B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig

c.

Reactor Steam Dome Pressure -

Low (Injection Permissive) 1, 2, 3 2

C SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)

SR 3.3.5.1.8 397 psig and 440 psig 4(a), 5(a) 2 B

SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)

SR 3.3.5.1.8 397 psig and 440 psig

d.

Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2

C B

SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)

SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)

SR 3.3.5.1.8 397 psig 397 psig

e.

Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2

C B

SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes 18 minutes (a)

When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown."

(ab) Also required to initiate the associated emergency diesel generator (EDG).

(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the Technical Requirements Manual (TRM).

Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-7 Amendment No. 146, XXX Table 3.3.5.1-1 (page 2 of 6)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Core Spray System
f.

Core Spray Pump Start - Time Delay Relay 1, 2, 3 4(a), 5(a) 1 per pump C

SR 3.3.5.1.7 SR 3.3.5.1.8 15.86 seconds

2. Low Pressure Coolant Injection (LPCI) System
a.

Reactor Vessel Water Level - Low Low 1, 2, 3, 4(a), 5(a) 4 B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

-48 inches

b.

Drywell Pressure -

High 1, 2, 3 4

B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig

c.

Reactor Steam Dome Pressure -

Low (Injection Permissive) 1, 2, 3 2

C SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)

SR 3.3.5.1.8 397 psig and 440 psig 4(a), 5(a) 2 B

SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)

SR 3.3.5.1.8 397 psig and 440 psig

d.

Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 1, 2, 3 2

C SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)

SR 3.3.5.1.8 397 psig 4(a), 5(a) 2 B

SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d)

SR 3.3.5.1.8 397 psig (a)

When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.

(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.

Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-8 Correction letter of 10/12/06 Amendment No. 146, 149, 151, 161, 170 176, XXX Table 3.3.5.1-1 (page 3 of 6)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. LPCI System
e.

Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2

C B

SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes 18 minutes

f.

Low Pressure Coolant Injection Pump Start - Time Delay Relay 1, 2, 3, 4(a), 5(a) 4 per pump B

SR 3.3.5.1.7 SR 3.3.5.1.8 Pumps A, B 5.33 seconds Pumps C, D 10.59 seconds

g.

Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2, 3, 4(a), 5(a) 1 per pump E

SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 360 gpm and 745 gpm

h.

Reactor Steam Dome Pressure -

Low (Break Detection) 1, 2, 3 4

B SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 873.6 psig and 923.4 psig

i.

Recirculation Pump Differential Pressure

- High (Break Detection) 1, 2, 3 4 per pump C

SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 63.5 inches wc

j.

Recirculation Riser Differential Pressure

- High (Break Detection) 1, 2, 3 4

C SR 3.3.5.1.2 SR 3.3.5.1.7(bc)(cd)

SR 3.3.5.1.8 100.0 inches wc (a)

When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.

(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.

Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-9 Amendment No. 146, 149, 151, 161, XXX Table 3.3.5.1-1 (page 4 of 6)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

2. LPCI System
k.

Recirculation Steam Dome Pressure -

Time Delay Relay (Break Detection) 1, 2, 3 2

B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 2.97 seconds

l.

Recirculation Pump Differential Pressure

- Time Delay Relay (Break Detection) 1, 2, 3 2

C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds

m. Recirculation Riser Differential Pressure

- Time Delay Relay (Break Detection) 1, 2, 3 2

C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds

3. High Pressure Coolant Injection (HPCI) System
a.

Reactor Vessel Water Level - Low Low 1, 2(de), 3(de) 4 B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

-48 inches

b.

Drywell Pressure -

High 1, 2(de), 3(de) 4 B

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig

c.

Reactor Vessel Water Level - High 1, 2(de), 3(de) 2 C

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 48 inches

d.

Condensate Storage Tank Level - Low 1, 2(de), 3(de) 2 D

SR 3.3.5.1.7 SR 3.3.5.1.8 29.3 inches

e.

Suppression Pool Water Level - High 1, 2(de), 3(de) 2 D

SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 3.0 inches

f.

High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2(de), 3(de) 1 E

SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 362 gpm and 849 gpm (de) With reactor steam dome pressure > 150 psig.

Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-10 Amendment No. 146, XXX Table 3.3.5.1-1 (page 5 of 6)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

4. Automatic Depressurization System (ADS) Trip System A
a.

Reactor Vessel Water Level - Low Low 1, 2(de), 3(de) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

-48 inches

b.

Automatic Depressurization System Initiation Timer 1, 2(de), 3(de) 1 G

SR 3.3.5.1.7 SR 3.3.5.1.8 120 seconds

c.

Core Spray Pump Discharge Pressure

- High 1, 2(de), 3(de) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)

SR 3.3.5.1.8 75 psig and 125 psig

d.

Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(de), 3(de) 4 G

SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)

SR 3.3.5.1.8 75 psig and 125 psig

5. ADS Trip System B
a.

Reactor Vessel Water Level - Low Low 1, 2(de), 3(de) 2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

-48 inches

b.

Automatic Depressurization System Initiation Timer 1, 2(de), 3(de) 1 G

SR 3.3.5.1.7 SR 3.3.5.1.8 120 seconds (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.

(de) With reactor steam dome pressure > 150 psig.

Draft

ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-11 Amendment No. 146, XXX Table 3.3.5.1-1 (page 6 of 6)

Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5. ADS Trip System B
c.

Core Spray Pump Discharge Pressure

- High 1, 2(de), 3(de) 2 G

SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)

SR 3.3.5.1.8 75 psig and 125 psig

d.

Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2(de), 3(de) 4 G

SR 3.3.5.1.2 SR 3.3.5.1.4(bc)(c d)

SR 3.3.5.1.8 75 psig and 125 psig (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.

(cd) The instrument channel setpoint shall be reset to a value that is within the as-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as-found tolerance and the as-left tolerance are specified in the TRM.

(de) With reactor steam dome pressure > 150 psig.

Draft

RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-1 Amendment No. XXX 3.3 INSTRUMENTATION 3.3.5.3 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.3 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.3-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.5.3-1.

ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.

A.1 Enter the Condition referenced in Table 3.3.5.3-1 for the channel.

Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.3-1.

B.1 Declare associated penetration flow path(s) incapable of automatic isolation.

AND B.2 Calculate DRAIN TIME.

Immediately Immediately C. As required by Required Action A.1 and referenced in Table 3.3.5.3-1.

C.1 Place channel in trip.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. As required by Required Action A.1 and referenced in Table 3.3.5.3-1.

D.1 Restore channel to OPERABLE status.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Draft

RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-2 Amendment No. XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met.

E.1 Declare associated low pressure ECCS injection/spray subsystem inoperable.

Immediately SURVEILLANCE REQUIREMENTS

NOTE-----------------------------------------------------------

Refer to Table 3.3.5.3-1 to determine which SRs apply for each ECCS Function.

SURVEILLANCE FREQUENCY SR 3.3.5.3.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.3.2 Perform CHANNEL FUNCTIONAL TEST.

92 days Draft

RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-3 Amendment No. XXX Table 3.3.5.3-1 (page 1 of 1)

RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Core Spray System
a.

Reactor Steam Dome Pressure - Low (Injection Permissive) 4, 5 2

C SR 3.3.5.3.2 397 psig and 440psig

2. Low Pressure Coolant Injection (LPCI)

System

a.

Reactor Steam Dome Pressure -

Low (Injection Permissive) 4, 5 2

C SR 3.3.5.3.2 397 psig and 440 psig

b.

Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 4, 5 1 per pump(a)

D SR 3.3.5.3.2 360 gpm and 745 gpm

3. RHR System Isolation
a.

Reactor Vessel Water Level - Low (b) 2 B

SR 3.3.5.3.1 SR 3.3.5.3.2 7 inches

4. Reactor Water Cleanup (RWCU) System Isolation
a.

Reactor Vessel Water Level - Low Low (b) 2 B

SR 3.3.5.3.1 SR 3.3.5.3.2

-48 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control."

(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.

Draft

Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-1 Amendment No. 146 XXX 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6.1-1.

ACTIONS

NOTES----------------------------------------------------------

1.

Penetration flow paths may be unisolated intermittently under administrative controls.

2.

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required channels inoperable.

A.1 Place channel in trip.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b B. One or more Functions with primary containment isolation capability not maintained.

B.1 Restore primary containment isolation capability.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Required Action and associated Completion Time of Condition A or B not met.

C.1 Enter the Condition referenced in Table 3.3.6.1-1 for the channel.

Immediately Draft

Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-2 Amendment No. 146 XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.

D.1 Isolate associated main steam line (MSL).

OR D.2.1 Be in MODE 3.

AND D.2.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.

E.1 Be in MODE 2.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> F. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.

F.1 Isolate the affected penetration flow path(s).

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> G. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.

G.1 Isolate the affected penetration flow path(s).

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> H. As required by Required Action C.1 and referenced in Table 3.3.6.1-1.

H.1 Declare associated standby liquid control (SLC) subsystem inoperable.

OR H.2 Isolate the Reactor Water Cleanup System.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour Draft

Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-3 Amendment No. 146 XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I.

As required by Required Action C.1 and referenced in Table 3.3.6.1-1.

I.1 Initiate action to restore channel to OPERABLE status.

OR I.2 Initiate action to isolate the Residual Heat Removal (RHR) Shutdown Cooling System.

Immediately Immediately SURVEILLANCE REQUIREMENTS

NOTES----------------------------------------------------------

1.

Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains primary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.1.3 Calibrate the trip unit.

92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.

92 days Draft

Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-4 Amendment No. 146 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months Draft

Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-5 Amendment No. 146, 176 Table 3.3.6.1-1 (page 1 of 3)

Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Main Steam Line Isolation
a.

Reactor Vessel Water Level - Low Low 1, 2, 3 2

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

-48 inches

b.

Main Steam Line Pressure - Low 1

2 E

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 815 psig

c.

Main Steam Line Flow - High 1, 2, 3 2 per MSL D

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 116.9% rated steam flow

d.

Main Steam Line Tunnel Temperature - High 1, 2, 3 2 per trip string D

SR 3.3.6.1.5 SR 3.3.6.1.6 209°F

2. Primary Containment Isolation
a.

Reactor Vessel Water Level - Low 1, 2, 3 2

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches

b.

Drywell Pressure -

High 1, 2, 3 2

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig

3. High Pressure Coolant Injection (HPCI) System Isolation
a.

HPCI Steam Line Flow - High 1, 2, 3 2

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 300,000 lb/hour with 5.58 second time delay Draft

Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-6 Amendment No. 146 Table 3.3.6.1-1 (page 2 of 3)

Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

3. HPCI System Isolation
b.

HPCI Steam Supply Line Pressure - Low 1, 2, 3 4

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 95.5 psig

c.

HPCI Steam Line Area Temperature -

High 1, 2, 3 16 F

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196°F

4.

Reactor Core Isolation Cooling (RCIC) System Isolation

a.

RCIC Steam Line Flow - High 1, 2, 3 2

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 45,903 lb/hour with 7.16 second time delay

b.

RCIC Steam Supply Line Pressure - Low 1, 2, 3 4

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 54 psig

c.

RCIC Steam Line Area Temperature -

High 1, 2, 3 16 F

SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196°F

5.

Reactor Water Cleanup (RWCU) System Isolation

a.

RWCU Flow - High 1, 2, 3 2

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 500 gpm with 11.4 second time delay

b.

RWCU Room Temperature - High 1, 2, 3 2

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188°F

c.

Drywell Pressure -

High 1, 2, 3 2

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig Draft

Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-7 Amendment No. 146, 164, XXX Table 3.3.6.1-1 (page 3 of 3)

Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

5. RWCU System Isolation
d.

SLC System Initiation 1, 2, 3 1

H SR 3.3.6.1.6 NA

e.

Reactor Vessel Water Level - Low Low 1, 2, 3 2

F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

-48 inches

6. Shutdown Cooling System Isolation
a.

Reactor Steam Dome Pressure -

High 1, 2, 3 2

F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 81.8 psig

b.

Reactor Vessel Water Level - Low 3, 4, 5 2(a)

I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches

7. Traversing Incore Probe System Isolation
a.

Reactor Vessel Water Level - Low 1, 2, 3 2

G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches

b.

Drywell Pressure -

High 1, 2, 3 2

G SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig (a)

Only one channel per trip system, with an isolation signal available to one shutdown cooling supply isolation valve, is required in MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained.

Draft

Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-1 Amendment No. 146 3.3 INSTRUMENTATION 3.3.6.2 Secondary Containment Isolation Instrumentation LCO 3.3.6.2 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.6.2-1.

ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.

A.1 Place channel in trip.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 1 and 2 AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 1 and 2 B. One or more Functions with secondary containment isolation capability not maintained.

B.1 Restore secondary containment isolation capability.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Required Action and associated Completion Time not met.

C.1.1 Isolate the associated penetration flow path(s).

OR C.1.2 Declare associated secondary containment isolation valves inoperable.

AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour Draft

Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-2 Amendment No. 146 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2.1 Place the associated standby gas treatment (SGT) subsystem in operation.

OR C.2.2 Declare associated SGT subsystem inoperable.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour SURVEILLANCE REQUIREMENTS

NOTES----------------------------------------------------------

1.

Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains secondary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.6.2.3 Calibrate the trip unit.

92 days SR 3.3.6.2.4 Perform CHANNEL CALIBRATION.

92 days SR 3.3.6.2.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.6.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months Draft

Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-3 Amendment No. 146, XXX Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE

1. Reactor Vessel Water Level - Low Low 1, 2, 3, (a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6

-48 inches

2. Drywell Pressure - High 1, 2, 3 2

SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 2 psig

3. Reactor Building Ventilation Exhaust Radiation - High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr
4. Refueling Floor Radiation - High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr (a)

During operations with a potential for draining the reactor vessel.

(ab) During movement of recently irradiated fuel assemblies in secondary containment.

Draft

CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-1 Amendment No. 146 148 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation LCO 3.3.7.1 The CREF System instrumentation for each Function in Table 3.3.7.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.7.1-1 ACTIONS

NOTE-----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.

B. Required Action and associated Completion Time not met.

A.1 Declare associated CREF subsystem inoperable.

AND A.2 Place channel in trip.

B.1 Place the associated CREF subsystem in the pressurization mode of operation.

OR B.2 Declare associated CREF subsystem inoperable.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of CREF initiation capability in both trip systems 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1 hour 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Draft

CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-2 Amendment No. 146 148 SURVEILLANCE REQUIREMENTS

NOTES----------------------------------------------------------

1. Refer to Table 3.3.7.1-1 to determine which SRs apply for each CREF System Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains CREF System initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.7.1.3 Calibrate the trip unit.

92 days SR 3.3.7.1.4 Perform CHANNEL CALIBRATION.

92 days SR 3.3.7.1.5 Perform CHANNEL CALIBRATION.

24 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

24 months Draft

CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-3 Amendment No. 146, 148, XXX Table 3.3.7.1-1 (Page 1 of 1)

Control Room Emergency Filtration System Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE

1. Reactor Vessel Water 1, 2, 3, (a) 2 SR 3.3.7.1.1

- 48 inches Level - Low Low SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.5 SR 3.3.7.1.6

2. Drywell Pressure -

1, 2, 3 2

SR 3.3.7.1.2 2 psig High SR 3.3.7.1.4 SR 3.3.7.1.6

3. Reactor Building 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Ventilation Exhaust SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.6
4. Refueling Floor 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Radiation - High SR 3.3.7.1.2 SR 3.3.7.1.4 SR 3.3.7.1.6 (a)

During operations with a potential for draining the reactor vessel.

(b)(a)

During movement of recently irradiated fuel assemblies in the secondary containment.

Draft

ECCS - Operating 3.5.1 Monticello 3.5.1-1 Amendment No. 146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of three safety/relief valves shall be OPERABLE.

NOTE--------------------------------------------

Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) shutdown cooling supply isolation interlock in MODE 3, if capable of being manually realigned and not otherwise inoperable.

APPLICABILITY:

MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig.

ACTIONS

NOTE-----------------------------------------------------------

LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A. One LPCI pump inoperable.

A.1 Restore LPCI pump to OPERABLE status.

30 days B. One LPCI subsystem inoperable for reasons other than Condition A.

OR One Core Spray subsystem inoperable.

B.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status.

7 days Draft

ECCS - Operating 3.5.1 Monticello 3.5.1-2 Amendment No. 146, 162, 184 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One LPCI pump in both LPCI subsystems inoperable.

C.1 Restore one LPCI pump to OPERABLE status.

7 days D. Two LPCI subsystems inoperable for reasons other than Condition C or G.

D.1 Restore one LPCI subsystem to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> E. One Core Spray subsystem inoperable.

AND One LPCI subsystem inoperable.

OR One or two LPCI pump(s) inoperable.

E.1 Restore Core Spray subsystem to OPERABLE status.

OR E.2 Restore LPCI subsystem to OPERABLE status.

OR E.3 Restore LPCI pump(s) to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met.

F.1 Be in MODE 3.

AND F.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours G. Two LPCI subsystems inoperable due to open RHR intertie return line isolation valve(s).

G.1 Isolate the RHR intertie line.

18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> Draft

ECCS - Operating 3.5.1 Monticello 3.5.1-3 Amendment No. 146, 162, 176, 184 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and associated Completion Time of Condition G not met.

H.1 Be in MODE 2.

6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I.

HPCI System inoperable.

I.1 Verify by administrative means RCIC System is OPERABLE.

AND I.2 Restore HPCI System to OPERABLE status.

Immediately 14 days J.

HPCI System inoperable.

AND Condition A, B, or C entered.

J.1 Restore HPCI System to OPERABLE status.

OR J.2 Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours K. One ADS valve inoperable.

K.1 Restore ADS valve to OPERABLE status.

14 days Draft

ECCS - Operating 3.5.1 Monticello 3.5.1-4 Amendment No. 146, 162, 176, 184 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. Required Action and associated Completion Time of Condition I, J, or K not met.

OR One ADS valve inoperable and Condition A, B, C, D, or G entered.

OR Two or more ADS valves inoperable.

OR HPCI System inoperable and Condition D, E, or G entered.

L.1 Be in MODE 3.

AND L.2 Reduce reactor steam dome pressure to 150 psig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours M. Two or more low pressure ECCS injection/spray subsystems inoperable for reasons other than Condition C, D, E, or G.

OR HPCI System and one or more ADS valves inoperable.

M.1 Enter LCO 3.0.3.

Immediately Draft

ECCS - Operating 3.5.1 Monticello 3.5.1-5 Amendment No. 146, 155, 162, 189, 190 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

31 days SR 3.5.1.2

NOTE------------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days SR 3.5.1.3 Verify ADS pneumatic pressure is as follows for each required ADS pneumatic supply:

a. S/RV Accumulator Bank header pressure 88.3 psig; and
b. Alternate Nitrogen System pressure is 1060 psig.

31 days SR 3.5.1.4

NOTE------------------------------

Only required to be met in MODE 1.

Verify the RHR System intertie return line isolation valves are closed.

31 days SR 3.5.1.5 Verify correct breaker alignment to the LPCI swing bus.

31 days SR 3.5.1.6 Verify each recirculation pump discharge valve cycles through one complete cycle of full travel or is de-energized in the closed position.

In accordance with the Inservice Testing Program Draft

ECCS - Operating 3.5.1 Monticello 3.5.1-6 Amendment No. 146, 162, 167 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.7 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor to containment pressure.

System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of Core Spray 2835 gpm 1 130 psi LPCI 3870 gpm 1 20 psi In accordance with the Inservice Testing Program SR 3.5.1.8

NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor steam dome pressure 1025.3 psig and 950 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.

In accordance with the Inservice Testing Program SR 3.5.1.9

NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.

24 months Draft

ECCS - Operating 3.5.1 Monticello 3.5.1-7 Amendment No. 146, 162, 168 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.10

NOTE------------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.

24 months SR 3.5.1.11

NOTE------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated automatic initiation signal.

24 months SR 3.5.1.12

NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam flow is adequate to perform the test.

Verify each ADS valve is capable of being opened.

In accordance with the Inservice Testing Program SR 3.5.1.13 Verify automatic transfer capability of the LPCI swing bus power supply from the normal source to the backup source.

24 months Draft

ECCS - Shutdown 3.5.2 Monticello 3.5.2-1 Amendment No. 146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.2 RPV Water Inventory Control ECCS - Shutdown LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

AND OneTwo low pressure ECCS injection/spray subsystems shall be OPERABLE.

NOTE--------------------------------------------

A One Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

APPLICABILITY:

MODE 4,

MODE and 5

, except with the spent fuel storage pool gates removed and water level 21 ft 11 inches over the top of the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rRequired ECCS injection/spray subsystem inoperable.

A.1 Restore required ECCS injection/spray subsystem to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Action and associated Completion Time of Condition A not met.

B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power.

Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).

Immediately C. DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.1 Verify secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Draft

ECCS - Shutdown 3.5.2 ACTIONS (continued)

Monticello 3.5.2-2 Amendment No. 146, XXX and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C. Two required ECCS injection/spray subsystems inoperable.

containment boundary is capable of being established in less than the DRAIN TIME.

AND C.2 Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME.

AND C.3 Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.

C.1 Initiate action to suspend OPDRVs.

AND C.2 Restore one required ECCS injection/spray subsystem to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. DRAIN TIME < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

D.1

NOTE ---------------

Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.

Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water level > TAF for 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Immediately Draft

ECCS - Shutdown 3.5.2 ACTIONS (continued)

Monticello 3.5.2-3 Amendment No. 146, XXX AND D.2 Initiate action to establish secondary containment boundary.

AND D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.

AND D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.

Immediately Immediately Immediately E. Required Action and associated Completion Time of Condition C or D not met.

OR DRAIN TIME < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

E.1 Initiate action to restore DRAIN TIME to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Immediately Draft

ECCS - Shutdown 3.5.2 ACTIONS (continued)

Monticello 3.5.2-4 Amendment No. 146, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and associated Completion Time not met.

D.1Initiate action to restore secondary containment to OPERABLE status.

AND D.2 Initiate action to restore one standby gas treatment subsystem to OPERABLE status.

AND D.3 Initiate action to restore isolation capability in each required secondary containment penetration flow path not isolated.

Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.5.2.21 Verify, for each a required ECCS injection/spray subsystem, the:

a. Suppression pool water level is -3 ft; or
b.

NOTE--------------------

Only one required ECCS injection/spray subsystem may take credit for this option during OPDRVs.

Condensate storage tank(s) water level is 7 ft for one tank operation and 4 ft for two tank operation.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Draft

ECCS - Shutdown 3.5.2 ACTIONS (continued)

Monticello 3.5.2-5 Amendment No. 146, XXX SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

31 days Draft

ECCS - Shutdown 3.5.2 Monticello 3.5.2-6 Amendment No. 146, 167, 189, 194, XXX SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.

31 days SR 3.5.2.43

NOTE------------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify for each the required ECCS injection/spray subsystem, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days SR 3.5.2.54 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes.

Verify each required ECCS pump develops the specified flow rate against a system head corresponding to the specified reactor to containment pressure.

System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of Core Spray 2835 gpm 1

130 psi LPCI 3870 gpm 1

20 psi In accordance with the INSERVICE TESTING PROGRAM 92 days SR 3.5.2.6 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.

24 months SR 3.5.2.75

NOTE------------------------------

Vessel injection/spray may be excluded.

Verify the each required ECCS injection/spray Draft

ECCS - Shutdown 3.5.2 Monticello 3.5.2-7 Amendment No. 146, 167, 189, 194, XXX SURVEILLANCE FREQUENCY subsystem operates actuates on a manual an actual or simulated automatic initiation signal.

24 months Draft

RCIC System 3.5.3 Monticello 3.5.3-1 Amendment No. 146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.3 RCIC System LCO 3.5.3 The RCIC System shall be OPERABLE.

APPLICABILITY:

MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

ACTIONS

NOTE-----------------------------------------------------------

LCO 3.0.4.b is not applicable to the RCIC System.

CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.

A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE.

AND A.2 Restore RCIC System to OPERABLE status.

Immediately 14 days B. Required Action and associated Completion Time not met.

B.1 Be in MODE 3.

AND B.2 Reduce reactor steam dome pressure to 150 psig.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Draft

RCIC System 3.5.3 Monticello 3.5.3-2 Amendment No. 146, 189 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1

NOTE------------------------------

Not required to be met for system vent flow paths opened under administrative control.

Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

31 days SR 3.5.3.2

NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 1025.3 psig and 950 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.

In accordance with the Inservice Testing Program SR 3.5.3.3

NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure 165 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.

24 months SR 3.5.3.4

NOTE------------------------------

Vessel injection may be excluded.

Verify the RCIC System actuates on an actual or simulated automatic initiation signal.

24 months SR 3.5.3.5 Verify the RCIC System locations susceptible to gas accumulation are sufficiently filled with water.

31 days Draft

PCIVs 3.6.1.3 Monticello 3.6.1.3-1 Amendment No. 146 148 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation."

ACTIONS

NOTES----------------------------------------------------------

1.

Penetration flow paths may be unisolated intermittently under administrative controls.

2.

Separate Condition entry is allowed for each penetration flow path.

3.

Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4.

Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment,"

when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------

Only applicable to penetration flow paths with two PCIVs.

One or more penetration flow paths with one PCIV inoperable for reasons other than Condition D or E.

A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except for main steam line AND 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for main steam line Draft

PCIVs 3.6.1.3 Monticello 3.6.1.3-2 Amendment No. 146 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2

NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.
2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Draft

PCIVs 3.6.1.3 Monticello 3.6.1.3-3 Amendment No. 146 148 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------

Only applicable to penetration flow paths with two PCIVs.

One or more penetration flow paths with two PCIVs inoperable for reasons other than Condition D or E.

B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. ------------NOTE------------

Only applicable to penetration flow paths with only one PCIV.

One or more penetration flow paths with one PCIV inoperable.

C.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except for excess flow check valves (EFCVs) and penetrations with a closed system AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for EFCVs and penetrations with a closed system Draft

PCIVs 3.6.1.3 Monticello 3.6.1.3-4 Amendment No. 146 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2

NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.
2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Draft

PCIVs 3.6.1.3 Monticello 3.6.1.3-5 Amendment No. 146 148 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration flow paths with one or more 18 inch primary containment purge and vent valves not within purge and vent valve leakage limits.

D.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND D.2

NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.
2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Once per 31 days for isolation devices outside containment E. One or more MSIVs with leakage rate not within limits.

E.1 Restore leakage rate to within limits.

8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> F. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3.

F.1 Be in MODE 3.

AND F.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Draft

PCIVs 3.6.1.3 Monticello 3.6.1.3-6 Amendment No. 146, 148, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and associated Completion Time of Condition A or B not met for PCIV(s) required to be OPERABLE during MODE 4 or 5.

G.1 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).

OR G.12 Initiate action to restore valve(s) to OPERABLE status.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1

NOTE------------------------------

Not required to be met when the 18 inch primary containment purge and vent valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 18 inch primary containment purge and vent valve is closed.

31 days Draft

PCIVs 3.6.1.3 Monticello 3.6.1.3-7 Amendment No. 146 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.2

NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual valve and blind flange that is located outside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

31 days SR 3.6.1.3.3

NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual isolation valve and blind flange that is located inside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge.

31 days SR 3.6.1.3.5 Verify the isolation time of each power operated automatic PCIV, except for MSIVs, is within limits.

24 months Draft

PCIVs 3.6.1.3 Monticello 3.6.1.3-8 Amendment No. 146 148, 176 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is 3 seconds and 9.9 seconds.

24 months SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation position on an actual or simulated isolation signal.

24 months SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV actuates on a simulated instrument line break to restrict flow to 2 gpm.

24 months SR 3.6.1.3.9 Verify each 18 inch primary containment purge and vent valve is blocked to restrict the valve from opening > 40°.

24 months SR 3.6.1.3.10 Remove and test the explosive squib from each shear isolation valve of the TIP System.

24 months on a STAGGERED TEST BASIS SR 3.6.1.3.11 Perform leakage rate testing for each 18 inch primary containment purge and vent valve with resilient seals.

In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify leakage rate through each MSIV is:

(a) 100 scfh when tested at 44.1 psig (Pa); or (b) 75.3 scfh when tested at 25 psig.

In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.13 Verify leakage rate through the main steam pathway is:

(a) 200 scfh when tested at 44.1 psig (Pa); or (b) 150.6 scfh when tested at 25 psig.

In accordance with the Primary Containment Leakage Rate Testing Program Draft

Secondary Containment 3.6.4.1 Monticello 3.6.4.1-1 Amendment No. 146, XXX 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment inoperable in MODE 1, 2, or 3.

A.1 Restore secondary containment to OPERABLE status.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Action and associated Completion Time of Condition A not met.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

C.1

NOTE--------------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND C.2 Initiate action to suspend OPDRVs.

Immediately Immediately Draft

Secondary Containment 3.6.4.1 Monticello 3.6.4.1-2 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge.

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.

31 days SR 3.6.4.1.3 Verify one secondary containment access door in each access opening is closed.

31 days SR 3.6.4.1.4 Verify the secondary containment can be maintained 0.25 inch of vacuum water gauge for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using one SGT subsystem at a flow rate 4000 cfm.

24 months on a STAGGERED TEST BASIS for each SGT subsystem Draft

SCIVs 3.6.4.2 Monticello 3.6.4.2-1 Amendment No. 146, XXX 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

NOTES----------------------------------------------------------

1.

Penetration flow paths may be unisolated intermittently under administrative controls.

2.

Separate Condition entry is allowed for each penetration flow path.

3.

Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration flow paths with one SCIV inoperable.

A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Draft

SCIVs 3.6.4.2 Monticello 3.6.4.2-2 Amendment No. 146 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2

NOTES-------------

1. Isolation devices in high radiation areas may be verified by use of administrative means.
2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.

Verify the affected penetration flow path is isolated.

Once per 31 days B. ------------NOTE------------

Only applicable to penetration flow paths with two isolation valves.

One or more penetration flow paths with two SCIVs inoperable.

B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Draft

SCIVs 3.6.4.2 Monticello 3.6.4.2-3 Amendment No.146, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

D.1

NOTE--------------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND D.2 Initiate action to suspend OPDRVs.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1

NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment isolation manual valve and blind flange that is not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

31 days SR 3.6.4.2.2 Verify the isolation time of each power operated, automatic SCIV is within limits.

92 days SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation position on an actual or simulated actuation signal.

24 months Draft

SGT System 3.6.4.3 Monticello 3.6.4.3-1 Amendment No. 146, XXX 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable.

A.1 Restore SGT subsystem to OPERABLE status.

7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.

B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

NOTE-------------------

LCO 3.0.3 is not applicable.

C.1 Place OPERABLE SGT subsystem in operation.

OR C.2.1 Suspend movement of recently irradiated fuel assemblies in secondary containment.

AND Immediately Immediately Draft

SGT System 3.6.4.3 Monticello 3.6.4.3-2 Amendment No. 146, 181, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2.2 Initiate action to suspend OPDRVs.

Immediately D. Two SGT subsystems inoperable in MODE 1, 2, or 3.

D.1 Enter LCO 3.0.3.

Immediately E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

E.1

NOTE--------------

LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in secondary containment.

AND E.2 Initiate action to suspend OPDRVs.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes.

31 days SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal.

24 months Draft

CREF System 3.7.4 Monticello 3.7.4-1 Amendment No. 146, 160, 175, XXX 3.7 PLANT SYSTEMS 3.7.4 Control Room Emergency Filtration (CREF) System LCO 3.7.4 Two CREF subsystems shall be OPERABLE.

NOTE--------------------------------------------

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment.,

During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREF subsystem inoperable for reasons other than Condition B.

A.1 Restore CREF subsystem to OPERABLE status.

7 days B. One or more CREF subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.

B.1 Initiate action to implement mitigating actions.

AND B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to OPERABLE status.

Immediately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 90 days Draft

CREF System 3.7.4 Monticello 3.7.4-2 Amendment No. 146, 160, XXX Draft

CREF System 3.7.4 Monticello 3.7.4-3 Amendment No. 146, 160, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours D. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

NOTE-------------------

LCO 3.0.3 is not applicable.

D.1 Place OPERABLE CREF subsystem in pressurization mode.

OR D.2.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND D.2.2 Initiate action to suspend OPDRVs.

Immediately Immediately Immediately E. Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

E.1 Enter LCO 3.0.3.

Immediately Draft

CREF System 3.7.4 Monticello 3.7.4-4 Amendment No. 146, 160, 175, 181, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREF subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

OR One or more CREF subsystems inoperable due to an inoperable CRE boundary during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

NOTE-------------------

LCO 3.0.3 is not applicable.

F.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND F.2 Initiate action to suspend OPDRVs.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each CREF subsystem for 15 continuous minutes.

31 days SR 3.7.4.2 Perform required CREF filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

In accordance with the VFTP SR 3.7.4.3 Verify each CREF subsystem actuates on an actual or simulated initiation signal.

24 months SR 3.7.4.4 Perform required CRE unfiltered air in-leakage testing in accordance with the Control Room Envelope Habitability Program.

In accordance with the Control Room Envelope Habitability Program Draft

Control Room Ventilation System 3.7.5 Monticello 3.7.5-1 Amendment No. 146, 148, 154, XXX 3.7 PLANT SYSTEMS 3.7.5 Control Room Ventilation System LCO 3.7.5 Two control room ventilation subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment,.

During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room ventilation subsystem inoperable.

A.1 Restore control room ventilation subsystem to OPERABLE status.

30 days B. Two control room ventilation subsystems inoperable.

B.1 Verify control room area temperature < 90°F.

AND B.2 Restore one control room ventilation subsystem to OPERABLE status.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 72 hours C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3.

C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the secondary containment or during OPDRVs.

NOTE-------------------

LCO 3.0.3 is not applicable.

D.1 Place OPERABLE control room ventilation subsystem in operation.

OR Immediately Draft

Control Room Ventilation System 3.7.5 Monticello 3.7.5-2 Amendment No. 146, 148, 154, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment.

AND D.2.2 Initiate action to suspend OPDRVs.

Immediately Immediately E. Required Action and associated Completion Time of Condition B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

NOTE-------------------

LCO 3.0.3 is not applicable.

E.1 Suspend movement of irradiated fuel assemblies in the secondary containment.

AND E.2 Initiate actions to suspend OPDRVs.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each control room ventilation subsystem has the capability to remove the assumed heat load.

24 months Draft

AC Sources - Shutdown 3.8.2 Monticello 3.8.2-1 Amendment No. 146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a.

One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown;" and

b.

One emergency diesel generator (EDG) capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS

NOTE-----------------------------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit inoperable.

NOTE-------------------

Enter applicable Condition and Required Actions of LCO 3.8.8, with one required division de-energized as a result of Condition A.

A.1 Declare affected required feature(s), with no offsite power available, inoperable.

OR Immediately Draft

AC Sources - Shutdown 3.8.2 Monticello 3.8.2-2 Amendment No. 146, 148, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).

AND A.2.34 Initiate action to restore required offsite power circuit to OPERABLE status.

Immediately Immediately Immediately Immediately B. One required EDG inoperable.

B.1 Suspend CORE ALTERATIONS.

AND B.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND B.3 Initiate action to suspend OPDRVs.

AND B.34 Initiate action to restore required EDG to OPERABLE status.

Immediately Immediately Immediately Immediately Draft

AC Sources - Shutdown 3.8.2 Monticello 3.8.2-3 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1

NOTES-----------------------------

1. The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.7, and SR 3.8.1.8 through SR 3.8.1.13.
2. SR 3.8.1.8 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown."

For AC sources required to be OPERABLE the SRs of Specification 3.8.1, except SR 3.8.1.6, are applicable.

In accordance with applicable SRs Draft

DC Sources - Shutdown 3.8.5 Monticello 3.8.5-1 Amendment No. 146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 Division 1 or Division 2 125 VDC electrical power subsystem shall be OPERABLE to support one division of the DC Electrical Power Distribution System required by LCO 3.8.8, "Distribution Systems -

Shutdown."

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS

NOTE-----------------------------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable.

A.1 Suspend CORE ALTERATIONS.

AND A.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND A.3 Initiate action to suspend operations with a potential for draining the reactor vessel.

AND A.34 Initiate action to restore required DC electrical power subsystem to OPERABLE status.

Immediately Immediately Immediately Immediately Draft

DC Sources - Shutdown 3.8.5 Monticello 3.8.5-2 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1

NOTE------------------------------

The following SR is not required to be performed:

SR 3.8.4.3.

For DC sources required to be OPERABLE, the following SRs are applicable:

SR 3.8.4.1, SR 3.8.4.2, and SR 3.8.4.3.

In accordance with applicable SRs Draft

Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-1 Amendment No. 146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS

NOTE-----------------------------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC or DC electrical power distribution subsystems inoperable.

A.1 Declare associated supported required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

AND A.2.2 Suspend handling of recently irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.

AND Immediately Immediately Immediately Immediately Draft

Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-2 Amendment No. 146, XXX ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.34 Initiate actions to restore required AC and DC electrical power distribution subsystems to OPERABLE status.

AND A.2.45 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.

Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage to required AC and DC electrical power distribution subsystems.

7 days Draft

Retrieved from "https://kanterella.com/w/index.php?title=ML17250A871&oldid=5112724"