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MNGP TSTF-542 TS Draft Markups
	ML17250A871
Person / Time
Site:	Monticello
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

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

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

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

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

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

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

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 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 CHECK adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.

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.

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.

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.

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.

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

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.

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

Definitions 1.1 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 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.

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

LEAKAGE e) Realistic cross-sectional areas and drain rates are used.

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

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; Monticello 1.1-3 Amendment No. 146 148, XXX

Definitions 1.1 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.

RATE (LHGR)

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.

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.

MODE D

MINIMUM CRITICAL POWER RATIO (MCPR)

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.

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

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).

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)

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.

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.

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

a.

b.

c.

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.

Monticello 1.1-5 Amendment No. 146, 172, 175, 176, 179

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.

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.

D Monticello 1.1-6 Amendment No. 146, 175

Definitions 1.1 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

ra Refueling(b) ft Shutdown or Refuel (a) All reactor vessel head closure bolts fully tensioned.

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

NA D

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.

APPLICABILITY: According to Table 3.3.5.1-1.

ACTIONS

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

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.

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

COMPLETION TIME Immediately Action A.1 and 1. Only applicable in D

referenced in Table 3.3.5.1-1.

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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 ---------------NOTE--------------

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

Declare High Pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery Coolant Injection (HPCI) of loss of HPCI System inoperable. initiation capability AND B.3 Place channel in trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action A.1 and referenced in ra C. As required by Required Table 3.3.5.1-1.

ft 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 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery D AND C.2 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

Monticello 3.3.5.1-2 Amendment No. 146, XXX

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 ---------------NOTE--------------

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.

Declare HPCI System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery inoperable. of loss of HPCI initiation capability AND D.2.1 Place channel in trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

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

1. Only applicable in MODES 1, 2, and 3.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Table 3.3.5.1-1.

D 2. Only applicable for Function 2.g.

Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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

ECCS Instrumentation 3.3.5.1 CTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required F.1 Declare Automatic 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 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.

(RCIC) inoperable AND 8 days 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 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)

Time of Condition B, C, inoperable.

D, E, F, or G not met.

Monticello 3.3.5.1-4 Amendment No. 146

ECCS Instrumentation 3.3.5.1 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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.

ft Perform CHANNEL CALIBRATION.

Perform CHANNEL FUNCTIONAL TEST.

92 days 92 days 12 months D

SR 3.3.5.1.6 SR 3.3.5.1.7 SR 3.3.5.1.8 Perform CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

Perform LOGIC SYSTEM 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

ECCS Instrumentation 3.3.5.1 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

1. Core Spray System (ab)

a. Reactor Vessel 1, 2, 3, 4 B SR 3.3.5.1.1 -48 inches (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)

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.

d.

Reactor Steam Reactor Steam Dome Pressure ra Dome Pressure -

Low (Injection Permissive) ft 1, 2, 3 (a) 4 ,5 1, 2, 3 (a) 2 2

2 C

B C

SR 3.3.5.1.2 SR 3.3.5.1.4 d)

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)

(bc)(c 397 psig and 440 psig 397 psig and 440 psig 397 psig d)

Permissive - Low D

e.

(Pump Permissive)

Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive)

(a) 4 ,5 1, 2, 3 (a) 4 ,5 (a)

(a) 2 2

2 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."

(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).

Monticello 3.3.5.1-6 Amendment No. 146, 151, 170, 176, XXX

ECCS Instrumentation 3.3.5.1 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

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)

Start - Time Delay 4 ,5 SR 3.3.5.1.8 seconds Relay

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)

Water Level - Low 4 ,5 SR 3.3.5.1.2 b.

c.

Low High Reactor Steam ra Dome Pressure -

Low (Injection Permissive) ft Drywell Pressure - 1, 2, 3 1, 2, 3 4

2 B

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)

SR 3.3.5.1.8 (bc)(c 2 psig 397 psig and 440 psig (a) (a)

D

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

2 B

C B

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 SR SR SR (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.

(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.

Monticello 3.3.5.1-7 Amendment No. 146, XXX

ECCS Instrumentation 3.3.5.1 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

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)

Permissive) 4 ,5 2 B SR 3.3.5.1.7 18 minutes SR 3.3.5.1.8

f. Low Pressure 1, 2, 3, 4 per pump B SR 3.3.5.1.7 (a) (a)

Coolant Injection 4 ,5 SR 3.3.5.1.8 g.

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

h. Reactor Steam 1, 2, 3 4 B SR 3.3.5.1.2 873.6 psig D

i.

j.

Dome Pressure -

Low (Break Detection)

Recirculation Pump Differential Pressure

- High (Break Detection)

Recirculation Riser Differential Pressure 1, 2, 3 1, 2, 3 4 per pump 4

C C

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)

- 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.

(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.

Monticello 3.3.5.1-8 Correction letter of 10/12/06 Amendment No. 146, 149, 151, 161, 170 176, XXX

ECCS Instrumentation 3.3.5.1 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

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)

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

- Time Delay Relay SR 3.3.5.1.9 (Break Detection) 3.

a.

ra

m. Recirculation Riser Differential Pressure

- Time Delay Relay Reactor Vesselft (Break Detection)

High Pressure Coolant Injection (HPCI) System Water Level - Low Low 1, 2, 3 1, 2 (de)

,3 (de) 2 4

C B

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

-48 inches SR 3.3.5.1.7 D

b.

c.

Drywell Pressure -

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

(de)

,3

,3 (de)

(de) 4 2

B C

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)

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)

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)

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)

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

Monticello 3.3.5.1-9 Amendment No. 146, 149, 151, 161, XXX

ECCS Instrumentation 3.3.5.1 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

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

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)

b. Automatic 1, 2 ,3 1 G SR 3.3.5.1.7 120 seconds c.

d.

Timer

- High Low Pressure ra Depressurization System Initiation ft Core Spray Pump Discharge Pressure Coolant Injection Pump Discharge 1, 2 1, 2 (de)

(de)

,3

,3 (de)

(de) 2 4

G G

SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4 d)

(bc)(c (bc)(c 75 psig and 125 psig 75 psig and 125 psig Pressure - High SR 3.3.5.1.8 5.

D ADS Trip System B a.

b.

Reactor Vessel Water Level - Low Low Automatic Depressurization 1, 2 1, 2 (de)

(de)

,3

,3 (de)

(de) 2 1

F G

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

-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.

(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.

Monticello 3.3.5.1-10 Amendment No. 146, XXX

ECCS Instrumentation 3.3.5.1 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

5. ADS Trip System B (de) (de)

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)

- High SR 3.3.5.1.8 (de) (de)

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)

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.

(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.

D Monticello 3.3.5.1-11 Amendment No. 146, XXX

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.

APPLICABILITY: According to Table 3.3.5.3-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION 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.

COMPLETION TIME Immediately B. As required by Required B.1 Declare associated Immediately D

Action A.1 and referenced in Table 3.3.5.3-1.

AND B.2 penetration flow path(s) incapable of automatic isolation.

Calculate DRAIN TIME. Immediately C. As required by Required C.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action A.1 and referenced in Table 3.3.5.3-1.

D. As required by Required D.1 Restore channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action A.1 and OPERABLE status.

referenced in Table 3.3.5.3-1.

Monticello 3.3.5.3-1 Amendment No. XXX

RPV Water Inventory Control Instrumentation 3.3.5.3 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.

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 SR 3.3.5.3.2 ra Perform CHANNEL CHECK.

ft Perform CHANNEL FUNCTIONAL TEST.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 92 days D

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

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)

2. Low Pressure Coolant Injection (LPCI)

System a.

b.

Permissive)

Low Pressure ra Reactor Steam Dome Pressure -

Low (Injection ft Coolant Injection Pump Discharge Flow - Low (Bypass) 4, 5 4, 5 2

1 per pump(a)

C D

SR 3.3.5.3.2 SR 3.3.5.3.2 397 psig and 440 psig 360 gpm and 745 gpm

3. RHR System Isolation 4.

D

a. Reactor Vessel Water Level - Low Reactor Water Cleanup (RWCU) System Isolation

a. Reactor Vessel Water Level - Low (b)

(b) 2 2

B B

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

-48 inches Low (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.

Monticello 3.3.5.3-3 Amendment No. XXX

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.

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 A. One or more required channels inoperable.

raft A.1 REQUIRED ACTION Place channel in trip.

COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND D

B. One or more Functions with primary B.1 Restore primary containment isolation 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months containment isolation capability.

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.

Monticello 3.3.6.1-1 Amendment No. 146 XXX

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required D.1 Isolate associated main 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action C.1 and steam line (MSL).

referenced in Table 3.3.6.1-1. OR D.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND D.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. As required by Required E.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action C.1 and referenced in Action C.1 and referenced in ra Table 3.3.6.1-1.

Table 3.3.6.1-1.ft F. As required by Required F.1 Isolate the affected penetration flow path(s).

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months G. As required by Required G.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months D

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).

Declare associated standby liquid control (SLC) subsystem inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Table 3.3.6.1-1.

OR H.2 Isolate the Reactor Water 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Cleanup System.

Monticello 3.3.6.1-2 Amendment No. 146 XXX

Primary Containment Isolation Instrumentation 3.3.6.1 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.

Table 3.3.6.1-1.

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

SURVEILLANCE REQUIREMENTS 2.

ra

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

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

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains primary containment isolation capability.

D SR 3.3.6.1.1 SR 3.3.6.1.2 SURVEILLANCE Perform CHANNEL CHECK.

Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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

Primary Containment Isolation Instrumentation 3.3.6.1 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

Monticello 3.3.6.1-4 Amendment No. 146

Primary Containment Isolation Instrumentation 3.3.6.1 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

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

b. Main Steam Line 1 2 E SR 3.3.6.1.2 815 psig Pressure - Low SR 3.3.6.1.4 2.

c.

d.

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

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

a.

b.

Reactor Vessel Water Level - Low Drywell Pressure -

High 1, 2, 3 1, 2, 3 2

2 F

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

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

Primary Containment Isolation Instrumentation 3.3.6.1 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

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

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

4. Reactor Core Isolation a.

b.

Flow - High ra Cooling (RCIC) System Isolation RCIC Steam Line ft RCIC Steam Supply Line Pressure - Low 1, 2, 3 1, 2, 3 2

4 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

c. RCIC Steam Line 1, 2, 3 16 F SR 3.3.6.1.2 196°F 5.

D Area Temperature -

High Reactor Water Cleanup (RWCU) System Isolation

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

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

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

Primary Containment Isolation Instrumentation 3.3.6.1 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

5. RWCU System Isolation

d. SLC System 1, 2, 3 1 H SR 3.3.6.1.6 NA Initiation

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

6. Shutdown Cooling System Isolation a.

b.

Reactor Steam ra Dome Pressure -

High Reactor Vessel ft Water Level - Low 1, 2, 3 3, 4, 5 2 2

(a)

F I

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.

D Traversing Incore Probe System Isolation a.

b.

Reactor Vessel Water Level - Low Drywell Pressure -

High 1, 2, 3 1, 2, 3 2

2 G

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.

Monticello 3.3.6.1-7 Amendment No. 146, 164, XXX

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.

APPLICABILITY: According to Table 3.3.6.2-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION A. One or more channels inoperable. raft A.1 REQUIRED ACTION Place channel in trip.

COMPLETION TIME 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for Functions 1 and 2 AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for Functions other than Functions 1 and 2 D

B. One or more Functions with secondary containment isolation capability not maintained.

B.1 Restore secondary containment isolation capability.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months C. Required Action and C.1.1 Isolate the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion penetration flow path(s).

Time not met.

OR C.1.2 Declare associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment isolation valves inoperable.

AND Monticello 3.3.6.2-1 Amendment No. 146

Secondary Containment Isolation Instrumentation 3.3.6.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2.1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months standby gas treatment (SGT) subsystem in operation.

OR C.2.2 Declare associated SGT 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable.

SURVEILLANCE REQUIREMENTS

2. ra

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

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

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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains secondary containment isolation capability.

D SR 3.3.6.2.1 SR 3.3.6.2.2 SURVEILLANCE Perform CHANNEL CHECK.

Perform CHANNEL FUNCTIONAL TEST.

FREQUENCY 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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

Secondary Containment Isolation Instrumentation 3.3.6.2 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

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

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

3. Reactor Building Ventilation Exhaust 1, 2, 3, 2 SR 3.3.6.2.1 100 mR/hr (a) 4.

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 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.

D Monticello 3.3.6.2-3 Amendment No. 146, XXX

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.

APPLICABILITY: According to Table 3.3.7.1-1 ACTIONS

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

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.

Place channel in trip.

COMPLETION TIME 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of CREF initiation capability in both trip systems 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months D

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.

Declare associated CREF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour subsystem inoperable.

Monticello 3.3.7.1-1 Amendment No. 146 148

CREF System Instrumentation 3.3.7.1 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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.

ft Perform CHANNEL CALIBRATION.

Perform CHANNEL CALIBRATION.

92 days 92 days 24 months D

SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months Monticello 3.3.7.1-2 Amendment No. 146 148

CREF System Instrumentation 3.3.7.1 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 Ventilation Exhaust Radiation - High

4. Refueling Floor Radiation - High raft 1, 2, 3, (a), (b) 1, 2, 3, (a), (b) 2 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)

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

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

Monticello 3.3.7.1-3 Amendment No. 146, 148, XXX

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.

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:

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.

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

LCO 3.0.4.b is not applicable to HPCI.

D CONDITION A. One LPCI pump inoperable.

A.1 REQUIRED ACTION 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.

OR One Core Spray subsystem inoperable.

Monticello 3.5.1-1 Amendment No. 146, XXX

ECCS - Operating 3.5.1 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.

inoperable.

D. Two LPCI subsystems D.1 Restore one LPCI 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable for reasons subsystem to OPERABLE other than Condition C status.

or G.

E. One Core Spray E.1 Restore Core Spray 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem inoperable. subsystem to OPERABLE status.

AND OR ra One or two LPCI ft One LPCI subsystem inoperable.

pump(s) inoperable.

OR E.2 OR E.3 Restore LPCI subsystem to OPERABLE status.

Restore LPCI pump(s) to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 72 hours D

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.

Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours G. Two LPCI subsystems G.1 Isolate the RHR intertie 18 hours2.083333e-4 days 0.005 hours 2.97619e-5 weeks 6.849e-6 months inoperable due to open line.

RHR intertie return line isolation valve(s).

Monticello 3.5.1-2 Amendment No. 146, 162, 184

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and H.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition G not met.

I. HPCI System I.1 Verify by administrative Immediately inoperable. means RCIC System is OPERABLE.

AND I.2 Restore HPCI System to 14 days OPERABLE status.

J. HPCI System inoperable.

AND raft Condition A, B, or C entered.

J.1 OR J.2 Restore HPCI System to OPERABLE status.

Restore low pressure ECCS injection/spray subsystem(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 72 hours OPERABLE status.

D K. One ADS valve inoperable.

K.1 Restore ADS valve to OPERABLE status.

14 days Monticello 3.5.1-3 Amendment No. 146, 162, 176, 184

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME L. Required Action and L.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition I, J, AND or K not met.

L.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR dome pressure to 150 psig.

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

OR inoperable.

OR ra Two or more ADS valves ft HPCI System inoperable and Condition D, E, or G entered.

M. Two or more low M.1 Enter LCO 3.0.3. Immediately D

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.

Monticello 3.5.1-4 Amendment No. 146, 162, 176, 184

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.

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 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.

SR 3.5.1.3 ra Verify ADS pneumatic pressure is as follows for a.

b.

ft each required ADS pneumatic supply:

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

31 days D

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 31 days 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

ECCS - Operating 3.5.1 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.

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

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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

SR 3.5.1.9 develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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.

Monticello 3.5.1-6 Amendment No. 146, 162, 167

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.10 -------------------------------NOTE------------------------------

Vessel injection/spray may be excluded.

Verify each ECCS injection/spray subsystem 24 months actuates on an actual or simulated automatic initiation signal.

SR 3.5.1.11 -------------------------------NOTE------------------------------

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.

ft

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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

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

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 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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: ra--------------------------------------------------------------------------------------------------

ft 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 DCONDITION A. One rRequired ECCS injection/spray subsystem inoperable.

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

COMPLETION TIME 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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.

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

C. DRAIN TIME < 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.1 Verify secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Monticello 3.5.2-1 Amendment No. 146, XXX

ECCS - Shutdown 3.5.2 ACTIONS (continued) and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . containment boundary is capable of being C. Two required ECCS established in less than the injection/spray DRAIN TIME.

subsystems inoperable.

AND C.2 Verify each secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months containment penetration flow path is capable of being isolated in less than the DRAIN TIME.

AND C.3 Verify one standby gas 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months raft C.1 AND treatment subsystem is capable of being placed in operation in less than the DRAIN TIME.

Initiate action to suspend OPDRVs.

Immediately 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C.2 Restore one required D

D. DRAIN TIME < 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . D.1 ECCS injection/spray subsystem to OPERABLE status.

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

Required ECCS injection/spray subsystem or additional method of Immediately 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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Monticello 3.5.2-2 Amendment No. 146, XXX

ECCS - Shutdown 3.5.2 ACTIONS (continued)

AND D.2 Initiate action to establish Immediately 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 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.

Initiate action to restore DRAIN TIME to 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Immediately Immediately not met.

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

Monticello 3.5.2-3 Amendment No. 146, XXX

ECCS - Shutdown 3.5.2 ACTIONS (continued)

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.

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

SURVEILLANCE FREQUENCY D

SR 3.5.2.1 SR 3.5.2.21 Verify DRAIN TIME 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Verify, for each a required ECCS injection/spray subsystem, the:

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 12 hours

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.

Monticello 3.5.2-4 Amendment No. 146, XXX

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.

raft D

Monticello 3.5.2-5 Amendment No. 146, XXX

ECCS - Shutdown 3.5.2 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.

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 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.

ft 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.

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.

SR 3.5.2.75 -------------------------------NOTE------------------------------

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

ECCS - Shutdown 3.5.2 SURVEILLANCE FREQUENCY subsystem operates actuates on a manual an actual 24 months or simulated automatic initiation signal.

raft D

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.

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 A. RCIC System inoperable.

raft A.1 AND REQUIRED ACTION Verify by administrative means High Pressure Coolant Injection System is OPERABLE.

COMPLETION TIME Immediately D

B. Required Action and associated Completion Time not met.

A.2 B.1 AND Restore RCIC System to OPERABLE status.

Be in MODE 3.

14 days 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months dome pressure to 150 psig.

Monticello 3.5.3-1 Amendment No. 146, XXX

RCIC System 3.5.3 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, 31 days 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------------------------------

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

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.

In accordance with the Inservice Testing Program SR 3.5.3.3 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after D 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 24 months 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.

Monticello 3.5.3-2 Amendment No. 146, 189

PCIVs 3.6.1.3 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.

3.

4. ra Separate Condition entry is allowed for each penetration flow path.

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,"

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

CONDITION REQUIRED ACTION COMPLETION TIME D

A. ------------NOTE------------

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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for main steam line AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main One or more penetration with flow through the valve steam line flow paths with one secured.

PCIV inoperable for reasons other than AND Condition D or E.

Monticello 3.6.1.3-1 Amendment No. 146 148

PCIVs 3.6.1.3 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 Once per 31 days for raft 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

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------ B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two PCIVs. and de-activated automatic

valve, closed manual valve, or blind flange.

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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for Only applicable to with only one PCIV.

ra penetration flow paths ft One or more penetration flow paths with one PCIV inoperable.

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

excess flow check valves (EFCVs) and penetrations with a closed system AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCVs and penetrations with a closed system D AND Monticello 3.6.1.3-3 Amendment No. 146 148

PCIVs 3.6.1.3 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 Once per 31 days for raft 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

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration D.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

leakage limits.

AND D.2 --------------NOTES-------------

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.

Verify the affected penetration flow path is Once per 31 days for isolation devices isolated. outside containment D

E. One or more MSIVs with leakage rate not within limits.

E.1 Restore leakage rate to within limits.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.1.3-5 Amendment No. 146 148

PCIVs 3.6.1.3 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).

required to be OPERABLE during OR MODE 4 or 5.

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

SR 3.6.1.3.1 ra SURVEILLANCE REQUIREMENTS ft SURVEILLANCE

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.

D ---------------------------------------------------------------------

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

PCIVs 3.6.1.3 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 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.

SR 3.6.1.3.3 ra

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

1. Valves and blind flanges in high radiation areas 2.

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)

SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is 24 months 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.

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.

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°.

ft 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

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

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.

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 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.

Be in MODE 3.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 12 hours met.

D C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the B.2 C.1 Be in MODE 4.

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

LCO 3.0.3 is not applicable.

Suspend movement of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Immediately secondary containment recently irradiated fuel or during OPDRVs. assemblies in the secondary containment.

AND C.2 Initiate action to suspend Immediately OPDRVs.

Monticello 3.6.4.1-1 Amendment No. 146, XXX

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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of vacuum water gauge.

SR 3.6.4.1.2 Verify all secondary containment equipment hatches 31 days are closed and sealed.

SR 3.6.4.1.3 Verify one secondary containment access door in 31 days 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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months using one SGT subsystem at a flow rate 4000 cfm.

ft TEST BASIS for each SGT subsystem D

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)

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.

ra Separate Condition entry is allowed for each penetration flow path.

ft

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months D

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.

Monticello 3.6.4.2-1 Amendment No. 146, XXX

SCIVs 3.6.4.2 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 Once per 31 days Only applicable to ra penetration flow paths ft B. ------------NOTE------------

with two isolation valves.

B.1 penetration flow path is isolated.

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months One or more penetration D

flow paths with two SCIVs inoperable.

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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.4.2-2 Amendment No. 146

SCIVs 3.6.4.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 ---------------NOTE--------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A or B -------------------------------------

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.

or during OPDRVs.

AND D.2 Initiate action to suspend Immediately OPDRVs.

SR 3.6.4.2.1 raft SURVEILLANCE REQUIREMENTS SURVEILLANCE

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

1. Valves and blind flanges in high radiation areas FREQUENCY may be verified by use of administrative means.

D 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.

SR 3.6.4.2.2 Verify the isolation time of each power operated, 92 days 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.

Monticello 3.6.4.2-3 Amendment No.146, XXX

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.

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 inoperable.

ra A. One SGT subsystem ft B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3.

A.1 B.1 AND Restore SGT subsystem to OPERABLE status.

Be in MODE 3.

7 days 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D

C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the

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

LCO 3.0.3 is not applicable.

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.

AND Monticello 3.6.4.3-1 Amendment No. 146, XXX

SGT System 3.6.4.3 ACTIONS (continued)

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

D. Two SGT subsystems D.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3.

E. Two SGT subsystems E.1 ---------------NOTE--------------

inoperable during LCO 3.0.3 is not applicable.

movement of recently -------------------------------------

irradiated fuel assemblies in the Suspend movement of Immediately ra secondary containment or during OPDRVs.

ft AND E.2 recently irradiated fuel assemblies in secondary containment.

Initiate action to suspend OPDRVs.

Immediately D

SURVEILLANCE REQUIREMENTS SR 3.6.4.3.1 SURVEILLANCE 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.

Monticello 3.6.4.3-2 Amendment No. 146, 181, XXX

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.

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 ra A. One CREF subsystemft inoperable for reasons other than Condition B.

A.1 REQUIRED ACTION Restore CREF subsystem to OPERABLE status.

COMPLETION TIME 7 days D

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

B.1 AND B.2 Initiate action to implement mitigating actions.

Verify mitigating actions ensure CRE occupant Immediately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months exposures to radiological, chemical and smoke hazards will not exceed limits.

AND B.3 Restore CRE boundary to OPERABLE status. 90 days Monticello 3.7.4-1 Amendment No. 146, 160, 175, XXX

CREF System 3.7.4 raft D

Monticello 3.7.4-2 Amendment No. 146, 160, XXX

CREF System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and --------------------NOTE-------------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not ------------------------------------------------

met during movement of recently irradiated fuel D.1 Place OPERABLE CREF Immediately assemblies in the subsystem in pressurization secondary containment mode.

ra or during OPDRVs.

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

Immediately D.2.2 Initiate action to suspend Immediately D

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

E.1 OPDRVs.

Enter LCO 3.0.3. Immediately Monticello 3.7.4-3 Amendment No. 146, 160, XXX

CREF System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREF subsystems --------------------NOTE-------------------

inoperable during LCO 3.0.3 is not applicable.

movement of recently ------------------------------------------------

irradiated fuel assemblies in the F.1 Suspend movement of Immediately secondary containment recently irradiated fuel or during OPDRVs. assemblies in the secondary containment.

OR AND One or more CREF subsystems inoperable F.2 Initiate action to suspend Immediately due to an inoperable OPDRVs.

CRE boundary during ra movement of recently irradiated fuel assemblies in the ft secondary containment or during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY D

SR 3.7.4.1 SR 3.7.4.2 Operate each CREF subsystem for 15 continuous minutes.

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

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.

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

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.

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 B. Two control room ra ventilation subsystem inoperable.

ft ventilation subsystems inoperable.

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

Verify control room area temperature < 90°F.

30 days Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B.2 Restore one control room 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months D

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.

Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and --------------------NOTE-------------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not ------------------------------------------------

met during movement of irradiated fuel D.1 Place OPERABLE control Immediately assemblies in the room ventilation subsystem secondary containment in operation.

or during OPDRVs.

OR Monticello 3.7.5-1 Amendment No. 146, 148, 154, XXX

Control Room Ventilation System 3.7.5 ACTIONS (continued)

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

AND D.2.2 Initiate action to suspend Immediately OPDRVs.

E. Required Action and --------------------NOTE-------------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition B not ------------------------------------------------

met during movement of ra recently irradiated fuel assemblies in the secondary containment ft or during OPDRVs.

E.1 AND E.2 Suspend movement of irradiated fuel assemblies in the secondary containment.

Initiate actions to suspend OPDRVs.

Immediately Immediately D

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:

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 ACTIONS ra LCO 3.0.3 is not applicable.

ft containment.

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

CONDITION REQUIRED ACTION COMPLETION TIME D

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 Immediately feature(s), with no offsite power available, inoperable.

OR Monticello 3.8.2-1 Amendment No. 146, 148, XXX

AC Sources - Shutdown 3.8.2 ACTIONS (continued)

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

AND A.2.2 Suspend movement of Immediately 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.2.34 Initiate action to restore required offsite power circuit to OPERABLE status.

Immediately D

B. One required EDG inoperable.

B.1 AND B.2 Suspend CORE ALTERATIONS.

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

AND Immediately B.3 Initiate action to suspend OPDRVs.

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

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-----------------------------

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 In accordance of Specification 3.8.1, except SR 3.8.1.6, are with applicable applicable. SRs raft D

Monticello 3.8.2-3 Amendment No. 146

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 -

Shutdown."

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

ACTIONS

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

CONDITION A. Required DC electrical power subsystem inoperable.

ra LCO 3.0.3 is not applicable.

ft A.1 REQUIRED ACTION Suspend CORE ALTERATIONS.

COMPLETION TIME Immediately AND D A.2 AND 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 Immediately A.34 Initiate action to restore required DC electrical power subsystem to OPERABLE status.

Monticello 3.8.5-1 Amendment No. 146, 148, XXX

DC Sources - Shutdown 3.8.5 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 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.

raft D

Monticello 3.8.5-2 Amendment No. 146

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.

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 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.

COMPLETION TIME Immediately OR D A.2.1 A.2.2 AND Suspend CORE ALTERATIONS.

Suspend handling of recently irradiated fuel Immediately Immediately assemblies in the secondary containment.

AND Immediately 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

Distribution Systems - Shutdown 3.8.8 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.

AND A.2.45 Declare associated Immediately 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.

FREQUENCY 7 days D

Monticello 3.8.8-2 Amendment No. 146, XXX

v t e Letter Sequence Draft Other
CAC:MG0155, (Open)
Initiation Acceptance... Administration Meeting Questions Answers Results Approval... Other:
MONTHYEAR2017-09-29 [Table View]

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