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Technical Specifications, Appendix a
	ML063070072
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Site:	Monticello
Issue date:	10/29/2006
From:	; Plant Licensing Branch III-2
To:	Conway J; Nuclear Management Co
	Merzke, D., NRR/ADRO/DLR/RLRB, 415-3777
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APPENDIX A TO FACILITY OPERATING LICENSE DPR-22 TECHNICAL SPECIFICATIONS FOR MONTICELLO NUCLEAR GENERATING PLANT UNIT1 MONTICELLO, MINNESOTA NORTHERN STATES POWER COMPANY NUCLEAR MANAGEMENT COMPANY, LLC DOCKET NO. 50-263 October 29, 2006

TABLE OF CONTENTS Page Number 1.0 USE AND APPLICATION 1.1 Defin itio ns ............................................. ........................................... ....... 1 .1-1 1.2 Logical C onnectors .............................................................................................. 1.2-1 1.3 C om pletion T im es ................................................................................................ 1.3-1 1.4 Freq uency ........................................................................................................... 1.4-1 2.0 SA FETY LIM ITS (S Ls) .............................................................................................. 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 A nom alies ................................................................................... 3.1.2-1 3.1.3 Control Rod OPERABILITY ........................................................................ 3.1.3-1 3.1.4 Control Rod Scram Times ........................................................................... 3.1.4-1 3.1.5 Control Rod Scram Accumulators ............................................................... 3.1.5-1 3.1.6 Rod Pattern C ontrol .................................................................................... 3.1.6-1 3.1.7 Standby Liquid Control (SLC) System ......................................................... 3.1.7-1 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves ............................. 3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ........................................... 3.2.1-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR) .................... 3.2.2-1 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) (Optional) ............................ 3.2.3-1 3.3 1NSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation ......... .... ..... 3.3.1.1-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation ........................ 3.8.1.2-1 3.3.2.1 Control Rod Block Instrumentation ........................... 3.3.2.1-1 3.3.2.2 Feedwater Pump and Main Turbine High Water Level Trip Instrum entation ..................................................................................

3.3.2.2-1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation ..................................... 3.3.3.1-1 3.3.3.2 Alternate Shutdown System ..................................................................... 3.3.3.2-1 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ................................. ....... .. 3.3.4.1-1 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation...................... 3.3.5.1-1 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation .............. 3.3.5.2-1 3.3.6.1 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 Instrum entation ....................................................... ......................... 3.3.7.1-1 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 Monticello i Amendment No. 146

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 P um ps .................................................................................................. 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 S hutd ow n .............................................................................................. 3 .4 .7-1 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold S hutd ow n .............................................................................................. 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) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating ....................................................................................... 3.5.1-1 3.5.2 ECCS - Shutdown ....................................................................................... 3.5.2-1 3 .5.3 R C IC S ystem .............................................................................................. 3.5.3-1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment ............................................................................... 3.6.1.1-1 3.6.1.2 Primary Containment Air Lock ................................................................. 3.6.1.2-1 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ....................................... 3.6.1.3-1 3.6.1.4 Drywell Air Temperature .......................................................................... 3.6.1.4-1 3.6.1.5 Low-Low Set (LLS) Valves ....................................................................... 3.6.1.5-1 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers ................. 3.6.1.6-1 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers ............................... 3.6.1.7-1 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray ......................................... 3.6.1.8-1 3.-62:1- -Suppression-Pool-Average-Temperature....................................... 3.6.2:1-1 3.6.2.2 Suppression Pool W ater Level ................................................................. 3.6.2.2-1 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ....................... 3.6.2.3-1 3.6.3.1 Primary Containment Oxygen Concentration ........................................... 3.6.3.1-1 3.6.4.1 Secondary Containment .......................................................................... 3.6.4.1-1 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ................................... 3.6.4.2-1 3.6.4.3 Standby Gas Treatment (SGT) System ................................................... 3.6.4.3-1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System .......................... 3.7.1-1 3.7.2 Emergency Service Water (ESW) System and Ultimate Heat S in k (U H S ) ............................................................................................ 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 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 M1onticello ii oAmendment No. 146

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 ................................ I.... 3.9.7-1 3.9.8 Residual Heat Removal (RHR) - Low Water Level ...................................... 3.9.8-1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation ................................... 3.10.1-1 3.10.2 Reactor Mode Switch Interlock Testing ..................................................... 3.10.2-1 3.10.3 Single Control Rod Withdrawal - Hot Shutdown ........................................ 3.10.3-1 3.10.4 Sing!e Control Rod Withdrawal - Cold Shutdown .................. 3.10.4-1 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling .............................. 3.10.5-1 3.10.6 Multiple Control Rod Withdrawal - Refueling ............................................. 3.10.6-1 3.10.7 Control Rod Testing - Operating ............................................................... 3.10.7-1 3.10.8 SHUTDOW N MARGIN (SDM) Test - Refueling ........................................ 3.10.8-1 4.0 DESIGN FEATURES ................................................................................................ 4.0-1 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage 5.0 ADMINISTRATIVE CONTROLS 5 .1 R esponsib ility ......................................................................................... 5.1-1 5 .2 O rg aniz atio n ........................................................................................................ 5.2-1 5.3 Unit Staff Qualifications ....................................................................................... 5.3-1 5 .4 P roced ure s .......................................................................................................... 5 .4-1 5.5 Programs and Manuals ....................................................................................... 5.5-1 5.6 Reporting Requirements ..................................................................................... 5.6-1 5.7 High R ad iation A rea ............................................................................................ 5.7-1 M onnft ,.1ll iii Amendment No. 146

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

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

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

1.1-1 Amendment No. 146 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.

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

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, "Calculation of Distance Factors for Power and Test Reactor Sites," or those listed in Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

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

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE; Monticello 1.1 Amendment No. 146

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.

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

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

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

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

Monticello 1.1-3 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).

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 1775 MWt.

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

SHUTDOWN MARGIN (SDM) SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical assuming that:

a. The reactor is xenon free;

b. The moderator temperature is 68 0 F; and

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

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.

1.1-4 Amendment No. 146 Monticello Monticello 1.1-4 Amendment No. 146

Definitions 1.1 1.1 Definitions TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME shall be RESPONSE TIME that time interval from when the main turbine trip solenoid is activated until 80% of the turbine bypass capacity is established. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

Monticello 1.1-5 Amendment No. 146

Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES AVERAGE REACTOR COOLANT REACTOR MODE TEMPERATURE MODE TITLE SWITCH POSITION (OF) 1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot Standby NA 3 Hot Shutdown(a) Shutdown > 212 4 Cold Shutdown(a) Shutdown *212 5 Refueling(b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

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

Monticello 1.1-6 lAmendment No. 146

Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Specifications (TS) to discriminate between, and yet connect, discrete Conditions, Required Actions, Completion Times, Surveillances, and Frequencies. The only logical connectors that appear in TS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Actions. These levels are identified by the placement (or nesting) of the logical connectors and by the number assigned to each Required Action. The first level of logic is identified by the first digit of the number assigned to a Required Action and the placement of the logical connector in the first level of nesting (i.e., left justified with the number of the Required Action).

The successive levels of logic are identified by additional digits of the Required Action number and by successive indentions of the logical connectors.

When logical connectors are used to state a Condition, Completion Time, Surveillance, or Frequency, only the first level of logic is used, and the logical connector is left justified with the statement of the Condition, Completion Time, Surveillance, or Frequency.

EXAMPLES The following examples illustrate the use of logical, connectors.

EXAMPLE 1.2-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Verify....

AND A.2 Restore...

In this example the logical connector AND is used to indicate that when in Condition A, both Required Actions A.1 and A.2 must be completed.

Monticello 1.21-1 Amendment No. 146

Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)

EXAMPLE 1.2-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip ...

OR A.2.1 Verify...

AND A.2.2.1 Reduce...

OR A.2.2.2 Perform...

OR A.3 Align...

This example represents a more complicated use of logical connectors.

Required Actions A.1, A.2, and A.3 are alternative choices, only one of which must be performed as indicated by the use of the logical connector OR and the left justified placement. Any one of these three Actions may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical connector AND. Required Action A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Monticello 1.2-2 Amendment No. 146

Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Limiting Conditions for Operation (LCOs) specify minimum requirements for ensuring safe operation of the unit. The ACTIONS associated with an LCO state Conditions that typically describe the ways in which the requirements of the LCO can fail to be met. Specified with each stated Condition are Required Action(s) and Completion Time(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Action. It is referenced to the time of discovery of a situation (e.g., inoperable equipment or variable not within limits) that requires entering an ACTIONS Condition unless otherwise specified, providing the unit is in a MODE or specified condition stated in the Applicability of the LCO. Required Actions must be completed prior to the expiration of the specified Completion Time. An ACTIONS Condition remains in effect and the Required Actions apply until the Condition no longer exists or the unit is not within the LCO Applicability.

If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions), the Required Actions for each Condition must be performed within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be inoperable or not within limits, will not result in separate entry into the Condition, unless specifically stated. The Required Actions of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

However, when a subsequent division, subsystem, component, or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this Completion Time extension, two criteria must first be met. The subsequent inoperability:

a. Must exist concurrent with the first inoperability; and

b. Must remain inoperable or not within limits after the first inoperability is resolved.

Monticello 1.3-1 Amendment No. 146

Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)

The total Completion Time allowed for completing a Required Action to address the subsequent inoperability shall be limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or

b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extensions do not apply to those Specifications that have exceptions that allow completely separate re-entry into the Condition (for each division, subsystem, component, or variable expressed in the Condition) and separate tracking of Completion Times based on this re-entry. These exceptions are stated in individual Specifications.

The above Completion Time extension does not apply to a Completion Time with a modified "time zero." This modified "time zero" may be expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase "from discovery . .

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

Monticello 1.3-12 Amendment No. 146

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-1 ACTFONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Condition B has two Required Actions. Each Required Action has its own separate Completion Time. Each Completion Time is referenced to the time that Condition B is entered.

The Required Actions of Condition B are to be in MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for reaching MODE 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Monticello 1.3-3 Amendment No. 146

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pump A.1 Restore pump to 7 days inoperable. OPERABLE status.

B. Required B-1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared inoperable, Condition A is entered. If the pump is not restored, to OPERABLE status within 7 days, Condition B is also entered and the Completion Time clocks for Required Actions B.1 and B.2 start. If the inoperable pump is restored to OPERABLE status after Condition B is entered, Conditions A and B are exited, and therefore, the Required Actions of Condition B may be terminated.

When a second pump is declared inoperable while the first pump is still inoperable, Condition A is not re-entered for the second pump.

LCO 3.0.3 is entered, since the ACTIONS do not include a Condition for more than one inoperable pump. The Completion Time clock for Condition A does not stop after LCO 3.0.3 is entered, but continues to be tracked from the time Condition A was initially entered.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has not expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition A.

While in LCO 3.0.3, if one of the inoperable pumps is restored to OPERABLE status and the Completion Time for Condition A has expired, LCO 3.0.3 may be exited and operation continued in accordance with Condition B. The Completion Time for Condition B is tracked from the time the Condition A Completion Time expired.

Monticello 1.3-4 Amendment No. 146

Completion Times 1.3 1,3 Completion Times EXAMPLES (continued)

On restoring one of the pumps to OPERABLE status, &e Condition A Completion Time is not reset, but continues from the time the first pump was declared inoperable. This Completion Time may be extended if the pump restored to OPERABLE status was the first inoperable pump. A 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months extension to the stated 7 days is allowed, provided this does not result in the second pump being inoperable for > 7 days.

EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore Function X 7 days Function X subsystem to subsystem OPERABLE status.

inoperable.

B. One B.1 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y subsystem to subsystem OPERABLE status.

inoperable.

C. One C.A Restore Function X 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X subsystem to subsystem OPERABLE status.

inoperable.

OR AND C.2 Restore Function Y 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months One subsystem to Function Y OPERABLE status.

subsystem inoperable.

1.3-5 Amendment No. 146 Monticello Monticello 1.3-5 A Amendrnent No. 146

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem starting from the time each subsystem was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

If Required Action C.2 is completed within the specified Completion Time, Conditions B and C are exited. If the Completion Time for Required Action A.1 has not expired, operation may continue in accordance with Condition A. The remaining Completion Time in Condition A is measured from the time the affected subsystem was declared inoperable (i.e., initial entry into Condition A).

It is possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. However, doing so would be inconsistent with the basis of the Completion Times. Therefore, there shall be administrative controls to limit the maximum time allowed for any combination of Conditions that result in a single contiguous occurrence of failing to meet the LCO. These administrative controls shall ensure that the Completion Times for those Conditions are not inappropriately extended.

Monticello 1.3-6 Amendment No. 146

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status..

inoperable.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months A single Completion Time is used for any number of valves inoperable at the same time. The Completion Time associated with Condition A is based on the initial entry into Condition A and is not tracked on a per valve basis. Declaring subsequent valves inoperable, while Condition A is still in effect, does not trigger the tracking of separate Completion Times.

Once one of the valves has been restored to OPERABLE status, the Condition A Completion Time is not reset, but continues from the time the first valve was declared inoperable. The Completion Time may be extended if the valve restored to OPERABLE status was the first inoperable valve. The Condition A Completion Time may be extended for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one or more valves are stillinoperable, Condition B is entered.

1.3-7 Amendment No. 146 Monticello Monticello 1.3-7 Amendment No. 146

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-5 ACTIONS Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months valves OPERABLE status.

inoperable.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months The Note above the ACTIONS Table is a method of modifying how the Completion Time is tracked. If this method of modifying how the Completion Time is tracked was applicable only to a specific Condition, the Note would appear iri that Condition rather than at the top of the ACTIONS Table.

The Note allows Condition A to be entered separately for each inoperable valve, and Completion Times tracked on a per valve basis. When a valve is declared inoperable, Condition A is entered and its Completion Time starts. If subsequent valves are declared inoperable, Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated with subsequent valves in Condition A expire, Condition B is entered separately for each valve and separate Completion Times start and are tracked for each valve. If a valve that caused entry into Condition B is restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and tracking of separate Completion Times, Completion Time extensions do not apply.

Monticello 1.31-8 Amendment No. 146

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform SR 3.x.x.x. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable.

OR A.2 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months POWER to

50% RTP.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated Completion Time not met.

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a "once per" Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2),

Condition.B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Action A.1 or A.2 is met, Condition B is exited and operation may then continue in Condition A.

1.3-9 Amendment No. 146 Monticello Monticello 1.3-9 Amendment No. 146

Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)

EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem isolated.

inoperable. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore subsystem 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action and associated AND Completion Time not met. B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Action A.1 has two Completion Times. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of Required Action A.1.

If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval from the previous performance (plus the extension allowed by SR 3.0.2), Condition B is entered. The Completion Time clock for Condition A does not stop after Condition B is entered, but continues from the time Condition A was initially entered. If Required Action A. I is met after Condition B is entered, Condition B is exited and operation may continue in accordance with Condition A, provided the Completion Time for Required Action A.2 has not expired.

Monticello 1.13-10 Amendment No. 146

Completion Times 1.3 1.3 Completion Times IMMEDIATE When "Immediately" is used as a Completion Time, the Required Action COMPLETION TIME should be pursued without delay and in a controlled manner.

Monticello 1.3-11 Amendment No. 146

Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Surveillance Requirement (SR) has a specified Frequency in which the Surveillance must be met in order to meet the associated LCO. An understanding of the correct application of the specified Frequency is necessary for compliance with the SR.

The "specified Frequency" is referred to throughout this section and each of the Specifications of Section 3.0, "Surveillance Requirement (SR)

Applicability." The "specified Frequency" consists of the requirements of the Frequency column of each SR as well as certain Notes in the Surveillance column that modify performance requirements.

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are "otherwise stated" conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both.

Situations where a Surveillance could be required (i.e., its Frequency could expire), but where it is not possible or not desired that it be performed until sometime after the associated LCO is within its Applicability, represent potential SR 3.0.4 conflicts. To avoid these conflicts, the SR (i.e., the Surveillance or the Frequency) is stated such that it is only "required" when it can be and should be performed. With an SR satisfied, SR 3.0.4 imposes no restriction.

The use of "met" or "performed" in these instances conveys specific meanings. A Surveillance is "met" only when the acceptance criteria are satisfied. Known failure of the requirements of a Surveillance, even without a Surveillance specifically being "performed," constitutes a Surveillance not "met." "Performance" refers only to the requirement to specifically determine the ability to meet the acceptance criteria.

Some Surveillances contain Notes that modify the Frequency of performance or the conditions during which the acceptance criteria must be satisfied. For these Surveillances, the MODE-entry restrictions of SR 3.0.4 may not apply. Such a Surveillance is not required to be performed prior to entering a MODE or other specified condition in the Applicability of the associated LCO if any of the following three conditions are satisfied:

1.4-1 Amendment No. 146 Monticello Monticello 1.4-1 Amendment No. 146

Frequency 1.4 1.4 Frequency DESCRIPTION (continued)

a. The Surveillance is not required to be met in the MODE or other specified condition to be entered;

b. The Surveillance is required to be met in the MODE or other specified condition to be entered, but has been performed within the specified Frequency (i.e., it is current) and is known not to befailed; or

c. The Surveillance is required to be met, but not performed, in the MODE or other specified condition to be entered, and is known not to be failed.

Examples 1.4-3, 1.4-4, 1.4-5, and 1.4-6 discuss these special situations.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the LCO (LCO not shown) is MODES 1,-2, and 3.

EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the associated Surveillance must be performed at least one time. Performance of the Surveillance initiates the subsequent interval. Although the Frequency is stated as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval specified in the Frequency is allowed by SR 3.0.2 for operational flexibility. The measurement of this interval continues at all times, even when the SR is not required to be met per SR 3.0.1 (such as when the equipment is inoperable, a variable is outside specified limits, or the unit is outside the Applicability of the LCO).

If the interval specified by SR 3.0.2 is exceeded while the unit is in a MODE or other specified condition in the Applicability of the LCO, and the performance of the Surveillance is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then SR 3.0.3 becomes applicable.

Monticello 1.4-2 Amendment No. 146

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, then SR 3.0.4 becomes applicable. The Surveillance must be performed within the Frequency requirements of SR 3.0.2, as modified by SR 3.0.3, prior to entry into the MODE or other specified condition or the LCO is considered not met (in accordance with SR 3.0.1) and LCO 3.0.4 becomes applicable.

EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

_ 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to Ž_25% RTP, the Surveillance must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified Frequency (assuming no other Frequencies are connected by "AND").

This type of Frequency does not qualify for the 25% extension allowed by SR 3.0.2. "Thereafter" indicates future performances must be established per SR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to

< 25% RTP, the measurement of both intervals stops. New intervals start upon reactor power reaching 25% RTP.

1.4-3 Amendment No. 146 Monticello Monticello 1.4-3 Amendment No. 146

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

NOTE------

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

_>25% RTP.

Perform channel adjustment. 7 days The interval continues, whether or not the unit operation is < 25% RTP between performances.

As the Note modifies the required performance of the Surveillance, it is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after power reaches > 25% RTP to perform the Surveillance.

The Surveillance is still considered to be within the "specified Frequency."

Therefore, if the Surveillance was not performed within the 7 day interval (plus the extension allowed by SR 3.0.2), but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO.

Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power __25% RTP.

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for completing the Surveillance. If the Surveillance was not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months interval, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

1.4-4 Amendment No. 146 Monticello Monticello 1.4-4 Amendment No. 146

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1.

Verify leakage rates are within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Surveillance do not have to be met until the unit is in MODE 1. The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance was not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), but the unit was not in MODE 1, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency was not met), SR 3.0.4 would require satisfying the SR.

1.4-5 Amendment No. 146 Monticello Monticello 1.4-5 Amendment No. 146

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be performed in MODE 1.

Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MOPE 1, 2, or 3 (the assumed Applicability of the associated LCO) between performances.

As the Note modifies the required performance of the Surveillance, the Note is construed to be part of the "specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1, this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance. The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to entering MODE 1.

Therefore, if the Surveillance was not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not result in entry into MODE 1.

Once the unit reaches MODE 1, the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Surveillance had been performed. If the Surveillance was not performed prior to entering MODE 1, there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.

1.4-6 Amendment No. 146 Monticello 1.4-6 Amendment No. 146

Frequency 1.4 1.4 Frequency EXAMPLES (continued)

EXAMPLE 1.4-6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY NOTE -------------

Not required to be met in MODE 3.

Verify parameter is within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-6 specifies that the requirements of this Surveillance do not have to be met while the unit is in MODE 3 (the assumed Applicability of the associated LCO is MODES 1, 2, and 3). The interval measurement for the Frequency of this Surveillance continues at all times, as described in Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Surveillance. Therefore, if the Surveillance was not performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months interval (plus the extension allowed by SR 3.0.2), and the unit was in MODE 3, there would be no failure of the SR nor failure to meet the LCO. Therefore, no violation of SR 3.0.4 occurs when changing MODES to enter MODE 3, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency exceeded, provided the MODE change does not result in entry into MODE 2. Prior to entering MODE 2 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency was not met), SR 3.0.4 would require satisfying the SR.

Monticello 1.4-7 Amendment No. 146

SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 785 psig or core flow

< 10% rated core flow:

THERMAL POWER shall be *25% RTP.

2.1.1.2 With the reactor steam dome pressure __785 psig and core flow

>10% rated core flow:

MCPR shall be > 1.10 for two recirculation loop operation or > 1.12 for single recirculation loop operation.

2.1.1.3 Reactor vessel water level shall be greater than the top of active irradiated fuel.

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be

1332 psig.

2.2 SL VIOLATIONS With any SL violation, the following actions shall be completed within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

2.2.1 Restore compliance with all SLs; and 2.2.2 Insert all insertable control rods.

Monticello 2.0-1 Amendment No. 146

LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) Applicability LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2, LCO 3.0.7, and LCO 3.0.8.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0:5 and LCO 3.0.6.

If the LCO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the Required Action(s) is not required, unless otherwise stated.

LCO 3.0.3 When an LCO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, the unit shall be placed in a MODE or other specified condition in which the LCO is not applicable. Action shall be initiated within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to place the unit, as applicable, in:

a. MODE 2 within 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ;

b. MODE 3 within 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months ; and

c. MODE 4 within 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months .

Exceptions to this Specification are stated in the individual Specifications.

Where corrective measures are completed that permit operation in accordance with the LCO or ACTIONS, completion of the actions required by LCO 3.0.3 is not required.

LCO 3.0.3 is only applicable in MODES 1, 2, and 3.

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made:

a. When the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time;

b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications; or

c. When an allowance is stated in the individual value, parameter, or other Specification.

Monticello 3.0-1 Amendment No. 146

LCO Applicability 3.0 LCO Applicability LCO 3.0.4 (continued)

This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

LCO 3.0.5 Equipment removed from service or declared inoperable to comply with ACTIONS may be returned to service under administrative control solely to perform testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an exception to LCO 3.0.2 for the system returned to service under administrative control to perform the testing required to demonstrate OPERABILITY.

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, an evaluation shall be performed in accordance with Specification 5.5.10, "Safety Function Determination Program (SFDP)." If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

When a support system's Required Action directs a supported system to be declared inoperable or directs entry into Conditions and Required Actions for a supported system, the applicable Conditions and Required Actions shall be entered in accordance with LCO 3.0.2.

LCO 3.0.7 Special Operations LCOs in Section 3.10 allow specified Technical Specifications (TS) requirements to be changed to permit performance of special tests and operations. Unless otherwise specified, all other TS requirements remain unchanged. Compliance with Special Operations LCOs is optional. When a Special Operations LCO is desired to be met but is not met, the ACTIONS of the Special Operations LCO shall be met.

When a Special Operations LCO is not desired to be met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with the other applicable Specifications.

LCO 3.0.8 When one or more required snubbers are unable to perform their associated support function(s), any affected supported LCO(s) are not required to be declared not met solely for this reason if risk is assessed and managed, and:

3.0-2 Amendment No. 146 Monticello 3.0-2 Amendment No. 146

LCO Applicability 3.0 LCO Applicability LCO 3.0.8 (continued)

a. The snubbers not able to perform their associated support function(s) are associated with only one subsystem of a multiple subsystem supported system or are associated with a single subsystem supported system and are able to perform their associated support function within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; or

b. The snubbers not able to perform their associated support function(s) are associated with more than one subsystem of a multiple subsystem supported system and are able to perform their associated support function within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

At the end of the specified period the required snubbers must be able to perform their associated support function(s), or the affected supported system LCO(s) shall be declared not met.

Monticello 3.0-3 Amendment No. 146

SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR.) Applicability SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR.

Failure to meet a Surveillance, whether such failure is experienced during the performance of the Surveillance or between performances of the Surveillance, shall be failure to meet the LCO. Failure to perform a Surveillance within the specified Frequency shall be failure to meet the LCO except as provided in SR 3.0.3. Surveillances do not have to be performed on inoperable equipment or variables outside specified limits.

SR 3.0.2 The specified Frequency for each SR is met if the Surveillance is performed within 1.25 times the interval specified in the Frequency, as measured from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does not apply.

If a Completion Time requires periodic performance on a "once per...

basis, the above Frequency extension applies to each performance after the initial performance.

Exceptions to this Specification are stated in the individual Specifications.

SR 3.0.3 If it is discovered that a Surveillance was not performed within its specified Frequency, then compliance with the requirement to declare the LCO not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance. A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and the risk impact shall be managed.

If the Surveillance is not performed within the delay period, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

When the Surveillance is performed within the delay period and the Surveillance is not met, the LCO must immediately be declared not met, and the applicable Condition(s) must be entered.

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR '3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.

3.0-4 Amendment No. 146 Monticello Monticello 3.0-4 Amendment No. 146

SR Applicability 3.0 SR Applicability SR 3.0.4 (continued)

This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.

Monticello 3.0-5 Amendment No. 146

SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)

LCO 3.1.1 SDM shall be:

a. _ 0.38% Ak/k, with the highest worth control rod analytically determined; or

b. _Ž0.28% Ak/k, with the highest worth control rod determined by test.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limits in A.1 Restore SDM to within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months MODE 1 or 2. limits.

B. Required Action and B.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 not met.

C. SDM not within limits in C.1 Initiate action to fully insert Immediately MODE 3. all insertable control rods.

D. SDM not within limits in D.1 Initiate action to fully insert Immediately MODE 4. all insertable control rods.

'AND D.2 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment to OPERABLE status.

AND Monticello 3.1.1-1 Amendment No. 146

SDM 3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D.3 Initiate action to restore one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months standby gas treatment (SGT) subsystem to OPERABLE status.

AND D.4 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolation capability in each required secondary containment penetration flow path not isolated.

E. SDM not within limits in E.1 Suspend CORE Immediately MODE 5. ALTERATIONS except for control rod insertion and fuel assembly removal.

AND E.2 Initiate action to fully insert Immediately all insertable control rods in core cells containing one or more fuel assemblies.

AND E.3 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months secondary containment to OPERABLE status.

AND E.4 Initiate action to restore one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SGT subsystem to OPERABLE status.

AND Monticello 3.1.1-2 Amendment No. 146

SDM 3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.5 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months isolation capability in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM to be within limits. Prior to each in vessel fuel movement during fuel loading sequence AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after criticality following fuel movement within the reactor pressure vessel or control rod replacement Monticello 3.1.1-3 Amendment No. 146

Reactivity Anomalies 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 The reactivity difference between the monitored control rod inventory and the predicted control rod inventory shall be within +/- 1% Ak/k.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Core reactivity difference A.1 Restore core reactivity 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months not within limit, difference to within limit.

B. Required Action and B.1 Be in MODE 3. 12,hours associated Completion Time not met.

Monticello 3.1.2-1 Amendment No. 146

Reactivity Anomalies 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SIR 3.-12-1 Verify core reactivity difference between the Once within monitored control rod inventory and the predicted 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after control rod inventory is within + 1% Ak/k. reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AND 1000 MWD/T thereafter during operations in MODE 1 Monticello 3.1.2-2 Amendment No. 146

Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS Separate Condition entry is allowed for each control rod.

CONDITION REQUIRED ACTION COMPLETION TIME A. One withdrawn control ----------

-NOTE--------

rod stuck. Rod worth minimizer (RWM) may be bypassed as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation," if required, to allow continued operation.

A.1 Verify stuck control rod Immediately separation criteria are met.

AND A.2 Disarm the associated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months control rod drive (CRD).

AND Monticello 3.1.3-1 Amendment No. 146

Control Rod OPERABILITY 3.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 Perform SR 3.1.3.2 and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from SR 3.1.3.3 for each discovery of withdrawn OPERABLE Condition A control rod. concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM AND A.4 Perform SR 3.1.1.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Two or more withdrawn B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months control rods stuck.

C. One or more control C.1 NOTE-rods inoperable for RWM may be bypassed as reasons other than allowed by LCO 3.3.2.1, if Condition A or B. required, to allow insertion of inoperable control rod and continued operation.

Fully insert inoperable 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months control rod.

AND C.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

Monticello 3.1.3-2 Amendment No. 146

Control Rod OPERABILITY 3.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. -------- NOTE- D.1 Restore compliance with 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Not applicable when BPWS.

THERMAL POWER

> 10% RTP. OR D.2 Restore control rod to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Two or more inoperable OPERABLE status.

control rods not in compliance with banked position withdrawal sequence (BPWS) and not separated by two or more OPERABLE control rods.

E. Required Action and E.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, C, or D not met.

OR Nine or more control rods inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.1.3.2 ------------- NOTE----------------

Not required to be performed until 7 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of RWM.

Insert each fully withdrawn control rod at least one 7 days notch.

Monticello 3.1.3-3 Amendment No. 146

Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.3.3 ----------------------- NOTE -----------

Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.

Insert each partially withdrawn control rod at least 31 days one notch.

SR 3.1.3.4 Verify each control rod scram time from fully In accordance withdrawn to notch position 06 is < 7 seconds. with SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 SR 3.1.3.5 Verify each control rod does not go to the withdrawn Each time the overtravel position. control rod is withdrawn to "full out" position AND Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling Monticello 3.1.3-4 Amendment No. 146

Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4 a. No more than 8 OPERABLE control rods shall be "slow," in accordance with Table 3.1.4-1, and

b. No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months LCO not met.

SURVEILLANCE REQUIREMENTS

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

During single control rod scram time Surveillances, the control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the limits Prior to exceeding of Table 3.1.4-1 with reactor steam dome pressure 40% RTP after

> 800 psig. each reactor shutdown

> 120 days SR 3.1.4.2 Verify, for a representative sample, each tested 200 days control rod scram time is within the limits of cumulative Table 3.1.4-1 with reactor steam dome pressure operation in

> 800 psig. MODE 1 Monticello 3.1.4-1 Amendment No. 146

Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3-1.4.3 Verify each affected control rod scram time is within Prior to declaring the limits of Table 3.1.4-1 with any reactor steam control rod dome pressure. OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within Prior to exceeding the limits of Table 3.1.4-1 with reactor steam dome 40% RTP after pressure _ 800 psig. fuel movement within the affected core cell AND Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Monticello 3.1.4 -2 Amendment No. 146

Control Rod Scram Times 3.1.4 Table 3.1.4-1 (page 1 of 1)

Control Rod Scram Times

-- NOTES NOTES.-------..........---------------------------------

1. " OPERABLE control rods with scram times not within the limits of this Table are considered "slow."

2. Enter applicable Conditions and Required Actions of LCO 3.1.3, "Control Rod OPERABILITY," for control rods with scram times > 7 seconds to notch position 06. These control rods are inoperable, in accordance with SR 3.1.3.4, and are not considered "slow."

SCRAM TIMES(a)(b) (seconds)

WHEN REACTOR STEAM DOME NOTCH POSITION PRESSURE Ž 800 psig 46 0.44 36 1.08 26 1.83 06 3.35 (a) Maximum scram time from fully withdrawn position based on de-energization of scram pilot valve solenoids at time zero.

(b) Scram times as a function of reactor steam dome pressure when < 800 psig are within established limits.

Monticello 3.1.4-3 Amendment No. 146

Control Rod Scram Accumulators 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Control Rod Scram Accumulators LCO 3.1.5 Each control rod scram accumulator shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

........ ------------------------------. NOTE.------.----------OE----

Separate Condition entry is allowed for each control rod scram accumulator.

CONDITION REQUIRED ACTION COMPLETION TIME A. One control rod scram A.1 ---------- NOTE- -

accumulator inoperable Only applicable if the with reactor steam dome associated control rod pressure _ 900 psig. scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod scram time "slow."

OR A.2 Declare the associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months control rod inoperable.

B. Two or more control rod B.1 Restore charging water 20 minutes from scram accumulators header pressure to discovery of inoperable with reactor >_940 psig. Condition B steam dome pressure concurrent with

Ž 900 psig. charging water header pressure

< 940 psig AND Monticello 3.1.5-1 MAmendment No. 146

Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2.1 NOTE-------

Only applicable if the associated control rod scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.

Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rod scram time "slow."

OR B.2.2 Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rod inoperable.

C. One or more control rod C.1 Verify all control rods Immediately upon scram accumulators associated with inoperable discovery of charging inoperable with reactor accumulators are fully water header steam dome pressure inserted, pressure < 940 psig

< 900 psig.

AND C.2 Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rod inoperable.

D. Required Action B.1 or D.1 ----- NOTE -------

C.1 and associated Not applicable if all Completion Time not inoperable control rod met. scram accumulators are associated with fully inserted control rods.

Place the reactor mode Immediately switch in the shutdown position.

Monticello 3.1.5-2 Amendment No. 146

Control Rod Scram Accumulators 3.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator pressure 7 days is Ž_940 psig.

Monticello 3.1.5-3 Amendment No. 146

Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 OPERABLE control rods shall comply with the requirements of the banked position withdrawal sequence (BPWS).

APPLICABILITY: MODES 1 and 2 with THERMAL POWER < 10% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 ----------- NOTE-------

OPERABLE control rods Rod worth minimizer not in compliance with (RWM) may be bypassed BPWS. as allowed by LCO 3.3.2.1, "Control Rod Block Instrumentation."

Move associated control 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months rod(s) to correct position.

OR A.2 Declare associated control 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months rod(s) inoperable.

B. Nine or more B.1 ----------- NOTE-------

OPERABLE control rods Rod worth minimizer not in compliance with (RWM) may be bypassed BPWS. as allowed by LCO 3.3.2.1.

Suspend withdrawal of Immediately control rods.

AND B.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

Monticello 3.1.6-1 Amendment No. 146

Rod Pattern Control 3.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.6.1 Verify all OPERABLE control rods comply with 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months BPWS.

Monticello 3.1-.6-2 Amendment No. 146

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of sodium A.1 Restore concentration of 7 days pentaborate in solution sodium pentaborate in not within limits of solution to within rimits.

Figure 3.1.7-1 and Table 3.1.7-1 Equation 2, but available volume of sodium pentaborate solution is within limits of Table 3.1.7-1 Equation 1.

B. One SLC subsystem B.1 Restore SLC subsystem to 7 days inoperable for reasons OPERABLE status.

other than Condition A.

C. Two SLC subsystems C.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for reasons subsystem to OPERABLE other than Condition A. status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

Monticello 3.1.7-1 Amendment No. 146

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months solution is within the limits of Figure 3.1.7-1 or Equation 1 of Table 3.1.7-1.

SR 3.1.7.2 Verify temperature of sodium pentaborate solution is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within the limits of Figure 3.1.7-2.

SR 3.1.7.3 Verify temperature of room in the vicinity of the SLC 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months pumps is within the solution temperature limits of Figure 3.1.7-2 or verify SLC pump suction lines heat tracing is OPERABLE.

SR 3.1.7.4 Verify continuity of explosive charge. 31 days SR 3.1.7.5 Verify the concentration of sodium pentaborate in 31 days solution is within the limits of Figure 3.1.7-1 or within the limits of Equation 2 of Table 3.1.7-1. AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or sodium pentaborate is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-2 SR 3.1.7.6 Verify each SLC subsystem manual valve in the flow 31 days path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

Monticello 3.1.7-2 Amendment No. 146

SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.7 Verify each pump develops a flow rate _> 24 gpm at In accordance a discharge pressure _>1275 psig. with the Inservice Testing Program SR 3.1.7.8 Verify flow through one SLC subsystem from pump 24 months on a into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.9 Verify all heat traced piping between storage tank 24 months and pump suction is unblocked.

AND NOTE --------

Only required if SLC pump suction lines heat tracing is inoperable.

Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after room temperature in the vicinity of the SLC pumps is restored within the solution temperature limits of Figure 3.1.7-2 SR 3.1.7.10 Verify sodium pentaborate enrichment is Prior to addition to 2: 55.0 atom percent B-10. SLC tank Monticello 3.1.7-3 Amendment No. 146

SLC System 3.1.7 tI-.-+-- 1

/ Allowed Operation -

14 C

(1167.13.0~

2

.0 13 a-0 I f I F

O C

7

.1 0

E CL 12 00 c.o E

a- 404,10.7 0

,/-T/; AN 9i_ IS 11 10 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 Indicated Tank Volume (Gallons)

Figure 3.1.7-1 (page 1 of 1)

Sodium Pentaborate Solution Volume Versus Concentration Requirements Monticello 3.1.7-4 Amendment No. 146

SLC System 3.1.7 I -_______________ - - A d-90 -4__ ._..... __ _ ------

I. ~~ ~ Alo e

-Operation______ ___- ____

........ .. x -,___-

8O E-0 CU a) 0.

E U)

- ._____ ____ L __________ { _____I

-0 I0 0___t ,

Cd)

U) ca, 60 50 10 t2 14 16 8 20 Sodium Pentaborate in Solution (Weight Percent, wt%)

Figure 3.1.7-2 (page 1 of 1)

Sodium Pentaborate Solution Temperature Versus Concentration Requirements Monticello 3.1.7-5 Amendment No. 146

SLC System 3.1.7 Table 3.1.7-1 (page 1 of 1)

Equations for Required Sodium Pentaborate Tank Volurne and Concentration Equation 1 V Ž 71.18 1+ 421-)E19.8-(-100+* 128 gal V_0.0051xC + 0.998) 11O1-E)E)C )

Where:

C = measured boron solution concentration (wt%)

E = measured boron solution enrichment (atom%)

V = indicated boron solution tank volume (gal)

Equation 2 8

C > 8.28 (86)(19 Where:

C = measured boron solution concentration (wt%)

E = measured boron solution enrichment (atom%)

Q = measured pump flow rate (gpm) at 1275 psig Monticello 3.1.7-6 Amendment No. 146

SDV Vent and Drain Valves 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves LCO 3.1.8 Each SDV vent and drain valve shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTIONS

.------------NOTES --------------------------------------- -

1. Separate Condition entry is allowed for each SDV vent and drain line.

2. An isolated line may be unisolated under administrative control to allow draining and venting of the SDV.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SDV vent A.1 Isolate the associated line. 7 days or drain lines with one valve inoperable.

B. One or more SDV vent B.1 Isolate the associated line. 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or drain lines with both valves inoperable.

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 not met.

Monticello 3.1.8-1 Amendment No. 146

SDV Vent and Drain Valves 3.1.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.8.1 --------------------- NOTE ----------

Not required to be met on vent and drain valves closed during performance of SR 3.1.8.2.

Verify each SDV vent and drain valve is open. 31 days SR 3.1.8.2 Cycle each SDV vent and drain valve to the fully 92 days closed and fully open position.

SR 3.1.8.3 Verify each SDV vent and drain valve: 24 months

a. Closes in < 30 seconds after receipt of an actual or simulated scram signal; and

b. Opens when the actual or simulated scram signal is reset.

Monticello 3.1.8-2 Amendment No. 146

APLHGR 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER >_25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any APLHGR not within A.1 Restore APLHGR(s) to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits, within limits.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal to the Once within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

>25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Monticello 3.2.1-1 Amendment No. 146

MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)

LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.

APPLICABILITY: THERMAL POWER Ž_25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any MCPR not within A.1 Restore MCPR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits, limits.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 25% RTP.

Time not metl SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to the Once within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

_>25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Monticello 3.2.2-1 Amendment No. 146

MCPR 3.2.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.2.2.2 Determine the MCPR limits. Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.1 AND Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.2 AND Once within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each completion of SR 3.1.4.4 Monticello 3.2.2-2 Amendment No. 146

LHGR 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.

APPLICABILITY: THERMAL POWER >_25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Any LHGR not within A.1 Restore LHGR(s) to within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months limits, limits.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the limits Once within specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

>Ž25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Monticello 3.2.3-1 Amendment No. 146

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS

-NOTE.

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

OR A.2 Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

B. One or more Functions B.1 Place channel in one trip 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one or more system in trip.

required channels inoperable in both trip OR systems.

B.2 Place one trip system in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trip.

C. One or more Functions C.1 Restore RPS trip capability. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with RPS trip capability not maintained.

D. Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, B, Table 3.3.1.1-1 for the or C not met. channel.

Monticello 3.3.1.1-1 Amendment No. 146

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action D.1 and POWER to < 45% RTP.

referenced in Table 3.3.1.1-1.

F. As required by Required F.1 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Action D.1 and referenced in AND Table 3.3.1.1-1.

F.2 N T ..... .

Only applicable to Function 5.

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

< 600 psig.

G. As required by Required G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and referenced in Table 3.3.1.1-1.

H. As required by Required H.1 Initiate action to fully insert Immediately Action D. 1 and all insertable control rods in referenced in core cells containing one or Table 3.3.1.1-1. more fuel assemblies.

Monticello 3.3.1.1-2 Amendment No. 146

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

NOTES.

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS 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 RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.1.2 ---------------------- NOTE ----------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER Ž25% RTP.

Verify the absolute difference between the average 7 days power range monitor (APRM) channels and the calculated power is < 2% RTP while operating at

Ž25% RTP.

SR 3.3.1.1.3 ---------------------- NOTE-----------------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 7 days SR 3.3.1.1.4 Perform a functional test of each RPS automatic 7 days scram contactor.

SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST. 31 days SR 3.3.1.1.6 Calibrate the local power range monitors. 2000 effective full power hours SR 3.3.1.1.7 Perform CHANNEL FUNCTIONAL TEST. 92 days Monticello 3.3.1.1-3 Amendment No. 146

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.8 Calibrate the trip units. 92 days SR 3.3.1.19 ---------- NOTE ------------------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days SR 3.3.1.1.10 Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.1.1-11 --------------------- NOTES ----------------

1. Neutron detectors are excluded.

2. For Function 1, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL CALIBRATION. 24 months SR 3.3.1.1.12 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SR 3.3.1.1.13 Verify Turbine Stop Valve - Closure and Turbine 24 months Control Valve Fast Closure, Acceleration Relay Oil Pressure - Low Functions are not bypassed when THERMAL POWER is > 45% RTP.

SR 3.3.1.1.14 -------------------- NOTE - ------------------

For Function 5 "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.

Verify the RPS RESPONSE TIME is within limits. 24 months on a STAGGERED TEST BASIS Monticello 3.3.1.1-4 Amendment No. 146

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

1. Intermediate Range Monitors

a. Neutron Flux - High 2 3 G SR 3.3.1.1.1 *5122/125 High SR 3.3.1.1.3 divisions of full SR 3.3.1.1.4 scale SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14 5(a) 3 H SR 3.3.1.1.1 <_122/125 SR 3.3.1.1.3 divisions of full SR 3.3.1.1.4 scale SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14

b. Inop 2 3 G SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.12 5 0a) 3 H SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.12

2. Average Power Range Monitors

a. Flow Referenced 1 2 F SR 3.3.1.1.1 :<0.66 W Neutron Flux - High SR 3.3.1.1.2 +67.6% RTP High SR 3.3.1.1.4 and SR 3.3.1.1.6 5 122% RTP(b)

SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.14

b. Inop 1 2 F SR 3.3.1.1.4 NA SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.12 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) 0.66 (W - 5.4) + 67.6% RTP when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating."

Monticello 3.3.1.1-5 Amendment No. 146

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

3. Reactor Vessel Steam 1,2 2 G SR 3.3.1.1.4 _ 1075 psig Dome Pressure - High SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.14

4. Reactor Vessel Water 1,2 2 G SR 3.3.1.1.1 _ 7 inches Level - Low SR 3.3.1.1.4 SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14

5. Main Steam Isolation 1, 2(c) 8 F SR 3.3.1.1.4 _*10% closed Valve - Closure SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.14

6. Drywell Pressure - High 1,2 2 G SR 3.3.1.1.4 < 2.0 psig SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12

7. Scram Discharge Volume Water Level -

High

a. Resistance 1,2 2 G SR 3.3.1.1.4 < 56.0 gallons Temperature SR 3.3.1.1.7 Detector SR 3.3.1.1.9 SR 3.3.1.1.12 5 (a) 2 H SR 3.3.1.1.4 <_56.0 gallons SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(c) With reactor pressure _>600 psig.

Monticello 3.3.1.1-6 Amendment No. 146

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE

7. Scram Discharge Volume Water Level -

High

b. Float Switch 1,2 2 G SR 3.3.1.1.4 56.0 gallons SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12 5(a) 2 H SR 3.3.1.1.4 < 56.0 gallons SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.12

8. Turbine Stop Valve - > 45% RTP 4 E SSR 3.3.1.1.4 < 10% closed Closure SR 3.3.1.1.7 SR 3.3.1.1.11 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.14

9. Turbine Control Valve > 45% RTP 2 E SR 3.3.1.1.4 > 167.8 psig Fast Closure, SR 3.3.1.1.7 Acceleration Relay Oil SR 3.3.1.1.9 Pressure - Low SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.14

10. Reactor Mode Switch - 1,2 1 G SR 3.3.1.1.10 NA Shutdown Position SR 3.3.1.1.12 5(a) 1 H SR 3.3.1.1.10 NA SR 3.3.1.1.12

11. Manual Scram 1,2 1 G SR 3.3.1:1.5 NA SR 3.3.1.1.12 5(a) .1 H SR 3.3.1.1.5 NA SR 3.3.1.1.12 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

Monticello 3.3.1.1-7 Amendment No. 146

SRM Instrumentation 3.3.1.2 3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor (SRM) Instrumentation LCO 3.3.1.2 The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.2-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required SRMs to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months SRMs inoperable in OPERABLE status.

MODE 2 with intermediate range monitors (IRMs) on Range 2 or below.

B. Three required SRMs B.1 Suspend control rod Immediately inoperable in MODE 2 withdrawal.

with IRMs on Range 2 or below.

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 not met.

D. One or more required D.1 Fully insert all insertable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SRMs inoperable in control rods.

MODE 3 or 4.

AND D.2 Place reactor mode switch 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in the shutdown position.

Monticello 3.3.1.2-1 Amendment No. 146

SRM Instrumentation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more required E.1 Suspend CORE Immediately SRMs inoperable in ALTERATIONS except for MODE 5. control rod insertion.

AND E.2 Initiate action to fully insert Immediately all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Monticello 3.3.1.2-2 Amendment No. 146

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.2 ---- NOTES-- -----------

1. Only required to be met during CORE ALTERATIONS.

2. One SRM may be used to satisfy more than one of the following.

Verify an OPERABLE SRM detector is located in: 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

a. The fueled region;

b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and

c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.

SR 3.3.1.2.3 Perform CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.1.2.4 - -------------.....------ NOTE ----------------

Not required to be met with less than or equal to two fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

Verify count rate is > 3.0 cps with a signal to noise 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during ratio Ž3:1. CORE ALTERATIONS AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Monticello 3.3.1.2-3 Amendment No. 146

SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.5 ------- NOTE------ -

The determination of signal to noise ratio is not required to be met with less than or equal to two fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.

Perform CHANNEL FUNCTIONAL TEST and 7 days determination of signal to noise ratio.

SR 3.3.1.2.6 ---------------------- NOTE------ -

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL FUNCTIONAL TEST and 31 days determination of signal to noise ratio.

SR 3.3.1.2.7 --------------------- NOTES----

1. Neutron detectors are excluded.

2. Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after IRMs on Range 2 or below.

Perform CHANNEL CALIBRATION. 24 months Monticello 3.3.1.2-4 Amendment No. 146

SRM Instrumentation 3.3.1.2 Table 3.3.1.2-1 (page 1 of 1)

Source Range Monitor Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS

1. Source Range Monitor 2(a) 3 SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1-2.6 SR 3.3.1.2.7 3, 4 2 SR 3.3.1-2.3 SR 3.3.124 SR 3.3.1-2.6 SR 3.3.1.2.7 2 (b), (c) SR 3.3.1-2.1, SR 3.3.1-2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (a) With IRMs on Range 2 or below.

(b) Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector.

(c) Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.

Monticello 3.3.1.2-5 Amendment No. 146

Control Rod Block Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Control Rod Block Instrumentation LCO 3.3.2.1 The control rod block instrumentation for each Function in Table 3.3.2. 1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One rod block monitor A.1 Restore RBM channel to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (RBM) channel OPERABLE status.

inoperable.

B. Required Action and B.1 Place one RBM channel in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion trip.

Time of Condition A not met.

OR Two RBM channels inoperable.

C. Rod worth minimizer C.1 Suspend control rod Immediately (RWM) inoperable movement except by during reactor startup. scram.

OR C.2.1.1 Verify 12 rods withdrawn. Immediately OR Monticello 3.3.2.1-1 Amendment No. 146

Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2.1.2 Verify by administrative Immediately methods that startup with RWM inoperable has not been performed in the last 12 months.

AND C.2.2 Verify movement of control During control rod rods is in compliance with movement banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.

D. RWM inoperable during D.1 Verify movement of control During control rod reactor shutdown. rods is in compliance with movement BPWS by a second licensed operator or other qualified member of the technical staff.

E. One or more Reactor E.1 Suspend control rod Immediately Mode Switch - Shutdown withdrawal.

Position channels inoperable. AND E.2 Initiate action to fully insert Immediately all insertable control rods in core cells containing one or more fuel assemblies.

Monticello 3.3.2.1-2 Amendment No. 146

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.

2. When an RBM 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 control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.2 ---------------------- NOTE- -----------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn at < 10% RTP in MODE 2.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.3 ---------------------- NOTE------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after THERMAL POWER is < 10% RTP in MODE 1.

Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.2.1.4 - --------------- NOTE -----------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days Monticello 3.3.2.1-3 Amendment No. 146

Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued) I SURVEILLANCE FREQUENCY I

SR 3.3.2.1.5 ----------- NOTE ----------------

Neutron detectors are excluded.

Verify the RBM: 92 days

a. Low Power Range - Upscale Function is not bypassed when THERMAL POWER is 2!30%

and < 65% RTP;

b. Intermediate Power Range - Upscale Function is not bypassed when THERMAL POWER is

>_65% and < 85% RTP; and

c. High Power Range - Upscale Function is not bypassed when THERMAL POWER is

>_85% RTP.

SR 3.3.2.1.6 Verify the RWM is not bypassed when THERMAL 24 months POWER is _<10% RTP.

SR 3.3.2.1.7 NOTE ----------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after reactor mode switch is in the shutdown position.

Perform CHANNEL FUNCTIONAL TEST. 24 months SR 3.3.2.1.8 Verify control rod sequences input to the RWM are Prior to declaring in conformance with BPWS. RWM OPERABLE following loading of sequence into RWM Monticello 3.3.2.1-4 Amendment No. 146

Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1)

Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1. Rod Block Monitor

a. Low Power Range - Upscale (a) 2 SR 3.3.2.1.1 As specified in SR 3.3.2.1.4 COLR SR 3.3.2.1.5

b. Intermediate Power Range- (b) 2 SR 3.3.2.1.1 As specified in Upscale SR 3.3.2.1.4 COLR SR 3.3.2.1.5

c. High Power Range - Upscale (c). (d) 2 SR 3.3.2.1.1- As specified in SR 3.3.2.1.4 COLR SR 3.3.2.1.5

d. Inop (d), (e) 2 SR 3.3.2.1.1 NA

e. Downscale (d), (e) 2 SR 3.3.2.1.1 >_93.6/125 SR 3.3.2.1.4 divisions of full scale

2. Rod Worth Minimizer 1(f), 2r 1 SR 3.3.2.1.2 NA SR 3.3.2.1.3 SR 3.3.2.1.6 SR 3.3.2.1.8

3. Reactor Mode Switch - Shutdown (g) 2 SR 3.3.2.1.7 NA Position (a) THERMAL POWER > 30% and < 65% RTP and MCPR is below the limit specified in COLR.

(b) THERMAL POWER Ž65% and < 85% RTP and MCPR is below the limit specified in COLR.

(c) THERMAL POWER > 85% and < 90% RTP and MCPR is below the limit specified in COLR.

(d) THERMAL POWER > 90% RTP and MCPR is below the limit specified in COLR.

(e) THERMAL POWER > 30% and < 90% RTP and MCPR is below the limit specified in COLR.

(f) With THERMAL POWER _ 10% RTP.

(9) Reactor mode switch in the shutdown position.

Monticello 3.3-2.1-5 Amendment No. 146

Feedwater Pump and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 3.3 INSTRUMENTATION 3.3.2.2 Feedwater Pump and Main Turbine High Water Level Trip Instrumentation LCO 3.3.2.2 Four channels of Feedwater Pump and Main Turbine High Water Level Trip Instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER a 25% RTP.

ACTIONS

NOTE--

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more feedwater A.1 Place channel in trip. 7 days pump and main turbine high water level trip channels inoperable.

B. Feedwater pump and B.1 Restore feedwater pump 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months main turbine high water and main turbine high water level trip capability not level trip capability.

maintained.

C. Required Action and C.1 ---------NOTE-------

associated Completion Only applicable if Time not met. inoperable channel is the result of inoperable feedwater pump breaker or main turbine stop valve.

Remove affected feedwater 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months pump(s) and main turbine valve(s) from service.

OR Monticello 3.3.2.2-1 Amendment No. 146

Feedwater Pump and Main Turbine High Water Level Trip Instrumentation 3.3.2.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months POWER to < 25% RTP.

SURVEILLANCE REQUIREMENTS

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

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 feedwater pump and main turbine high water level trip capability is maintained.

SURVEILLANCE FREQUENCY SR 3.3.2.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.2.2.2 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.2.2.3 Calibrate the trip units. 184 days SR 3.3.2.2.4 Perform CHANNEL CALIBRATION. The Allowable 24 months Value shall be

49 inches.

SR 3.3.2.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including valve and breaker actuation.

Monticello 3.3.2.2-2 Amendment No. 146

PAM Instrumentation 3.3.3.1 3.3 INSTRUMENTATION 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3.1 The PAM instrumentation for each Function in Table 3.3.3.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS M---r Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Restore required channel to 30 days with one required OPERABLE status.

channel inoperable.

B. Required Action and B.1 Initiate action in accordance Immediately associated Completion with Specification 5.6.4.

Time of Condition A not met.

C. One or more Functions C.1 Restore one required 7 days with two required channel to OPERABLE channels .inoperable. status.

D. Required Action and D.1 Enter the Condition Immediately' associated Completion referenced in Time of Condition C not Table 3.3.3.1-1 for the met. channel.

Monticello 3.3.3.1-1 Amendment No. 146

PAM Instrumentation 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action D.1 and referenced in Table 3.3.3.1-1.

F. As required by Required F.1 Initiate action in accordance Immediately Action D.1 and with Specification 5.6.4.

referenced in Table 3.3.3.1-1.

SURVEILLANCE REQUIREMENTS

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

1. These SRs apply to each Function in Table 3.3.3.1-1.

2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the other required channel in the associated Function is OPERABLE.

SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Perform CHANNEL CHECK. 31 days SR 3.3.3.1.2 Perform CHANNEL CALIBRATION. 24 months Monticello 3.3.3.1-2 Amendment No. 146

PAM Instrumentation 3.3.3.1 Table 3.3.3.1-1 (page 1 of 1)

Post Accident Monitoring Instrumentation CONDITIONS REFERENCED REQUIRED FROM REQUIRED FUNCTION CHANNELS ACTION D.1

1. Reactor Vessel Pressure 2 E

2. Reactor Vessel Water Level 2 E

3. Suppression Pool Water Level 2 E

4. Drywell Pressure 2 E

5. Primary Containment Area Radiation 2 F

6. Penetration Flow Path PCIV Position 2 per penetration flow E path(a) (b)

7. Suppression Pool Water Temperature 2 F (a) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and deactivated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(b) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

Monticello 3.3.3.1-3 Amendment No. 146

Alternate Shutdown System 3.3.3.2 3.3 INSTRUMENTATION 3.3.3.2 Alternate Shutdown System LCO 3.3.3.2 The Alternate Shutdown System Functions shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

___ --- NOTE--.

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required Function 30 days Functions inoperable, to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.2.1 Perform CHANNEL CHECK for each required 31 days instrumentation channel that is normally energized.

SR 3.3.3.2.2 Verify each required control circuit and transfer 24 months switch is capable of performing the intended function.

SR 3.3.3.2.3 Perform CHANNEL CALIBRATION for each 24 months required instrumentation channel.

Monticello 3.3.3.2-1 Amendment No. 146

ATWS-RPT Instrumentation 3.3.4.1.

3.3 INSTRUMENTATION 3.3.4.1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT)

Instrumentation LCO 3.3.4.1 Two channels per trip system for each ATWS-RPT instrumentation Function listed below shall be OPERABLE:

a. Reactor Vessel Water Level - Low Low; and

b. Reactor Vessel Steam Dome Pressure - High.

APPLICABILITY: MODE 1.

ACTIONS NO )TE-...

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Restore channel to 14 days inoperable. OPERABLE status.

OR A.2 NOTE Not applicable if inoperable channel is the result of an inoperable breaker.

Place channel in trip. 14 days B. One Function with B.1 Restore ATWS-RPT trip 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ATWS-RPT trip capability.

capability not maintained.

Monticello 3.3.4.1-1 Amendment No. 146

ATWS-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Both Functions with C.1 Restore ATWS-RPT trip 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ATWS-RPT trip capability for one Function.

capability not maintained.

D. Required Action and D.1 --------------- NOTE ------------.

associated Completion Only applicable if Time not met. inoperable channel is the result of an inoperable breaker.

Remove the affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months recirculation pump from service.

OR D.2 Be in MODE 2. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months SURVEILLANCE REQUIREMENTS

....-....---------------- ----------------------------- NOTE------------ -

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 ATWS-RPT trip capability.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 NOTE----------- .------------

Not required for the time delay portion of the Reactor Vessel Water Level - Low Low Function.

Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.4.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days Monticello 3.3.4.1-2 Amendment No. 146

ATWS-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.1.3 Calibrate the trip units. 92 days SR 3.3.4.1.4 Perform CHANNEL.CALIBRATION of Reactor 184 days Vessel Water Level - Low Low time delay relays.

The Allowable Value shall be > 6 seconds and

_ 8.6 seconds.

SR 3.3.4.1.5 Perform CHANNEL CALIBRATION. The Allowable 24 months Values shall be:

a. Reactor Vessel Water Level - Low Low

> -48 inches; and

b. Reactor Vessel Steam Dome Pressure - High

1155 psig.

SR 3.3.4.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months including breaker actuation.

Monticello 3.3.4.1-3 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 Separate Condition entry. is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable, referenced in Table 3.3.5.1-1 for the channel.

B. As required by Required B.1 ---------- NOTES-Action A.1 and 1. Only applicable in referenced in MODES 1, 2, and 3.

Table 3.3.5.1-1.

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

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 C. As required by Required C.1-------------- NOTES-----

Action A.1 and 1. Only applicable in referenced in MODES 1, 2, and 3.

Table 3.3.5.1-1.

2. Only applicable for Functions 1.c, 1.d, 1.e, 1.f, 2.c, 2.d, 2.e, 2.i, 2.j, 2.1, and 2.m.

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 C.2 Restore channel to 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

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 OR D.2.2 Align the HPCI pump 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months suction to the suppression pool.

E. As required by Required E.1 ----- NOTES.......

Action A.1 and 1. Only applicable in referenced in MODES 1, 2, and 3.

Table 3.3.5.1-1.

2. Only applicable for Function 2.g.

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 subsystems in both inoperable, divisions AND E.2 Restore channel to 7 days OPERABLE status.

Monticello 3.3.5.1-3 Amendment No. 146

ECCS Instrumentation 3.3.5.1 ACTIONS (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 (RCIC) inoperable AND 8 days G. As required by Required G.1 Declare ADS valves 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery Action A.1 and inoperable, of loss of ADS referenced in initiation capability in Table 3.3.5.1-1. both trip systems AND G.2 Restore channel to 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from OPERABLE status. 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 Calibrate the trip unit. 92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION. 92 days SR 3.3.5.1.5 Perform CHANNEL FUNCTIONAL TEST. 12 months SR 3.3.5.1.6 Perform CHANNEL CALIBRATION. 12 months SR 3.3.5.1.7 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.1.8 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months Monticello 3.3.5.!-5 Amendment No. 146

ECCS InstrImentation 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 SURVEILLANrE ALLOWABLE FUNCTION CONDITIONS FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Core Spray System

a. Reactor Vessel 1,2,3, 4 (b) B SR 3.3.5.1.1 >-48. inches Water Level - Low 4 (a), 5(8) 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

b. Drywell Pressure - (b) B SR 3.3.5.1.2.

1,2,3 4 <_2 psig High SR 3.3.5.1.4 SR 3.3.5.1.8

c. Reactor Steam 1,2,3 2 C SR 3.3.5.1.2 _ 39T psig and Dome Pressure - SR 3.3.5.1.-48(c)(d *_440 psig Low (Injection SR 3.3.5.1.-

Permissive) 4(a), (a) 5 2 B SR 3.3.5.1-2 > 397 psIg and SR 3.3.5.1.84'cý) <_440 psig SR 3.3.5.1.8

d. Reactor Steam 1,2,3 2 C SR 3 .3.5- 1 -2 2:397 psig Dome Pressure SR 3.3.5.1.4tc" Permissive - Low SR 3.3.5.1.8 (Pump Permissive) 4(a) (a) 5 2 B SR 3.3.5.1-2 2! 397 psig SR 3.3.5.1.48*'

SR 3.3.5.1.7

e. Reactor Steam 1,2,3 2 C SR 3.3.5.1.7 > 18a mrinutes Dome Pressure SR 3.3.5.1.8 and Permissive - Bypass *_ 22 minutes Timer (Pump 4(a), 5(a Permissive) 2 B SR 3.3.5.1.7 > 18 minutes SR 3.3.5.1-8 and

s 22 minutes (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown-"

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

(c) 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.

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

Monticello 3.3.5.1-6 Amendme-nt N-o. 146

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 6)

Emergency Core Cooling System Instrumentation APPUCABLE 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 4 (a), 5 (a) SR 3.3.5.1.8 Start - Time Delay 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 Water Level - Low 4(a), 5 (a) 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

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. Reactor Steam 1,2,3 2 C SR 3.3.5.1.2 > 397 psig and Dome Pressure - SR 3.3.5.1. 4 (C)(d) *_440 psig Low (Injection SR 3.3.5.1.8 Permissive) 4(a), 5 (a) 2 B SR 3.3.5.1.2 > 397 psig and SR 3.3.5.1. 4 (c)(d) *<440 psig SR 3.3.5.1.8 d., Reactor Steam 1,2,3 2 C SR 3.3.5.1.2 _ 397 psig Dome Pressure SR 3.3.5.1.4(c)(d)

Permissive - Low SR 3.3.5.1.8 (Pump Permissive) 4(a), 5(a) 2 B SR 3.3.5.1.2 >_397 psig SR 3.3.5.1.4(c)(d)

SR 3.3.5.1.8 (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.

(c) Ifthe 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.

(d) 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

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 and Permissive - Bypass *22 minutes Timer (Pump. 4(a), 5(a)

Permissive) 2 B SR 3.3.5.1.7 > 18 minutes SR 3.3.5.1.8 and

< 22 minutes

f. Low Pressure 1,2,3, 4 per pump B SR 3.3.5.1.7 Coolant Injection 4 (a) 5 (a) SR 3.3.5.1.8 Pump Start - Time Delay Relay Pumps A, B _*5.33 seconds Pumps C, D _<10.59 seconds

g. Low Pressure 1,2,3, 4 I(a) ' 1 per pump E SR 3.3.5.1.2 >360 gpm and 5 (a)

Coolant Injection SR 3.3.5.1.7 < 745 gpm Pump Discharge SR 3.3.5.1.8 Flow - Low (Bypass)

h. Reactor Steam 1,2,3, 4 B SR 3.3.5.1.2 _ 873.6 psig Dome Pressure - SR 3.3.5.1.7 and Low (Break SR 3.3.5.1.8

923.4 psig Detection)

I. Recirculation Pump 1,2.3 4 per pump C SR 3.3.5.1.2 Z: 63.5 inches Differential Pressure SR 3.3.5.1.7 wc

- High (Break SR 3.3.5.1.8 Detection)

j. Recirculation Riser - 1,2,3 4 C SR 3.3.5.1.2 <_24.0 inches Differential Pressure SR 3.3.5.1.6 wc

- High (Break SR 3.3.5.1.8 Detection)

k. Reactor Steam 1,2,3 2 B SR 3.3.5.1.2 :5 2.79 seconds Dome Pressure - SR 3.3.5.1.4 Time Delay Relay SR 3.3.5.1.8 (Break Detection)

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

Monticello 3.3.5.1-8 A^--n^m t-^m-".446 Correction letter of 10/12/06

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 I. Recirculation Pump 1,2,3 2 C SR 3.3.5.1.2 < 0.716 seconds Differential Pressure SR 3.3.5.1.4

- Time Delay Relay SR 3.3.5.1.8 (Break Detection)

m. Recirculation Riser 1,2,3 2 C SR 3.3.5.1.2 < 0.697 seconds Differential Pressure SR 3.3.5.1.4

- Time Delay Relay SR 3.3.5.1.8 (Break Detection)

3. High Pressure Coolant Injection (HPCI) System

a. Reactor Vessel 1, 2(e), 3 (e) 4 SR 3.3.5.1.1 Ž -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

b. Drywell Pressure - 1, 2(a), 3 (e) 4 B SR 3.3.5.1.2 < 2 psig High SR 3.3.5.1.4 SR 3.3.5.1.8

c. Reactor Vessel 1, 2(e), 3 (e) 2 C SR 3.3.5.1.1

48 inches Water Level - High SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8

d. Condensate Storage 1, 2(e), 3(e) 2 D SR 3.3.5.1.7 - 29.3 inches Tank Level - Low SR 3.3.5.1.8

e. Suppression Pool 1, 2 (e), 3 (e) 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

f. High Pressure 1, 2(e), 3 (e) 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)

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

Monticello 3.3.5.1-9 Amendment No. 146

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

a. Reactor Vessel 1, 2 (e), 3(e) 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

b. Automatic 1, 2(e), 3(e) 1 G SR 3.3.5.1.7 _<120 seconds Depressurization SR 3.3.5.1.8 System Initiation Timer

c. Core Spray Pump 1, 2 (e), 3 (e) 2 G SR 3.3.5.1.2 > 75 psig and Discharge Pressure SR 3.3.5.1.4(c)(d) _<125 psig

- High SR 3.3.5.1.8

d. Low Pressure 1, 2(e), 3 (e) 4 G SR 3.3.5.1.2 > 75 psig and Coolant Injection SR 3.3.5.1.4(c)(d) < 125 psig Pump Discharge SR 3.3.5.1.8 Pressure - High

5. ADS Trip System B

a. Reactor Vessel 1, 2(e), 3(e) 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

b. Automatic 1, 2(e), 3 (e) 1 G SR 3.3.5.1.7 < 120 seconds Depressurzation SR 3.3.5.1.8 System Initiation Timer (c) 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 retuming the channel to service.

(d) 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.

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

Monticello 3.3.5.1-10 Amendment No. 146

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

c. Core Spray Pump 1, 2(e), 3(e) 2 G SR 3.3.5.1.2 _>75 psig and Discharge Pressure SR 3 .3.5.1. 4 (c)(d) _ 125 psig

- High SR 3.3.5.1.8 d.P Leswu e* 3( )- . .

d. Low Pressure 1, 2ý1, 3(e) 4 G SR 3.3.5.1.2 Ž 75 psig and Coolant Injection SR 3 .3.5.1.4((d) < 125 psig Pump Discharge SR 3.3.5.1.8 Pressure - High (c) 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.

(d) 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.

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

Monticello 3.3.5.1-11 Amendment No. 146

RCIC System Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.2 The RCIC System instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

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

ACTIONS

-.-.--------------------..........------------------------- NOTE-----

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Enter the Condition Immediately inoperable, referenced in Table 3.3.5.2-1 for the channel.

B. As required by Required B.1 Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery Action A.1 and inoperable. of loss of RCIC referenced in initiation capability Table 3.3.5.2-1.

AND B.2 Place channel in trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. As required by Required C.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 3.3.5.2-1.

Monticello 3.3.5.2-1 Amendment No. 146

RCIC System Instrumentation 3.3.5.2 ACTIONS (continued)

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

Action A.1 and Only applicable if RCIC referenced in pump suction is not aligned Table 3.3.5.2-1. to the suppression pool.

Declare RCIC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery inoperable, of loss of RCIC 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 OR D.2.2 Align RCIC pump suction to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the suppression pool.

E. Required Action and E.1 Declare RCIC System Immediately associated Completion inoperable.

Time of Condition B, C, or D not met.

SURVEILLANCE REQUIREMENTS

................................................... I*ll II

-4. -I----- - ----------- - -- - - -

1. Refer to Table 3.3.5.2-1 to determine which SRs apply for each RCIC 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 Function 2; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.5.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Monticello 3.3.5.2-9 Amendment No. 146

RCIC System Instrumentation 3.3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.5.2.3 Calibrate the trip units. 92 days SR 3.3.5.2.4 Perform CHANNEL CALIBRATION. 24 months SR 3.3.5.2.5 Perform LOGIC SYSTEM FUNCTIONAL TEST. -24 months Monticello 3.3.5.2-3 Amendment No. 146

RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED CHANNELS FROM PER REQUIRED SURVEILLANCE ALLOWABLE FUNCTION FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Reactor Vessel Water Level - Low 4 8 SR 3.3.5.2.1 > -48 inches Low SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 SR 3.3.5.2.5

2. Reactor Vessel Water Level - High 2 C SR 3.3.5.2.1 < 48 inches SR 3.3.5.2.2 SR 3.3.5.2.3 SR 3.3.5.2.4 SIR 3.3.5.2.5

3. Condensate Storage Tank Level - 2 D SR 3.3.5.2.4 _ 29.3 inches Low SR 3.3.5.2.5 Monticello 3.3.5.2-4 Amendment No. 146

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 REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for channels inoperable. Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND 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 B. One or more Functions B.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with primary containment isolation 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

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 Table 3.3.6.1-1.

F. As required by Required F.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and penetration flow path(s).

referenced in Table 3.3.6.1-1.

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 Action C.1 and penetration flow path(s).

referenced in Table 3.3.6.1-1.

H. As required by Required H.1 Declare associated standby 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action C.1 and liquid control (SLC) referenced in subsystem inoperable.

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

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME As required by Required 1.1 Initiate action to restore Immediately Action C.1 and channel to OPERABLE referenced in status.

Table 3.3.6.-1.

OR 1.2 Initiate action to isolate the Immediately Residual Heat Removal (RHR) Shutdown Cooling System.

SURVEILLANCE REQUIREMENTS

---- -- NOTES-- -............----------------------------------

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

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

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3 Calibrate the trip unit. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 92 days Monticello 3.3.6.1-3 Amendment No. 146

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 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.A 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 SR 3.3.6.1.6

c. Main Steam Line 1,2,3 2 per D SR 3.3.6.1.1 < 142% rated Flow - High MSL SR 3.3.6.1.2 steam flow SR 3.3.6.1.4 SR 3.3.6.1.6

d. Main Steam Line 1,2,3 2 per trip D SR 3.3.6.1.5 _<

209°F Tunnel string SR 3.3.6.1.6 Temperature- High

2. Primary Containment Isolation

a. Reactor Vessel 1,2,3 2 F SR 3.3.6.1.1 _7 inches Water Level - Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

b. 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

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

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 Cooling (RCIC) System Isolation

a. RCIC Steam Line 1,2,3 2 F SR 3.3.6.1.2 _<45,903 lb/hour Flow - High SR 3.3.6.1.4 with SR 3.3.6.1.6 < 7.16 second time delay

b. RCIC Steam Supply 1,2,3 4 F SR 3.3.6.1.2 > 54 psig Line Pressure - Low SR 3.3.6.1.4 SR 3.3.6.1.6

c. RCIC Steam Line 1,2,3 16 F SR 3.3.6.1.2 < 196oF Area Temperature - SR 3.3.6.1.4 High SR 3.3.6.1.6

5. Reactor Water Cleanup (RWCU) System Isolation

a. RWCU Flow - High 1,2,3 2 F SR 3.3.6.1.1 5 500 gpm with SR 3.3.6.1.2 < 11.4 second SR 3.3.6.1.3 time delay SR 3.3.6.1.5 SR 3.3.6.1.6

b. RWCU Room 1,2,3 2 F SR 3.3.6.1.1 _<188 0F 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 :5 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 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. Reactor Steam 1,2,3 2 F SR 3.3.6.1.2 < 81.8 psig Dome Pressure - SR 3.3.6.1.4 High SR 3.3.6.1.6

b. Reactor Vessel 3,4,5 2(a) SR 3.3.6.1.1 >_7 inches Water Level - Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

7. Traversing Incore Probe System Isolation

a. Reactor Vessel 1,2,3 2 G SR 3.3.6.1.1 et 7 inches Water Level - Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6

b. Drywell Pressure - 1,2,3 2 G SR 3.3.6.1.2 < 2.0 psig High SR 3.3.6.1.4 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

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

N( r------------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in trip. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for inoperable. 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 B. One or more Functions B.1 Restore secondary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with. secondary. containment isolation containment isolation capability.

capability not maintained.

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

N I rI'*--------------------------------- ---------------

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

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

SURVEILLANCE FREQUENCY SIR 3.3.6.2.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.2.3 Calibrate the trip unit. 92 days SR 3.3.6.2.4 Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.2.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months 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 Radiation - High (a), (b) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6

4. Refueling Floor Radiation - High 1, 2, 3, 2 SR 3.3.6.2.1 < 100 mRlhr (a), (b) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 (a) During operations with a potential for draining the reactor vessel.

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

Monticello 3.3.6.2-3 Amendment No. 146

LLS Instrumentation 3.3.6.3 3.3 INSTRUMENTATION 3.3.6.3 Low-Low Set (LLS) Instrumentation LCO 3.3.6.3 The LLS valve instrumentation for each Function in Table 3.3.6.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS S ----------------------- NO r- -- ý - - -- - ----------------------------- ---------

Separate Condition entry is allowed for each LLS valve.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more LLS valves A.1 Declare associated LLS 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery with one or more valve inoperable, of loss of LLS valve channels inoperable, initiation capability in both trip systems AND A.2 Restore channel(s) to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

B. Required Action and B.1 Declare the associated LLS Immediately associated Completion valve(s) inoperable.

Time not met.

Monticello 3. 3y.6. 3- 1 Amendment No. 146

LLS Instrumentation 3.3.6.3 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.6.3-1 to determine which SRs apply for each 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 LLS initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.3.1 Perform CHANNEL CHECK. 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 's SR 3.3.6.3.2 ----------- NOTE ------------------------------

For Function 1, only required to be performed prior to entering MODE 2 or 3 from MODE 4.

Perform CHANNEL FUNCTIONAL TEST.- 92 days S R 3.3.6.3.3 Calibrate the trip unit. 92 days SR 3.3.6.3.4 Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.3.5 Perform CHANNEL CALIBRATION. 24 months S R 3.3.6.3.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months Monticello 3.3.6.3-2 Amendment No. 146

LLS Instrumentation 3.3.6.3 w

Table 3.3.6.3-1 (page 1 of 1)

Low-Low Set Instrumentation REQUIRED CHANNELS PER SURVEILLANCE ALLOWABLE FUNCTION FUNCTION REQUIREMENTS VALUE

1. Reactor Scram Detection 4 per LLS valve SR 3.3.6.3.2 NA SR 3.3.6.3.6

2. Low-Low Set Pressure Setpoints 4 per ILLS valve SR 3.3.6.3.1 Low:

SR 3.3.6.3.2 Open < 1066 psig SR 3.3.6.3.3 Close < 986 psig SR 3.3.6.3.5 SR 3.3.6.3.6 Medium:

Open _ 1076 psig Close < 996 psig High:

Open < 1086 psig Close < 1006 psig

3. Tailpipe Pressure Switch 4 per LLS valve SR 3.3.6.3.1 > 27 psid and SR 3.3.6.3.2 < 33 psid SR 3.3.6.3.5 SR 3.3.6.3.6

4. Inhibit Timers 4 per LLS valve SR 3.3.6.3.2 > 8 seconds and SR 3.3.6.3.4 <_12 seconds SR 3.3.6.3.6 Monticello 3.3.6.3-3 Amendment No. 146

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 One channel per trip system of the Control Room Air Inlet Radiation -

High Function 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

NOTE---.

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place the associated CREF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, subsystem in the pressurization mode of operation.

OR A.2 Declare associated CREF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem inoperable.

Monticello 3.3.7.1-1 Amendment No. 146

CREF System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS

-NOTE-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 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-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. 31 days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. The Allowable 24 months Value shall be < 2 mR/hour.

Monticello 3.3.7.1-2 Amendment No. 146

LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, When the associated emergency diesel generator (EDG) is required to be OPERABLE by LCO 3.8.2, "AC Sources - Shutdown."

ACTIONS

--.-.-.---------- -NOT r::.-------------------------------------------------------

Separate Condition entry is allowed for each chan CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable.

B. Required Action and B.1 Declare associated EDG Immediately associated Completion inoperable.

Time not met Monticello 3.3.8.1-1 Amendment No. 146

LOP Instrumentation 3.3.8.1 SURVEILLANCE REQUIREMENTS

. - -NOTES ----------------------------------------------------------

1. Refer to Table 3.3.8.1-1 to determine which SRs apply for each LOP Instrumentation 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 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided the associated Function maintains EDG initiation capability.

SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL FUNCTIONAL TEST. 31 da-ys SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. 92 days SR 3.3.8.1.3 Perform CHANNEL CALIBRATION. 24 months SR 3.3.8.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months Monticello 3.3.8.1-2 Amendment No. 146

LOP Instrumentation 3.3.8.1 Table 3.3.8.1-1 (page 1 of 1)

Loss of Power Instrumentation REQUIRED CHANNELS SURVEILLANCE ALLOWABLE FUNCTION PER BUS REQUIREMENTS VALUE

1. 4.16 kV Essential Bus Loss of Voltage 4 SR 3.3.8.1.1 >2345 V and* 2905 V SR 3.3.8.1.3 SR 3.3.8.1.4

2. 4.16 kV Essential Bus Degraded Voltage

a. Bus Undervoltage 3 SR 3.3.8.1.1 _>3913 V and* 3927 V SR 3.3.8.1.2 SR 3.3.8.1.4

b. Time Delay 3 SR 3.3.8.1.1 Žt 8.8 seconds and SR 3.3.8.1.2 *59.2 seconds SR 3.3.8.1.4 Monticello 3.3.8.1-3 Amendment No. 446,147

RPS Electric Power Monitoring 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply.

APPLICABILITY: MODES 1, 2, and 3, MODES 4 and 5 with residual heat removal (RHR) shutdown cooling supply isolation valves open, MODE 5 with any control rod withdrawn from a core cell containing one or

-. more fuel assemblies, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or both inservice A.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power supplies with one inservice power supply(s) electric power from service.

monitoring assembly inoperable.

B. One or both inservice B.1 Remove associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months power supplies with both inservice power supply(s) electric power from service.

monitoring assemblies inoperable.

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 Monticello 3.3.8.2-1 Amendment No. 146

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to restore one Immediately associated Completion electric power monitoring Time of Condition A or B assembly to OPERABLE not met in MODE 4 or 5 status for inservice power with RHR shutdown supply(s) supplying cooling supply isolation required instrumentation.

valves open.

OR D.2 Initiate action to-isolate the Immediately RHR Shutdown Cooling System.

E. Required Action and E.1 Initiate action to fully insert Immediately associated Completion all insertable control rods in Time of Condition A or B core cells containing one or not met in MODE 5 with more fuel assemblies.

any control rod withdrawn from a core cell containing one or more fuel assemblies.

F. Required Action and F.1.1 Isolate the associated Immediately associated Completion secondary containment Time of Condition A or B penetration flow path(s).

not met during movement of recently OR irradiated fuel assemblies in the F.1.2 Declare the associated Immediately secondary containment secondary containment or during OPDRVs. isolation valve(s) inoperable.

AND F.2.1 Place the associated Immediately standby gas treatment (SGT) subsystem(s) in operation.

OR Monticello 3.3.8.2-9 Amendment No. 146

RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F.2.2 Declare associated SGT Immediately subsystem(s) inoperable.

AND F.3.1 Place the associated Immediately control room emergency filtration (CREF) subsystem(s) in operation.

OR F.3.2 Declare associated CREF Immediately subsystem(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 Perform CHANNEL FUNCTIONAL TEST. 184 days SR 3.3.8.2.2 Perform CHANNEL CALIBRATION. The Allowable 184 days Values shall be:

a. Overvoltage _<128 V;

b. Undervoltage > 104 V; and

c. Underfrequency __57 Hz.

SR 3.3.8.2.3 Perform CHANNEL CALIBRATION of each 24 months Overvoltage, Undervoltage, and Underfrequency time delay relay. The Allowable Value shall be

< 4 seconds.

SR 3.3.8.2.4 Perform a system functional test. 24 months Monticello 3.3.8.2-3 Amendment No. 146

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation within the Normal Region of the power to flow map specified in the COLR.

OR One recirculation loop shall be in operation within the Normal Region of the power to flow map specified in the COLR and with the following limits applied when the associated LCO is applicable:

a. LCO 3.2.1, "AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR;

b. LCO 3.2.2, "MINIMUM CRITICAL POWER RATIO (MCPR)," single loop operation limits specified in the COLR; and

c. LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"

Function 2.a (Average Power Range Monitors Flow Referenced Neutron Flux- High High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

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

Operation within the Stability Buffer Region of the power to flow map specified in the COLR is allowed provided the power distribution controls specified in the COLR are in effect.

APPLICABILITY: MODES 1 and 2.

Monticello 3.4.1-1 Amendment No. 146

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Operation within the A.1 Initiate action to restore Immediately Stability Exclusion operation to within the Region of the power to Normal Region of the flow map specified in the power to flow map specified COLR. in the COLR.

OR Operation within the Stability Buffer Region of the power to flow map specified in the COLR and the power distribution controls specified in the COLR not in effect.

B. Requirements of the B.1 Satisfy the requirements of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO not met for reasons the LCO.

other than Condition A.

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 B not met.

OR No recirculation loops in operation.

Monticello 3.4.1-2 Amendment No. 146

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 ----------------------- NOTE-Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

Verify jet pump loop flow mismatch with both 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months recirculation loops in operation is:

a. < 10% of rated core flow when operating at

< 70%of rated core flow; and

b. < 5% of rated core flow when operating at

> 70% of rated core flow.

SR 3.4.1.2 Verify either: 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

a. Operation is in the Normal Region of the power to flow map specified in the COLR; or

b. Operation is in the Stability Buffer Region of the power to flow map specified in the COLR and the power distribution controls specified in the COLR are in effect.

Monticello 3.4.1-3 Amendment No. 146

Jet Pumps 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 Jet Pumps LCO 3.4.2 All jet pumps shall be OPERABLE.

APPLICABILITY: MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more jet pumps A.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 ..-.-.-- ..---------- NOTES ----------------

1. Not required to be performed until 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after associated recirculation loop is in operation.

2. Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after > 25% RTP.

Verify at least one of the following criteria (a or b) is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months satisfied for each operating recirculation loop:

a. Recirculation pump flow to speed ratio differs by

< 5% from established patterns, and jet pump loop flow to recirculation pump speed ratio differs by < 5% from established patterns; or

b. Each jet pump diffuser to lower plenum differential pressure differs by < 20% from established patterns.

Monticello 3.4.2-1 Amendment No.. 146

S/RVs 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 Safety/Relief Valves (S/RVs)

LCO 3.4.3 The safety function of seven S/RVs shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two required A.1 Restore the required S/RVs 14 days S/RVs inoperable, to OPERABLE status.

B. Required Action and B.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 not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Three or more required S/RVs inoperable.

Monticello 3-4-3-1 Amendment No. 146

S/RVs 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify the safety function lift setpoints of the required In accordance S/RVs are 1109 + 33.2 psig. Following testing, lift with the Inservice settings shall be 1109 + 11.0 psig. Testing Program SR 3.4.3.2 --------------------- 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 flow is adequate to perform the test.

Verify each required S/RV opens when manually 24 months actuated.

Monticello 3.4.3-2 Amendment No. 146

RCS Operational LEAKAGE 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Operational LEAKAGE LCO 3.4.4 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE;

b. _<5 gpm unidentified LEAKAGE;

c. < 25 gpm total LEAKAGE averaged over the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period; and

d. 5 2 gpm increase in unidentified LEAKAGE within the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months perind in .AMDE !.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Unidentified LEAKAGE A.1 Reduce LEAKAGE to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months not within limit, limits.

OR Total LEAKAGE not within limit.

B. Unidentified LEAKAGE BA1 Reduce LEAKAGE to within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months increase not within limit, limits.

OR B.2 Verify source of unidentified 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months LEAKAGE increase is not service sensitive type 304 or type 316 austenitic stainless steel.

Monticello 3.4.4-1 Amendment No. 146

RCS Operational LEAKAGE 3.4.4 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.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Pressure boundary LEAKAGE exists.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify RCS unidentified and total LEAKAGE and 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months unidentified LEAKAGE increase are within limits.

Monticello 3.4.4-2 Amendment No. 146

RCS Leakage Detection Instrumentation 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Leakage Detection Instrumentation LCO 3.4.5 The following RCS leakage detection instrumentation shall be OPERABLE:

a. Either the drywell floor drain sump monitoring system or the drywell equipment drain sump monitoring system with the drywell floor drain sump overflowing to the drywell equipment drain sump; and

b. Drywell particulate radioactivity monitoring system.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO 3.4.5.a not met. A.1 -- -- NOTE-----

LCO 3.0.4.c is applicable.

Satisfy the requirements of 30 days LCO 3.4.5.a.

B. Drywell particulate B.1 Analyze grab samples of Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months radioactivity monitoring primary containment system inoperable, atmosphere.

C. All required leakage C.1 Satisfy the requirements of 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months detection systems LCO 3.4.5.a.

inoperable.

OR C.2 Restore drywell particulate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months radioactivity monitoring system to OPERABLE status.

Monticello 3.4.5-1 Amendment No. 146

RCS Leakage Detection Instrumentation 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Perform a CHANNEL CHECK of required leakage 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months detection instrumentation.

SR 3.4.5.2 Perform a CHANNEL FUNCTIONAL TEST of the 31 days drywell particulate radioactivity monitoring system and the flow instrumentation of the required drywell drain sump monitoring system.

SR 3.4.5.3 Perform a CHANNEL CALIBRATION of required 24 months leakage detection instrumentation.

Monticello 3.4.5-2 Amendment No. 146

RCS Specific Activity 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Specific Activity LCO 3.4.6 The specific activity of the reactor coolant shall be limited to DOSE EQUIVALENT 1-131 specific activity < 2.0 pLCi/gm.

APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor coolant specific ----------- NOTE--------------

activity > 2.0 pCi/gm and LCO 3.0.4.c is applicable.

4.0 liCi/gm DOSE -..--... .... ............------------

EQUIVALENT 1-131.

A.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months EQUIVALENT 1-131.

AND A.2 Restore DOSE 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months EQUIVALENT 1-131 to within limits.

B. Required Action and B.1 Determine DOSE Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion EQUIVALENT 1-131.

Time of Condition A not met. AND OR B.2.1 Isolate all main steam lines. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Reactor Coolant specific OR activity > 4.0 jiCi/gm DOSE EQUIVALENT B.2.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 1-131.

AND B.2.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.4.6-1 Amendment No. 146

RCS Specific Activity 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 ----------------------- NOTE---------------...---------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT 1-131 7 days specific activity is < 2.0 IpCi/gm.

Monticello 3.4.6-2 Amendment No. 146

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

-NOTES-

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY: MODE 3 with reactor steam dome pressure less than the RHR shutdown cooling supply isolation interlock.

ACTIONS

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

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR A.1 Initiate action to restore Immediately shutdown cooling RHR shutdown cooling subsystems inoperable, subsystem(s) to OPERABLE status.

AND A.2 Verify an alternate method 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of decay heat removal is available for each inoperable RHR shutdown cooling subsystem.

AND A.3 Be in MODE 4. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Monticello 3.4.7-1 Amendment No. 146

RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown B.1 Initiate action to restore one Immediately cooling subsystem in RHR shutdown cooling operation. subsystem or one recirculation pump to AND operation.

No recirculation pump in AND operation.

B.2 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery circulation by an alternate of no reactor coolant method. circulition AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.3 Monitor reactor coolant Once per hour temperature and pressure.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 ----------------------

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

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is less than the RHR shutdown cooling supply isolation interlock.

Verify one RHR shutdown cooling subsystem or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months recirculation pump is operating.

Monticello 3.4.7-2 Amendment No. 146

RHR Shutdown Cooling System - Cold Shutdown

. 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown LCO 3.4.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and, with no recirculation pump in operation, at least one RHR shutdown cooling subsystem shall be in operation.

J Il L-.. ,- -I - - --

1. Both RHR shutdown cooling subsystems and recirculation pumps may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

2. One RHR shutdown cooling subsystem may be inoperable for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for the performance of Surveillances.

APPLICABILITY: MODEý 4.

ACTIONS

-- NOTE .....-------------

Separate Condition entry is allowed for each RHR shutdown cooling subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR A.1 Verify an alternate method 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months shutdown cooling of decay heat removal is subsystems inoperable, available for each AND inoperable RHR shutdown cooling subsystem. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. No RHR shutdown B.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery cooling subsystem in circulating by an alternate of no reactor coolant operation. method. circulation AND AND No recirculation pump in Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operation. thereafter AND Monticello 3.4.8-1 Amendment No. 146

RHR Shutdown Cooling System - Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2 Monitor reactor coolant Once per hour temperature and pressure.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify one RHR shutdown cooling subsystem or 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months recirculation pump is operating.

Monticello 3.4.8-2 Amendment No. 146

RCS PIT Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (P/T) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rates, and the recirculation pump starting temperature requirements shall be maintained within limits.

APPLICABILITY: At all times.

ACTIONS UUNDiTiON REUUIDLU ACTION COMPLL I IUN I IML A. -------- NOTE ---------. A.1 Restore parameter(s) to 30 minutes Required Action A.2 within limits.

shall be completed if this Condition is entered. AND A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Requirements of the acceptable for continued LCO not met in operation.

MODE 1, 2, or 3.

B. Required Action and B.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 not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. -------- NOTE --------- C.1 Initiate action to restore Immediately Required Action C.2 parameter(s) to within shall be completed if this limits.

Condition is entered.

AND Requirements of the C.2 Determine RCS is Prior to entering LCO not met in other acceptable for operation. MODE 2 or 3 than MODES 1, 2, and 3.

Monticello 3.4.9-1 Amendment No. 146

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 --------------------- NOTES ----------

1. Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.

2. Figures 3.4.9-2 and 3.4.9-3 shall be adjusted as required by Figure 3.4.9-1 for the reactor vessel shell and fluid temperature limits.

Verify: 30 minutes

a. RCS pressure and RCS temperature are within the applicable limits specified in Figures 3.4.9-2 and 3.4.9-3; and

b. RCS heatup and cooldown rates are < 100°F average over a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period.

SR 3.4.9.2 ----------- ---------- NOTE -----------------

Figure 3.4.9-4 shall be adjusted as required by Figure 3.4.9-1 for the reactor vessel shell fluid temperature limits.

Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in Figure 3.4.9-4. 15 minutes prior to control rod withdrawal for the purpose of achieving criticality Monticello 3.4.9-2 Amendment No. 146

RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.3 -- ------------------- NOTE ----------------

Only required to be met in MODES 1, 2, 3, and 4 during recirculation pump startup.

Verify the difference between the reactor coolant Once within temperature in the recirculation loop to be started 15 minutes prior and the RPV coolant temperature is < 50 0 F. to each startup of a recirculation pump SR 3.4.9.4 ----------------------- NOTE ----------------

Only required to be performed when tensioning the reactor vessel head bolting studs.

Verify reactor vessel flange and head flange 30 minutes temperatures are > 700°F.

SR 3.4.9.5 ----------------------- NOTE --------------

Not required to be performed until 30 minutes after RCS temperature < 80°F in MODE 4.

Verify reactor vessel flange and head flange 30 minutes temperatures are _>70'F.

SR 3.4.9.6 ------- NOTE--- ----

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature < 100°F in MODE 4.

Verify reactor vessel flange and head flange 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months temperatures are _> 70°F.

Monticello 3.4.9-3 Amendment No. 146

RCS P/T Limits 3.4.9 M!l Vtu Ix0

'I")

Onfl HIEU Hlfrfl

W 9&

LI-

~70

~s0 I-0 z

I-40 30 20 In, U

0 0.5 1.5 2.5 .3 3.5 18 2 1/4 Vessel Wall Thickness Fluence (10 n/cm )

Figure 3.4.9-1 Core Beltline Operating Limits Curve Adjustment Versus Fluence Monticello 3.4.9-4 Amendment No. 146

RCS Pff Limits 3.4.9 200 a)

CI-a)

E E

0 200 400 600 800 1000 13]0 1400 16M IBM] 2900 Pressure Limit in Vessel Top Head (psig)

Figure 3.4.9-2 RCS Pressure Versus Temperature Limits Inservice Leak and Hydrostatic Testing Monticello 3.4.9-5 Amendment No. 146

RCS PIT Limits 3.4.9 LO a)

E (D

E E

1wJ Pressure Limit in Vessel Top Head (psig)

Figure 3.4.9-3 RCS Pressure Versus Temperature Limits Non-Nuclear Heatup and Cooldown Monticello 3.4.9-6 Amendment No. 146

RCS P/IT Limits 3.4.9 200 S]E U- ,-- - E

/ i I

i iI-150 Core Beine -

IL 0

U-a)

CI- 100 a)

J I L . geoFulIPower E

a)

E

-1 E

I _Te_ , 'I rs) 50 0

0 200 400. 6W W00 1000 1200 1400 160 1E00 200 Pressure Limit in Vessel Top Head (psig)

Figure 3.4.9-4 RCS Pressure Versus Temperature Limits Critical Operation Monticello 3.4.9-7 Amendment No. 146

Reactor Steam Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be *1025.3 psig.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Reactor steam dome A.1 Restore reactor steam 15 minutes pressure not within limit, dome pressure to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

< 1025.3 psig.

Monticello 3.4.10-1 Amendment No. 146

ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) AND REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of three safety/relief valves shall be OPERABLE.

-- NOTE ------------------------------...--------

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

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

ACTIONS

-NOTE-LCO 3.0.4.b is not applicable to HPCI.

CONDITION REQUIRED ACTION COMPLETION TIME A. One LPCI pump A.1 Restore LPCI pump to 30 days inoperable. . OPERABLE status.

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

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 injection 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable due to path to OPERABLE status.

inoperable injection paths.

E. Required Action and L.1 Be in MuuO 6. 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.

E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Two LPCI subsystems F.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).

G. Required Action and G.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 F not met.

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

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

Monticello 3.5.1-2 Amendment No. 146

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME HPCI System 1.1 Restore HPCI System to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

AND OR Condition A, B, or C 1.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months entered. ECCS injection/spray subsystem(s) to OPERABLE status.

J. One ADS valve J.1 Restore ADS valve to 14 days inoperable. OPERABLE status.

K. One ADS valve K.1 Restore ADS valve to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable. OPERABLE status.

AND OR Condition A, B, or C K.2 Restore low pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months entered. ECCS injection/spray subsystem(s) to OPERABLE status.

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 H, 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.

Two or more ADS valves inoperable.

OR HPCI System or one or more ADS valves inoperable and Condition D or F entered.

Monticello 3.5.1-3 Amendment No. 146

ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME M. Two or more low M.1 Enter LCO 3.0.3. Immediately pressure ECCS injection/spray subsystems inoperable for reasons other than Condition C, D, or F.

OR HPCI System and one or more ADS valves SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each low pressure ECCS injection/spray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.1.2 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 Verify ADS pneumatic pressure is as follows for 31 days each required ADS pneumatic supply:

a. S/RV Accumulator Bank header pressure

> 88.3 psig; and

b. Alternate Nitrogen System pressure is

> 220 psig.

Monticello 3.5.1-4 Amendment No. 146

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.4 --------------------- NOTE------- --------

Only required to be ,met in MODE 1.

Verify the RHR System intertie return line isolation 31 days valves are closed.

SR 3.5.1.5 Verify correct breaker alignment to the LPCl 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 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 Ž2800 gpm 1 130 psi LPCI > 3870 gpm 1 > 20 psi SR 3.5.1.8 ---------------- 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 develop a flow rate Ž>2700 gpm against a system Testing Program head corresponding to reactor pressure.

Monticello 3.5.1-5 Amendment No. 146

ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.9 - ------------------ 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 pressure < 165 psig, the HPCI 24 months pump can develop a flow rate _ 2700 gpm against a system head corresponding to reactor pressure.

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 automatic initiation signal.

SR 3.5.1.12 -------------------- 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 opens when manually 24 months actuated.

SR 3.5.1.13 Verify automatic transfer capability of the LPCI 24 months swing bus power supply from the normal source to the backup source.

Monticello 3.5.1-6 Amendment No. 146

ECCS - Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) AND REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) 3.5.2 ECCS - Shutdown LCO 3.5.2 Two low pressure ECCS injection/spray subsystems shall be OPERABLE.

- 1' Ir-------- - - -

One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.

APPLICABILITY: MODE 4, MODE 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 CONDTON REQUIRED ACTION COMPLETION TIME A. One required ECCS A.1 Restore required ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months injection/spray injection/spray subsystem subsystem inoperable, to OPERABLE status.

B. Required Action and B.1 Initiate action to suspend Immediately associated Completion operations with a potential Time of Condition A not for draining the reactor met. vessel (OPDRVs).

C. Two required ECCS C.1 Initiate action to suspend Immediately injection/spray OPDRVs.

subsystems inoperable.

AND C.2 Restore one required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ECCS injection/spray subsystem to OPERABLE status.

Monticello 3.5.2-1 Amendment No. 146

ECCS - Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and D.1 Initiate 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.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required ECCS injection/spray 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months subsystem, the:

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

b. ------ NOTE------ -----

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

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

Monticello 3.5.2-2 Amendment No. 146

ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required ECCS injectiontspray 31 days subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.2.3 Verify each required ECCS injection/spray 31 days subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.4 Verify each required ECCS pump develops 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 _2800 gpm 1 > 130 psi LPCI > 3870 gpm 1 > 20 psi SR 3.5.2.5 ----------------------- NOTE-Vessel injection/spray may be excluded.

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

Monticello 3.5.2-3 Amendment No. 146

RCIC System 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS) AND REACTOR CORE ISOLATION COOLING 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-I Cro 3" 4 h is nnt pnnli~habl to the RC!C. -Syseftm CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System A.1 Verify by administrative Immediately inoperable, means High Pressure Coolant Injection System is OPERABLE.

AND A.2 Restore RCIC System to 14 days OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND 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

RCIC System 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.'1 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 perform the test.

Verify, with reactor pressure _ 1025.3 psig and In accordance

_ 950 psig, the RCIC pump can develop a flow rate with the Inservice

Ž_ 400 gpm against a system head corresponding to Testing Program reactor pressure.

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 reactor steam pressure and flow are adequate to perform the test.

Verify, with reactor pressure < 165 psig, the RCIC 24 months pump can develop a flow rate _> 400 gpm against a system head corresponding to reactor pressure.

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.

Monticello 3.5.3-2 Amendment No. 146

Primary Containment 3.6.1.1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment LCO 3.6.1-.1 Primary containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable, containment to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and leakage In accordance rate testing except for primary containment air lock with the Primary testing, in accordance with the Primary Containment Containment Leakage Rate Testing Program. Leakage Rate Testing Program Monticello 3.6.1..1-1 Amendment No. 146

Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY I

SR 3.6.1.1.2 Verify drywell to suppression chamber bypass 24 months leakage is less than that equivalent to a one inch diameter orifice. AND NOTE -------- -

Only required after two consecutive tests fail and continues until two consecutive tests pass 12 months Monticello 3.6.1.1-2 Amendment No. 146

Primary Containment Air Lock 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Lock LCO 3.6.1.2 The primary containment air lock shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

,M h*.i,*T*I-- C'*

I In -----------------------------------------------------------

1. Entry and exit is permissible to perform repairs of the air lock components.

2. Enter applicable Conditions qnd Requ1itired Artinns of L_(CO1' R*1 "Primann Containment,"

when air lock leakage results in exceeding overall primary containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. One primary -- - -NOTES ---------

containment air lock 1. Required Actions A.1, A.2, door inoperable, and A.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls.

A.1 Verify the OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed.

AND A.2 Lock the OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed.

AND Monticello 3.6.1.2-1 Amendment No. 146

Primary Containment Air Lock 316.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 ---------- NOTE ----------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify the OPERABLE door Once per 31 days is locked closed.

B. Primary containment air ------------- NOTES----------

lock interlock 1. Required Actions B.1, B.2, mechanism inoperable, and B.3 are not applicable if both doors in the air lock are inoperable and Condition C is entered.

2. Entry into and exit from containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed.

AND B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed.

AND Monticello 3.6.1.2-2 Amendment No. 146

Primary Containment Air Lock 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.3 ---- NOTE--------

Air Lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify an OPERABLE door Once per 31 days is rocked closed.

C. Primary containment air C.1 initiate action to evaluate Immediately lock inoperable for prymary containment overall reasons other than leakage rate per Condition A or B. LCO 3.6.1.1, using current air lock test results.

AND C.2 Verfy a door is. closed. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND C.3 Restore air lock to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3*.61.2-3 Amendment No. 146

Primary Containment Air Lock 3.6.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 ------------------------------ NOTES------- ------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria applicable to SR 3.6.1.1.1.

Perform required primary containment air lock In accordance leakage rate testing in accordance with the Primary with the Primary Cnntninm ent I eaka-e Rate Testing D, ,C.4,, , t Leakage Rate Testing Program SR 3.6.1.2.2 Verify only one door in the primary containment air 24 months lock can be opened at a time.

Monticello 3.6.1.2-4 Amendment No. 146

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

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

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A.- --------- NOTE --------- A.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 penetration flow path by main steam line penetration flow paths use of at least one closed with two PCIVs. and de-activated automatic AND valve, closed manual valve, blind flange, or check valve 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.

Monticello 3.6.1.3-1 Amendment No. 146

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, penetration flow path is isolation devices isolated. outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment Monticello 3.6.1.3-2 Amendment No. 146

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. -------- NOTE ------------ 8 .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.

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 penetration flow path by excess flow check penetration flow paths use of at least one closed valves (EFCVs) and with only one PCIV. and de-activated automatic penetrations with a valve, closed manual valve, closed system or blind flange.

One or more penetration AND flow paths with one PCIV inoperable. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for EFCVs and penetrations with a closed system AND Monticello 3.6.1.3-3 Amendment No. 146

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C.2 ---------- NOTES-------

1. Isolation devices in high radiation areas may be verifiedby 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 penetration flow path is isolation devices isolated. outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, not af performed within the previous 92 days, for isolation devices inside primary containment Monticello 3.6.1.3-4 Amendmenrt 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.

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 penetration flow path is isolation devices isolated. outside containment E. Required Action and E.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. E.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

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.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.

F.2 Initiate action to restore Immediately valve(s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 --------------- NOTE -----------------

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

Verify each 18 inch primary containment purge and 31 days vent valve is closed.

Monticello 3.6.1.3-6 Amendment No. 146

PC IVs 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

,TArl irpri qnri and not locked,*, sealed, icz raq irirrij f*,to be or, otherwise clI-, -se

, during a ^id-I.

ondtions - - -- - . . -- I I conditions is closed.

SR 3.6.1.3.3 ....-------.---------- NOTES ---------------

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

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment manual isolation Prior to entering valve and blind flange that is located inside primary MODE 2 or 3 from containment and not locked, sealed, or otherwise MODE 4 if secured and is required to be closed during accident primary conditions is closed. 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 sim~lated 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 vent valve is blocked to restrict the valve from opening > 400.

SR 3.6.1.3.10 Remove and test the explosive squib from each 24 months on a shear isolation valve of the TIP System. STAGGERED TEST BASIS SR 3.6.1.3.11 Perform leakage rate testing for each 18 inch In accordance primary containment purge and vent valve with with the Primary resilient seals. Containment Leakage Rate Testing Program Monticello 3.6.1.3-8 Amendment No. 146

Drywell Air Temperature 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Drywell Air Temperature LCO 3.6.1.4 Drywell average air temperature shall be _*135°F.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell average air 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within temperature to within limit.

limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.4.1 Verify drywell average air temperature is within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ' Monticello 3.6.1.4-1 Amendment No. 146

LLS Valves 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Low-Low Set (LLS) Valves LCO 3.6.1.5 The LLS function of three safety/relief valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One LLS valve A.1 Restore LLS valve to 14 days inoperable. OPERABLE status.

B. Required Action and B.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 not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Two or more LLS valves inoperable.

Monticello 3.6.1.5-1 Amendment No. 146

LLS Valves 3.6.1.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 ---------------------- 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 LLS valve opens when manually 24 months on a actuated. STAGGERED TEST BASIS for each valve solenoid SR 3.6.1.5.2 ---------------------- NOTE----------------

Valve actuation may be excluded.

Verify the LLS System actuates on an actual or 24 months simulated automatic initiation signal.

Monticello 3.6.1.5-2 Amendment No. 146

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Reactor Building-to-Suppression Chamber Vacuum Breakers LCO 3.6.1.6 Each reactor building-to-suppression chamber vacuum breaker shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

--- ----------- NOTI= -----------------------------------------------------------

Separate Condition entry is allowed for each line.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more lines with A.1 Close the open vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months one reactor building-to- breaker.

suppression chamber vacuum breaker not closed.

B. One or more lines with B.1 Close one open vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months two reactor building-to- breaker.

suppression chamber vacuum breakers not closed.

C. One line with one or C.1 Restore the vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months more reactor building-to- breaker(s) to OPERABLE suppression chamber status.

vacuum breakers inoperable for opening.

D. Two lines with one or D.1 Restore all vacuum 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months more reactor building-to- breakers in one line to suppression chamber OPERABLE status.

vacuum breakers inoperable for opening.

Monticello 3.6.1.6-1 Amendment No. 146

Reactor Building-to-Suppression Chamber Vacuum Breakers 3.6.1.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time not met. AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS

I ID\I./:II I A#lIfr"

,*,,,,,,-,-*,,*.,,-FREQUENCY SR 3.6.1.6.1 -NOTES -------

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers open when performing their intended function.

Verify each vacuum breaker is closed. 14 days SR 3.6.1.6.2 Perform a functional test of each vacuum breaker. 92 days SR 3.6.1.6.3 Verify the opening setpoint of each vacuum breaker 92 days is < 0.5 psid.

Monticello 3.6.1.6-2 Amendment No. 146

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 3.6 CONTAINMENT SYSTEMS 3.6.1.7 Suppression Chamber-to-Drywell Vacuum Breakers LCO 3.6.1-7 Seven suppression chamber-to-drywell vacuum breakers shall be OPERABLE for opening.

AND Eight suppression chamber-to-drywell vacuum breakers shall be closed.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required A.1 Restore one vacuum 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months suppression chamber-to- breaker to OPERABLE drywell vacuum breaker status.

inoperable for opening.

B. One suppression B.1 Close the open vacuum 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

- chamber-to-drywell breaker.

vacuum breaker not closed.

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 not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.6.1.7-1 Amendment No. 146

Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.7.1 -------------------- NOTES--------------

1. Not required to be met for vacuum breakers that are open during Surveillances.

2. Not required to be met for vacuum breakers performing their intended function.

3. Not required to be met for vacuum breakers being cycled, one at a time, during primary containment inerting and de-inerting operations.

Verify each vacuum breaker is closed. 14 days AND Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after any operation that causes the drywell-to-suppression chamber differential pressure to be reduced by

> 0.5 psid if any vacuum breaker position indicator does not indicate closed SR 3.6.1.7.2 Perform a functional test of each required vacuum 31 days' breaker.

SR 3.6.1.7.3 Verify the opening setpoint of each required vacuum 24 months breaker is < 0.5 psid.

Monticello 3.6.1.7-2 Amendment No. 146

RHR Drywell Spray 3.6.1.8 3.6 CONTAINMENT SYSTEMS 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray LCO 3.6.1.8 Two RHR drywell spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR drywell spray A.1 Restore -RHR drywell spray 7 days subsystem inoperable. subsystem to OPERABLE status.

B. Two RHR drywell spray B.1 Restore one RHR drywell 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months subsystems inoperable, spray subsystem to OPERABLE status.

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 not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.8.1 Verify each RHR drywell spray subsystem manual 31 days and power operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

Monticello 3.6.1.8-1 Amendment No. 146

RHR Drywell Spray 3.6.1.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.8.2 Verify each drywell spray header and nozzle is 10 years unobstructed.

Monticello 3.6.1.8-2 Amendment No. 146

Suppression Pool Average Temperature 3.6.2.1 3.6 CONTAINMENT SYSTEMS 3.6.2.1 Suppression Pool Average Temperature LCO 3.6.2.1 Suppression pool average temperature shall be:

a. __9 0 ° F with THERMAL POWER > 1% RTP and no testing that adds heat to the suppression pool is being performed;

b. <_1000 F with THERMAL POWER > 1% RTP and testing that adds heat to the suppression pool is being performed; and

c. < 11 0°F with THERMAL POWER < 1% RTP.

APPLICABILITY-:- -MODESj1-,2,-and-3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool A.1 Verify suppression pool Once per hour average temperature average temperature

> 9 0 °F but.< 110°F. -110 0 F.

AND AND THERMAL POWER A.2 Restore suppression pool 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> 1% RTP. average temperature to

_900 F.

AND Not performing testing that adds heat to the suppression pool.

B. Required Action and B.1 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion POWER to

1% RTP.

Time of Condition A not met.

Monticello 3-6-2-1-1 Amendment No. 146

Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Suppression pool C.1 Suspend all testing that Immediately average temperature adds heat to the

> 100 0 F. suppression pool.

AND THERMAL POWER

> 1% RTP.

AND Performing testing that adds heat to the suippression pool_ .. . .. .. . . . . . . . . ..... .. . . .. . . .. ...

D. Suppression pool D.1 Place the reactor mode Immediately average temperature switch in the shutdown

> 110 0 F. position.

AND D.2 Determine suppression Once per 30 minutes pool average temperature.

AND D.3 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Suppression pool E.1 Depressurize the reactor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months average temperature vessel to < 200 psig.

> 120 0 F.

Monticello 3.6.2.1-2 Amendment No. 146

Suppression Pool Average Temperature 3.6.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within the applicable limits.

AND 5 minutes when performing testing that adds heat to the suppression pool Monticello 3.6.2.1-3 Amendment No. 146

Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be > - 4.0 inches and _< + 3.0 inches.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression pool 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within limits, water level to within-li- its. -

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Monticello 3.6.2.2-1 Amendment No. 146

RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 Two RHR suppression pool cooling subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression A.1 Restore RHR suppression 7 days pool cooling subsystem poo I-cooling-sby 5ite-m-f--

inoperable. OPERABLE status.

B. Two RHR suppression B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months pool cooling subsystems suppression pool cooling inoperable, subsystem to OPERABLE status.

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 not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days subsystem manual and power operated valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

Monticello 3.6.2.3-1 Amendment No. 146

RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.2.3.2 Verify each required RHR pump develops a flow In accordance rate > 3870 gpm through the associated heat with the Inservice exchanger while operating in the suppression pool Testing Program cooling mode.

Monticello 3.6.2.3-2 Amendment No. 146

Primary Containment Oxygen Concentration 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Oxygen Concentration LCO 3.6.3.1 The primary containment oxygen concentration shall be < 4.0 volume percent.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months oxygen concentration concentration to within limit.

not within limit.

B. Required Action and B.1 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion POWER to _ 15% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Verify primary containment oxygen concentration is 7 days within limits.

Monticello 3.6.3.1-1 Amendment No. 146

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 A. Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable in MODE 1, containment to OPERABLE 2, or 3. status.

B. Required Action and B.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 not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Secondary containment C.1 NOTE-......-

inoperable during LCO 3.0.3 is not applicable.

movement of recently --

irradiated fuel assemblies in the Suspend movement of 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

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is Ž 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.

-S.13-3.6.4.1.4-- VerLfythe secondary.containment can be 24 months on a maintained _>0.25 inch of vacuum water gauge for STAGGERED 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 TEST BASIS for

4000 cfm. each SGT subsystem 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. Separate Condition entry is allowed for each penetration flow path.

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow paths with one penetration flow path by SCIV inoperable, use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND Monticello 3.6.4.2-1 Amendment No. 146

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 penetration flow path is isolated.

B. ------- NOTE --------- B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path by penetration flow paths use of at least one closed with two isolation valves, and de-activated automatic valve, closed manual valve, or blind flange.

One or more penetration flow paths with two SCIVs inoperable.

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 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 OPDR Vs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 --------------------- NOTES -------------------

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

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment isolation manual 31 days valve and blind flange that is not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.

SR 3.6.4.2.2 Verify the isolation time of each power operated, 92 days automatic SCIV is within limits.

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

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 C-IOMFIETION TIME A. One SGT subsystem A.1 Restore SGT subsystem to 7 days inoperable. OPERABLE status.

B. Required Action and B.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 not AND met in MODE 1, 2, or 3.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. 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 C.1 Place OPERABLE SGT Immediately assemblies in the subsystem in operation.

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

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 secondary containment recently irradiated fuel or during OPDRVs. assemblies in secondary containment.

AND E.2 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each S.GT subsystem for > 10 continuous 31 days hours with heaters operating.

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

RHRSW System 3.7.1 3.T PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System LCO 3.7.1 Two RHRSW subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

'A,&_One-RHRSaW-subsystem. A.1 ------------ NOTE -------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown," for RHR shutdown cooling made inoperable by RHRSW System.

Restore RHRSW 7 days subsystem to OPERABLE status.

B. Both RHRSW B.1 ----------- NOTE-------

subsystems inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7 for RHR shutdown cooling made inoperable by RHRSW System.

Restore one RHRSW 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months subsystem to OPERABLE status.

Monticello 3.7.1-1 Amendment No. 146

RHRSW System 3.7.1 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 not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify each RHRSW manual, power operated, and 31 days automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position or can be aligned to the correct position.

Monticello 3.7.1-2 Amendment No. 146

ESW System and UHS 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS)

_CO 3.7.2 Two ESW subsystems and UHS shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.- -One-ESW subsystem.---A.-I NOTE-...

inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.7, "Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown," for RHR shutdown cooling made inoperable by ESW.

Restore the ESW 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status.

B. Required Action and B.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 not AND met.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Both ESW subsystems inoperable.

OR UHS inoperable.

Monticello 3.7.2-1 Amendment No. 146

ESW System and UHS 3.7.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level in the intake structure is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> 899 ft mean sea level.

SR 3.7.2.2 Verify the average water temperature of UHS is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

< 90 0 F.

SIR 3.7.2.3 --. NOTE ----------------

Isolation of flow to individual components does not render ESW System inoperable.

Verify each ESW subsystem manual and automatic 31 days valve in the flow paths servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.2.4 Verify each ESW subsystem actuates on an actual 24 months or simulated initiation signal.

Monticello 3.7.2-2 Amendment No. 146

EDG-ESW System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Emergency Diesel Generator-Emergency Service Water (EDG-ESW) System LCO 3.7.3 Two EDG-ESW subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

NOTE- -...--.------------

Separate Condition entry is allowed for each EDG-ESW subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more EDG-ESW A.1 Declare associated EDG Immediately subsystems inoperable. inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify each EDG-ESW subsystem manual valve in 31 days the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.3.2 Verify each EDG-ESW subsystem pump starts 24 months automatically when the associated EDG starts and energizes the respective bus.

Monticello 3.7.3-1 Amendment No. 146

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.

,I*IL J I

I'.ALJ" r .....

The main control room 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, Du ring operations with a potential for - rainingthereactoryessel-(OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREF subsystem A.1 Restore CREF subsystem 7 days inoperable, to OPERABLE status.

B. Two CREF subsystems B.1 Restore control room 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months inoperable due to boundary to OPERABLE inoperable control room status.

boundary in MODE 1, 2, or 3.

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 Monticello 3.7.4-1 Amendment No. 146

CREF System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 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.

or during OPDRVs.

OR D.2.1 Suspend movement of Immediately recently irradiated fuel

-assemblies-in-the. .

secondary containment.

AND D.2.2 Initiate action. to suspend Immediately OPDRVs.

E. Two CREF subsystems E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

Monticello 3.7.4-2 Amendment No. 146

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.

AND F.2 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each CREF subsystem for _ 10 continuous 31 days hours with the heaters operating.

SR 3.7.4.2 Perform required CREF filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). 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 Verify each CREF subsystem can maintain a 24 months on a positive pressure relative to adjacent areas during STAGGERED the pressurization mode of operation at a flow rate TEST BASIS of *< 1100 cfm.

Monticello 3.7.4-3 Amendment No. 146

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 A. 1 Restore control room 30 days ventilation subsystem ventilation subsystem to inoperable. OPERABLE status.

B. Required Action and B.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 not AND met in MODE 1, 2, or 3.

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Required Action and --------------NOTE ------

associated Completion LCO 3.0.3 is not applicable.

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

met during movement of irradiated fuel C.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

Control Room Ventilation System 3.7.5 ACTIONS (continued)

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

AND C.2.2 Initiate action to suspend Immediately OPDRVs.

D. Two control room D.1 Enter LCO 3.0.3. Immediately ventilation subsystems inoperable-in MODEI -..

2, or 3.

E. Two control room ---- NOTE----

ventilation subsystems LCO 3.0.3 is not applicable.

inoperable during -----.......---------------------------

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

AND E.2 Initiate actions to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each control room ventilation subsystem has 24 months the capability to remove the assumed heat load.

Monticello 3.7.5-2 Amendment No. 146

Main Condenser Offgas 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Condenser Offgas LCO 3.7.6 The gross gamma activity rate of the noble gases measured at the main condenser offgas system pretreatment monitor station shall be

< 260 mCi/second after decay of 30 minutes.

APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated and steam jet air ejector (SJAE) in operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross gamma activity A.1 Restore gross gamma 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months rate of the noble gases activity rate of the noble not within limit. gases to within limit.

B. Required Action and B.1 Isolate all main steam lines. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. OR B.2 Isolate SJAE. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR B.3.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.3.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.7.6-1 Amendment No. 146

Main Condenser Offgas 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 -------------------- NOTE---------------

Not required to be performed until 31 days after any main steam line not isolated and SJAE in operation.

Verify the gross gamma activity rate of the noble 31 days gases is < 260 mCi/second after decay of 30 ,minutes. AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a

> 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level Monticello 3.7.6-2 Amendment No. 146

Main Turbine Bypass System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Main Turbine Bypass System LCO 3.7.7 The Main Turbine Bypass System shall be OPERABLE.

APPLICABILITY: THERMAL POWER _>25% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

--A. -Main-Turbine-Bypass- . A.1 ---,-...RestoreMain_-urbine_- .2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ....

System inoperable. Bypass System to OPERABLE status.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to < 25% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Verify one complete cycle of each main turbine 92 days bypass valve.

SR 3.7.7.2 Perform a system functional test. 24 months SR 3.7.7.3 Verify the TURBINE BYPASS SYSTEM 24 months RESPONSE TIME is within limits.

Monticello 3.7.7-1 Amendment No. 146

Spent Fuel Storage Pool Water Level 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Spent Fuel Storage Pool Water Level LCO 3.7.8 The spent fuel storage pool water level shall be 2!37 ft above the bottom of the spent fuel storage pool.

APPLICABILITY: During movement of irradiated fuel assemblies in the spent fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Spent fuel storage pool A.1 ----- NOTE -....--------

water level not within LCO 3.0.3 is not applicable.

limit.

Suspend movement of Immediately irradiated fuel assemblies in the spent fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify the spent fuel storage pool water level is 7 days

> 37 ft above the bottom of the spent fuel storage pool.

Monticello 3.7.8-1 Amendment No. 146

AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmrssion network and the onsite Class 1E AC Electrical Power Distribution System; and

b. Two emergency diesel generators (EDGs).

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

-NOTE.

LCO 3.0.4.b is not applicable to EDGs.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite A.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months circuit inoperable. OPERABLE required offsite circuit. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Declare required feature(s) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from with no offsite power discovery of no offsite available inoperable when power to one division the redundant required concurrent with feature(s) are inoperable. inoperability of redundant required feature(s)

AND Monticello 3.8.1-1 Amendment No. 146

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3 Restore required offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE status.

B. One EDG inoperable. B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OPERABLE required offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required feature(s), 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from supported by the inoperable discovery of EDG, inoperable when the Condition B redundant required concurrent with feature(s) are inoperable. inoperability of redundant required feature(s)

AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months EDG is' not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE EDG.

AND Monticello 3.8.1-2 Amendment No. 146

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.4 Restore EDG to 7 days OPERABLE status.

C. Two required offsite C.1 Declare required feature(s) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from circuits inoperable. inoperable when the discovery of redundant required Condition C feature(s) are inoperable, concurrent with inoperability of redundant required feature(s)

AND C.2 Restore one required offsite 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months circuit to OPERABLE status.

D. One required offsite ----------------- NOTE----

circuit inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.7, AND "Distribution Systems - Operating,"

when Condition D is entered with no One EDG inoperable. AC power source to any division.

D.1 Restore required offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status.

OR D.2 Restore EDG to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OPERABLE status.

E. Two EDGs inoperable. E.1 Restore one EDG to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months OPERABLE status.

Monticello 318.1-3 Amendment No. 146

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME 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, D, or E not met.

F.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months G. Three or more required G.1 Enter LCO 3.0.3. Immediately AC sources inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated 7 days power availability for each required offsite circuit.

SR 3.8.1.2 ----------------------- NOTES ----------------

1. All EDG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

2. A modified EDG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer.

Verify each EDG starts from standby conditions and 31 days achieves steady state voltage > 3975 V and

4400 V and frequency > 58.8 Hz and _< 61.2 Hz.

Monticello 3.8.1-4 Amendment No. 146

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.3 -NOTES -----------------------------

1. EDG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveiflance shall be conducted on only one EDG at a time.

4. This SR shall be preceded by and immediately follow, without shutdown, a successful performance of SR 3.8.1.2.

Verify each EDG is synchronized and loaded and 31 days operates for _>60 minutes at a load > 2250 kW and

< 2500 kW.

SR 3.8.1.4 Check for and remove accumulated water from each 31 days day tank and base tank.

SR 3.8.1.5 Verify the fuel oil transfer system operates to 31 days transfer fuel oil from the storage tank to the day tanks and from each day tank to the associated base tank.

SR 3.8.1.6 - -NOTE ------- ------

This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify automatic and manual transfer of unit power 24 months on a supply from the normal offsite circuit to the alternate STAGGERED offsite circuit. TEST BASIS for each division Monticello 3.8.1-5 Amendment No. 146

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.7 -------------------- NOTES ---

1. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

2. If performed with EDG synchronized with offsite power, it shall be performed within the power factor limit. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each EDG rejects a load greater than or equal 24 months to its associated single largest post-accident load, and following load rejection, the frequency is

< 67.5 Hz.

SR 3.8.1.8 --------------------- NOTE-------

This Surveillance shall not normally be performed in MODE 1 or 2. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated Emergency Core 24 months Cooling System (ECCS) initiation signal, permanently connected loads remain energized' from the offsite power system and emergency loads are auto-connected through the time delay relays from the offsite power system.

Monticello 3-8-1-6 Amendment No. 146

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 -NOTES ----------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not normally be performed in MODE 1 or 2. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

3. If part b is performed with EDG synchronized with offsite power, it shall be performed within the power factor limit. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.

Verify each EDG operates for Ž_8 hours: 24 months

a. For _ 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded _>2625 kW and

_<2750 kW; and

b. For the remaining hours of the test loaded

_ 2250 kW and < 2500 kW.

Monticello 3.8.1-7 Amendment No. 146

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.10 NOTES- --

1. This Surveillance shall be performed within 5 minutes of shutting down the EDG after the EDG has operated > 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded >_2250 kW and < 2500 kW.

Momentary transients outside of load range do not invalidate this test.

2. All EDG starts may be preceded by an engine prelube period.

Verify each EDG starts and achieves: 24 months

a. 10 seconds, voltage > 3975 V and In <__

frequency > 58.8 Hz; and

b. Steady state voltage __3975 V and

4400 V and frequency > 58.8 Hz and < 61.2 Hz.

i SR 3.8.1.11 -NOTE This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify each EDG: 24 months

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

Monticello 3.8.1-8 Amendment No. 146

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUEN'CY SR 3.8.1.12 -------------------- NOTES--------------

1. All EDG starts may be preceded by an engine prelube period.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of offsite 24 months power signal in conjunction with an actual or simulated ECCS initiation signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. EDG auto-starts from standby condition and:

1. Energizes permanently connected loads in < 10 seconds;

2. Energizes auto-connected emergency loads through time delay relays;

3. Achieves steady state voltage > 3975 V and _< 4400 V;

4. Achieves steady state frequency

> 58.8 Hz and < 61.2 Hz; and

5. Supplies permanently connected and auto-connected emergency loads for

Ž_5 minutes.

Monticello 3.8.1-9 Amendment No. 146

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13 7----- -- NOTE ----------------------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, this Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load block 24 months is greater than or equal to the minimum design load interval.

Monticello 3.8.1-10 Amendment No. 146

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 lE AC electrical power distribution subsystem(s) required by LCO 3.8.8.

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

ACTIONS

1. I~T~'I JI ---------------------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite ------------- NOTE - --

circuit inoperable. 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

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 irradiated fuel assemblies in the secondary containment AND A.2.3 Initiate action to suspend Immediately operations with a potential for draining the reactor vessel (OPDRVs).

AND A.2.4 Initiate action to restore immediately required offsite power circuit to OPERABLE status.

B. One required EDG B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

AND B.2 Suspend movement of immediately irradiated fuel assemblies in the secondary containment AND B.3 Initiate action to suspend Immediately OPDRVs.

AND B.4 Initiate action to restore Immediately required EDG to OPERABLE status.

Monticello 3.8.2-2 Amendment No. 146

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: SIR 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 Monticello 3.8.2-3 Amendment No. 146

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystems shall be within limits for each required emergency diesel generator (EDG).

APPLICABILITY: When associated EDG is required to be OPERABLE.

ACTIONS Separate-Condition-entry-is-allowed-for-eac-NOTE- ---

Separate Condition entry is allowed for each EDG.

CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel oil level A.1 Restore fuel oil level to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

< 38,300 gal and within limits.

> 33,600 gal in storage tank.

B. One or more EDGs with B.1 Restore lube oil inventory to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months lube oil inventory within limits.

< 165 gal and > 142 gal.

C. Stored fuel oil total C.1 Restore fuel oil total 7 days particulates not within particulates to within limit.

limit.

D. New fuel oil properties D.1 Restore stored fuel oil 30 days not within limits, properties to within limits.

Monticello 3.8.3-1 Amendment No. 146

Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more EDGs with E.1 Restore starting air receiver 7 days starting air receiver pressure to > 165 psig.

pressure in one starting air subsystem

< 165 psig.'

F. One or more EDGs with F.1 Restore starting air receiver 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months starting air receiver pressure in one starting air pressure in both starting subsystem to > 165 psig.

air subsystems

< 165 psig and

Ž125 psig.

G. Required Action and G.1 Declare associated EDG Immediately associated Completion inoperable.

Time of Condition A, B, C, D, E, or F not met.

OR One or more EDGs with diesel fuel oil, lube oil, or starting air subsystem(s) not within limits for reasons other than Condition A, B, C, D, E, or F.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify the fuel oil storage tank contains > 38,300 gal 31 days of fuel.

SR 3.8.3.2 Verify, for each EDG, lube oil inventory is > 165 gal. 31 days Monticello 3.8.3-2 Amendment No. 146

Diesel Fuel Oil, Lube Oil. and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance are tested in accordance with, and maintained within with. the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuet Oil Testing Program SR 3.8.3.4 Verify each EDG air start receiver pressure is 31 days

> 165 psig.

SR 3.8.3.5 Check for and remove accumulated water from the 31 days fuel oil storage tank.

Monticello 3.8.3-3 Am*ndment No. 146

DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 The Division 1 and Division 2 125 VDC and 250 VDC electrical power subsystems shall be OPERABLE.

APPLICABILITY: MODES 1,2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore battery terminal 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months battery chargers on voltage to greater than or Division 1 or Division 2 equal to the minimum inoperable, established float voltage.

AND A.2 Verify battery float current Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

< 2 amps for 250 VDC batteries and < 1 amp for 125 VDC batteries.

AND A.3 Restore required Division 1 7 days or Division 2 battery charger(s) to OPERABLE status.

B. One Division 1 or B.1 Restore Division 1 or 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Division 2 DC electrical Division 2 DC electrical power subsystem power subsystem to inoperable for reasons OPERABLE status.

other than Condition A.

Monticello 3.8.4-1 Amendment No. 146

DC Sources - Operating 3.8.4 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 not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater than or 7 days equal to the minimum established float voltage.

SR 3.8.4.2 Verify each required battery charger supplies 24 months

> 150 amps for 250 VDC subsystems and

_ 50 amps for 125 VDC subsystems, at greater than or equal to the minimum established float voltage for 2!4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

OR Verify each required battery charger can recharge the battery to the fully charged state within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for 250 VDC subsystems and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for 125 VDC subsystems while supplying the largest combined demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state.

Monticello 3.8.4-2 Amendment No. 146

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.3 ------------------- NOTES -----------------------------

1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of SR 3.8.4.3.

2. This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and 24 months maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

Monticello 3.8.4-3 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 irradiated fuel assemblies in the secondary containment.

ACTIONS

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical A.1 Suspend CORE Immediately power subsystem ALTERATIONS.

inoperable.

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

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

AND A.4 Initiate action to restore Immediately required DC electrical power subsystem to OPERABLE status.

Monticello 3.8.5-1 Amendment No. 146

DC Sources - Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 NOTE.-------------N----------------

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.

Monticello 3.8.5-2 Amendment No. 146

Battery Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters LCO 3.8.6 Battery parameters for the Division 1 and Division 2 125 VDC and 250 VDC batteries shall be within limits.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS k I ~X.Y.I.

ZL JI ------------ - - ------------------------

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries A.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with one or more battery cells float voltage AND

< 2.07 V.

A.2 Perform SR 3.8.6.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months AND A.3 Restore affected cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months yoltage >_2.07 V.

B. One or more batteries B.1 Perform SR 3.8.4.1. 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months with float current

> 2 amps for 250 VDC AND batteries or > 1 amp for 125 VDC batteries. B.2 Restore battery float current 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to < 2 amps for 250 VDC batteries or < 1 amp for 125 VDC batteries.

Monticello 3.8.6-1 Amendment No. 146

Battery Parameters 3.8.6 ACTIONS (continued)__

CONDITION REQUIRED ACTION COMPLETION TIME

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

Required Action C.2 shall be Required Actions C.1 and C.2 are completed if electrolyte level only applicable if electrolyte level was below the top of plates. was below the top of plates.

C. One or more batteries C.1 Restore electrolyte level to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months with one or more cells above top of plates.

electrolyte level less than minimum AND established design limits. C.2 Verify no evidence of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months leakage.

AND C-3 Restore electrolyte level to 31 days greater than or equal to minimum established design limits.

D. One or more batteries D-1 Restore battery pilot cell 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with pilot cell electrolyte temperature to greater than temperature less than or equal to minimum minimum established established design limits.

.design limits.

E. Batteries in redundant E.1 Restore battery parameters 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months divisions with battery for batteries in one division parameters not within to within limits.

limits.

Monticello 3.8.6-2 Amendment No. 146

Battery Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Declare associated battery Immediately associated Completion inoperable.

Time of Condition A, B, C, D, or E not met.

OR One or more batteries with one or more battery cells float voltage

< 2.07 V and float current > 2 amps for 250 VDC batteries or

> 1 amp for 125 VDC batteries.

OR SR 3.8.6.6 not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 ----------------------- NOTE -----

Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1.

Verify each battery float current is < 2 amps for 7 days 250 VDC batteries and < 1 amp for 125 VDC batteries.

SR 3.8.6.2 Verify each battery pilot cell voltage is > 2.07 V. 31 days SR 3.8.6.3 Verify each battery connected cell electrolyte level is 31 days greater than or equal to minimum established design limits.

Monticello 3.8.6-3 Amendment No. 146

Battery Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.4 Verify each battery pilot cell temperature is greater 31 days than or equal to minimum established design limits.

SR 3.8.6.5 Verify each battery connected cell voltage is 92 days

Ž2.07 V.

SR 3.8.6.6 -------------------- NOTE---------------

This Surveillance shall not normally be performed in MODE 1, 2, or 3. However, portions of the Surveillance may be performed to reestablish OPERABILITY provided an assessment determines the safety of the plant is maintained or enhanced.

Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is > 90% of the 60 months manufacturer's rating when subjected to a performance discharge test or a modified AND performance discharge test.

12 months when battery shows degradation, or has reached 85%

of the expected life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity

_>100% of manufacturer's rating Monticello 3.8.6-4 Amendment No. 146

Distribution Systems - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Distribution Systems - Operating LCO 3.8.7 Division 1 and Division 2 AC and DC electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more AC -------------- NOTE ----------

electrical power Enter applicable Conditions and distribution subsystems Required Actions of LCO 3.8.4, "DC inoperable. Sources - Operating," for DC divisions made inoperable by inoperable power distribution subsystems.

A.1 Restore AC electrical power 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months distribution subsystem(s) to OPERABLE status.

B. One or more DC B.1 Restore DC electrical 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months electrical power power distribution distribution subsystems subsystem(s) to inoperable. OPERABLE status.

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.

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Monticello 3.8.7-1 Amendment No. 146

Distribution Systems - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two or more electrical D.1 Enter LCO 3.0.3. Immediately power distribution subsystems inoperable that result in a loss of function.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct breaker alignments and voltage to 7 days required AC and DC electrical power distribution subsystems.

Monticello 3.8.7-2 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 irradiated fuel assemblies in the secondary containment.

ACTIONS

.- .....--------- ..-.-.-------.-------------- NOTE.

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC or DC electrical supported required power distribution - feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

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

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

AND Monticello 3.8.8-1 Amendment No. 146

Distribution Systems - Shutdown 3.8.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.4 Initiate actions to restore Immediately required AC and DC electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling subsystem(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage to 7 days required AC and DC electrical power distribution subsystems.

Monticello 3.8.8-2 Amendment No. 146

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks associated with the reactor mode switch refuel position shall be OPERABLE.

.APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks when the reactor mode switch is in the refuel position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with equipment interlocks inoperable, associated with the inoperable interlock(s).

OR A.2.1 Insert a control rod Immediately withdrawal block.

AND A.2.2 Verify all control rods are Immediately fully inserted.

Monticello 3.9.1-1 Amendment No. 146

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY i

SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of 7 days the following required refueling equipment interlock inputs:

a. All-rods-in;

b. Refuel platform position;

c. Refuel platform fuel grapple, fuel loaded;

d. Refuel platform fuel grapple fully retracted position;

e. Refuel platform frame mounted hoist, fuel loaded;

f. Refuel platform monorail mounted hoist, fuel loaded; and

g. Service platform hoist, fuel loaded.

Monticello 3.9.1-2 Amendment No. 146

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 The refuel position one-rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position one-rod- A.1 Suspend control rod Immediately out interlock inoperable, withdrawal.

AND A.2 Initiate action to fully insert Immediately all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel position. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.2.2 ----- ------- NOTE------------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. 7 days Monticello 3.9.2-1 Amendment No. 146

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control A.1 Suspend loading fuel Immediately rods not fully inserted, assemblies into the core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Monticello 3.9.3-1 Amendment No. 146

Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 The control rod "full-in" position indication channel for each control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS

--------------- NOTE-Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control rod A.1.1 Suspend in vessel fuel Immediately position indication movement.

channels inoperable.

AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to fully insert Immediately all insertable control rods in core cells containing one or more fuel assemblies.

OR A.2.1 Initiate action to fully insert Immediately the control rod associated with the inoperable position indicator.

AND Monticello 3.9.4-1 Amendment No. 146

Control Rod Position Indication 3.9.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.2.2 Initiate action to disarm the Immediately control rod drive associated with the fully inserted control rod.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the channel has no "full-in" indication on each Each time the control rod that is not "full-in." control rod is withdrawn from the "full-in" position Monticello 3.9.4-2 Amendment No. 146

Control Rod OPERABILITY - Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY - Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to fully insert Immediately control rods inoperable, inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 ----------------------- NOTE-- -----------

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least one notch. 7 days SR 3.9.5.2 Verify each withdrawn control rod scram 7 days accumulator pressure is 2! 940 psig.

Monticello 3.9.5-1 Amendment No. 146

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be 2!21 ft 11 inches above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not A.1 Suspend movement of fuel Immediately within limit, assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is 2t 21 ft 11 inches above the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months top of the RPV flange.

Monticello 3.9.6-1 Amendment No. 146

RHR - High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR) - High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

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

The required RHR shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level > 21 ft 11 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A, Required RHR shutdown A.1 Verify an alternate method 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem of decay heat removal is inoperable. available. AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Suspend loading irradiated Immediately associated Completion fuel assemblies into the Time of Condition A not RPV.

met.

AND B.2 Initiate action to restore Immediately secondary containment to OPERABLE status.

AND Monticello 3.9.7-1 Amendment No. 146

RHR - High Water Level 3.9.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.3 Initiate action to restore one Immediately standby gas treatment subsystem to OPERABLE status.

AND B.4 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

C. No RHR shutdown C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery cooling subsystem in circulation by an alternate of no reactor coolant operation. method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE. FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating.

Monticello 3.9.7-2 Amendment No. 146

RHR - Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR) - Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.

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

The required operating shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 21 ft 11 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------- NOTE ------..----- A.1 Verify an alternate method 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Separate Condition entry of decay heat removal is is allowed for each available for the inoperable AND required RHR shutdown required RHR shutdown cooling subsystem. cooling subsystem. Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter One or two required RHR shutdown cooling subsystems inoperable.

B. Required Action and B.1 Initiate action to restore Immediately associated Completion secondary containment to Time of Condition A not OPERABLE status.

met.

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

AND Monticello 3.9.8-1 Amendment No. 146

RHR - Low Water Level 3.9.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.3 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

C. No RHR shutdown C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery cooling subsystem in circulation by an alternate of no reactor coolant operation. method. circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY, SR 3.9.8.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating.

Monticello 3.9.8-2 Amendment No. 146

Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3-10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to "NA," and operation considered not to be in MODE 3; and the requirements of LCO 3.4.8, "Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown," may be suspended, to allow performance of an inservice leak or hydrostatic test provided the specific activity of the reactor coolant is < 0.02 pCi/gm DOSE EQUIVALENT 1-131 and the following MODE 3 LCOs are met:

a. LCO 3.3.6.2, "Secondary Containment Isolation Instrumentation,"

Functions 1, 3, and 4 of Table 3.3.6.2-1;

b. LCO 3.6.4.1, "Secondary Containment";

c. LCO 3.6.4.2, "Secondary Containment Isolation Valves (SCIVs)";

and

d. LCO 3.6.4.3, "Standby Gas Treatment (SGT) System."

APPLICABILITY: MODE 4 with average reactor coolant temperature > 212 0 F.

Monticello 3.10.1-1 Amendment No. 146

Inservice Leak and Hydrostatic Testing Operation 3.10.1 ACTIONS NOTE -----------------------------------

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the LCO A1 ----- NOTE --------------

requirements not met. Required Actions to be in MODE 4 include reducing average reactor coolant temperature to < 212 0 F.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Suspend activities that Immediately could increase the average reactor coolant temperature or pressure.

AND A.2.2 Reduce average reactor 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coolant temperature to

< 212 0 F.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.1.1 Perform the applicable SRs for the required According to the MODE 3 LCOs. applicable SRs Monticello 3.10.1-2 Amendment No. 146

Inservice Leak and Hydrostatic Testing Operation 3.10.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.1.2 Verify reactor coolant DOSE EQUIVALENT 1-131 Once within 0.02 pCi/gm.

specific activity is _< 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to increasing average reactor coolant temperature

> 212oF Monticello 3.10.1-3 Amendment No. 146

Reactor Mode Switch Interlock Testing 3.10.2 3.10 SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testing LCO 3.10.2 The reactor mode switch position specified in Table 1.1-1 for MODES 3, 4, and 5 may be changed to include the run, startup/hot standby, and refuel position, and operation considered not to be in MODE 1 or 2, to allow testing of instrumentation associated with the reactor mode switch interlock functions, provided:

a. All control rods remain fully inserted in core cells containing one or more fuel assemblies; and

b. No CORE ALTERATIONS are in progress.

APPLICABILITY: MODES 3 and 4 with the reactor mode switch in the run, startup/hot standby, or refuel position, MODE 5 with the reactor mode switch in the run or startup/hot standby position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Suspend CORE Immediately LCO not met. ALTERATIONS except for control rod insertion.

AND A.2 Fully insert all insertable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rods in core cells containing one or more fuel assemblies.

AND A-3.1 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

OR Monticello 3.10.2-1 Amendment No. 146

Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3.2 ---------- NOTE---

Only applicable in MODE 5.

Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the refuel position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted in core cells 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containing one or more fuel assemblies.

SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Monticello 3.10.2-2 Amendment No. 146

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 3.10 SPECIAL OPERATIONS 3.10.3 Single Control Rod Withdrawal - Hot Shutdown LCO 3.10.3 The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, provided the following requirements are met:

a. LCO 3.9.2, "Refuel Position One-Rod-Out Interlock";

b. LCO 3.9.4, "Control Rod Position Indication";

c. All other control rods are fully inserted; and d.1. LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"

MODE 5 requirements for Functions 1.a, 1,b, 7.a, 7.b, 10, and 11 of Table 3.3.1.1-1 and LCO 3.9.5, "Control Rod OPERABILITY -

Refueling,"

OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 3 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY: MODE 3 with the reactor mode switch in the refuel position.

Monticello 3.10.3-1 Amendment No. 146

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 ACTIONS

...-.-..--.-.-.-....------ --------- .-NC-) r ------------------------------------------------------------

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the LCO A.1 ---- -----------

NOTES-------

requirements not met. 1. Required Actions to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to fully insert Immediately all insertable control rods.

AND A.2.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required LCOs. According to the applicable SRs Monticello 3.10.3-2 Amendment No. 146

Single Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.3.2 ---------------------- NOTE-- -----

Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.

Verify all control rods, other than the control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed.

SR 3.10.3.3 Verify all control rods, other than the control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months being withdrawn, are fully inserted.

Monticello 3.10.3-3 Amendment No. 146

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Single Control Rod Withdrawal - Cold Shutdown LCO 3.10.4 The reactor mode switch position specified in Table 1.1-1 for MODE 4 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod, and subsequent removal of the associated control rod drive (CRD) if desired, provided the following requirements are met:

a. All other control rods are fully inserted; b.1. LCO 3.9.2, "Refuel Position One-Rod-Out Interlock," and LCO 3.9.4, "Control Rod Position Indication,"

OR

2. A control rod withdrawal block is inserted; and c.1. LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation,"

MODE 5 requirements for Functions 1.a, 1.b, 7.a, 7.b, 10, and 11 of Table 3.3.1.1-1, LCO 3.3.8.2, "Reactor Protection System (RPS)

Electric Power Monitoring," MODE 5 requirements, and LCO 3.9.5, "Control Rod OPERABILITY - Refueling,"

OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 4 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod.

APPLICABILITY: MODE 4 with the reactor mode switch in the refuel position.

Monticello 3.10.4-1 Amendment No. 146

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS

NO r -- - ----- - - - --------------------------------- - -----

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the LCO A.1 ----------- NOTES-----

requirements not met 1. Required Actions to fully with the affected control insert all insertable rod insertable. control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to fully insert Immediately all insertable control rods.

AND A.2.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

B. One or more of the LCO B.1 Suspend withdrawal of the Immediately requirements not met control rod and removal of with the affected control associated CRD.

rod not insertable.

AND B.2.1 Initiate action to fully insert Immediately all control rods.

OR Monticello 3.10.4-2 Amendment No. 146

Single Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B.2.2 Initiate action to satisfy the Immediately requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required LCOs. According to the applicable SRs SR 3.10.4.2 ---------------------- NOTE ----------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months being withdrawn, in a five by five array centered on.

the control rod being withdrawn, are disarmed.

SR 3.10.4.3 Verify all control rods, other than the control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months being withdrawn, are fully inserted.

SR 3.10.4.4 ---------------------- NOTE ----------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is inserted. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Monticello 3.10.4-3 Amendment No. 146

Single CRD Removal - Refueling 3.10.5 3.10 SPECIAL OPERATIONS 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling LCO 3.10.5 The requirements of:

LCO 3.3.1.1, "Reactor Protection System (RPS) Instrumentation";

LCO 3.3.8.2, "Reactor Protection System (RPS) Electric Power Monitoring";

LCO 3.9.1, "Refueling Equipment Interlocks";

LCO 3.9.2, "Refuel Position One-Rod-Out Interlock";

LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY - Refueling";

may be suspended in MODE 5 to allow the removal of a single CRD associated with a control rod withdrawn from a core cell containing one or more fuel assemblies, provided the following requirements are met:

a. All other control rods are fully inserted;

b. All other control rods in a five by five array centered on the withdrawn control rod are disarmed;

c. A control rod withdrawal block is inserted and LCO 3.1.1, "SHUTDOWN MARGIN (SDM)," MODE 5 requirements may be changed to allow the single control rod withdrawn to be assumed to be the highest worth control rod; and

d. No other CORE ALTERATIONS are in progress.

APPLICABILITY: MODE 5 with LCO 3.9.5 not met.

Monticello 3.10.5-1 Amendment No. 146

Single CRD Removal - Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.i Suspend removal of the Immediately LCO not met. CRD mechanism.

AND A.2.1 Initiate action to fully insert Immediately all control rods.

OR A.2.2 Initiate action to satisfy the Immediately requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months withdrawn for the removal of the associated CRD, are fully inserted.

SR 3.10.5.2 Verify all control rods, other than the control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months withdrawn for the removal of the associated CRD, in a five by five array centered on the control rod withdrawn for the removal of the associated CRD, are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is inserted. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 SR 3.10.5.5 Verify no other CORE ALTERATIONS are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months progress.

Monticello 3.10.5-2 Amendment No. 146

Multiple Control Rod Withdrawal - Refueling 3.10.6 3.10 SPECIAL OPERATIONS 3.10.6 Multiple Control Rod Withdrawal - Refueling LCO 3.10.6 The requirements of:

LCO 3.9.3, "Control Rod Position";

LCO 3.9.4, "Control Rod Position Indication"; and LCO 3.9.5, "Control Rod OPERABILITY - Refueling";

may be suspended, and the "full-in" position indicators may be bypassed for any number of control rods in MODE 5, to allow withdrawal of these control rods, removal of associated control rod drives (CRDs), or both, provided the following requirements are met:

a. The four fuel assemblies are removed from the core cells associated with each control rod or CRD to be removed;

b. All other control rods in core cells containing one or more fuel assemblies are fully inserted; and

c. Fuel assemblies shall only be loaded in compliance with an approved reload sequence.

APPLICABILITY: MODE 5 with LCO 3.9.3, LCO 3.9.4, or LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Suspend withdrawal of Immediately LCO not met. control rods and removal of associated CRDs.

AND A.2 Suspend loading fuel Immediately assemblies.

AND Monticello 3.10.6-1 Amendment No. 146

Multiple Control Rod Withdrawal - Refueling 3.10.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME A.3.1 Initiate action to fully insert Immediately all control rods in core cells containing one or more fuel assemblies.

OR A.3.2 Initiate action to satisfy the Immediately requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed from 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months core cells associated with each control rod or CRD removed.

SR 3.10.6.2 Verify all other control rods in core cells containing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months one or more fuel assemblies are fully inserted.

SR 3.10.6.3- ------------------ NOTE ----------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months compliance with an approved reload sequence.

Monticello 3.10.6-2 Amendment No. 146

Control Rod Testing - Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing - Operating LCO 3.10.7 The requirements of LCO 3.1.6, "Rod Pattern Control," may be suspended to allow performance of SDM demonstrations, control rod scram time testing, and control rod friction testing, provided:

a. The banked position withdrawal sequence requirements of SR 3.3.2.1.8 are changed to require the control rod sequence to conform to the specified test sequence; OR

b. The RWM is bypassed; the requirements of LCO 3.3.2.1, "Control Rod Block Instrumentation," Function 2 are suspended; and conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.

APPLICABILITY: MODES 1 and 2 with LCO 3.1.6 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1 Suspend performance of Immediately LCO not met. the test and exception to LCO 3.1.6.

Monticello 3.10.7-1 Amendment No. 146

Control Rod Testing - Operating 3.10.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.7.1 -----------------------

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

Not required to be met if SR 3.10.7.2 satisfied.

Verify movement of control rods is in compliance During control rod with the approved control rod sequence for the movement specified test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.7.2 ---------------------- NOTE ----------------

Not required to be met if SR 3.10.7.1 satisfied.

Verify control rod sequence input to the RWM is in Prior to control conformance with the approved control rod rod movement sequence for the specified test.

Monticello 3.10.7-2 Amendment No. 146

SDM Test - Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a. All Reactor Protection System (RPS) shorting links are removed; b.1. LCO 3.3.2.1, "Control Rod Block Instrumentation," MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the SDM test sequence, OR

2. Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff; c.. Each withdrawn control rod shall be coupled to the associated CRD;

d. All control rod withdrawals during out of sequence control rod moves shall be made in the single notch withdrawal mode;

e. No other CORE ALTERATIONS are in progress; and

f. CRD charging water header pressure __940 psig.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

Monticello 3.10.8-1 Amendment No. 146

SDM Test - Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.- -----..... NOTE -------------------- NOTE----------

Separate Condition entry Rod worth minimizer may be is allowed for each bypassed as allowed by control rod. LCO 3.3.2.1, "Control Rod Block

-..--------------.... Instrumentation," if required, to allow insertion of inoperable control One or more control rod and continued operation.

rods not coupled to its associated CRD.

A.1 Fully insert inoperable 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months control rod.

AND A.2 Disarm the associated 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CRD.

B. Requirements of the B.1 Place the reactor mode Immediately LCO not met for reasons switch in the shutdown or other than Condition A. refuel position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Verify all RPS shorting links are removed. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.10.8.2 ---------------------- NOTE ----------------------------.

Not required to be met if SR 3.10.8.3 satisfied.

Perform the MODE 2 applicable SRs for According to the LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1. applicable SRs Monticello 3.10.8-2 Amendment No. 146

SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.3------------------------- NOTE ------------------------------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in compliance During control rod with the approved control rod sequence for the SDM movement test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months progress.

SR 3.10.8.5 Verify each withdrawn control rod does not go to the Each time the withdrawn overtravel position. control rod is withdrawn to "full out" position AND Prior to satisfying LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling SR 3.10.8.6 Verify CRD charging water header pressure 7 days

> 940 p3sig.

Monticello 3.10.8-3 Amendment No. 146

Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site Location 4.1.1 Site and Exclusion Area Boundaries The site area and exclusion area boundaries are as shown in Chapter 15, Figure ND-95208 of the USAR.

4.1.2 Low Population Zone The low population zone is all the land within a 1 mile radius circle as shown in Chapter 15, Figure ND-95208 of the USAR.

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 484 fuel assemblies. Each assembly shall consist of a matrix of Zircalloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (U0 2 ) as fuel material and waterrods. Some fuel rods may consist of a Zircalloy base and a zirconium inner liner. Fuel assemblies shall be limited to those fuel designs that have been analyzed with NRC staff approved codes and methods and have been shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions:

4.2.2 Control Rod Assemblies The reactor core shall contain 121 cruciform shaped control rod assemblies. The control material shall be boron carbide or hafnium metal as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum k-infinity of 1.33 in the normal reactor core configuration at cold conditions;

b. ke, < 0.95 for high density fuel racks if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 10.2.1 of the USAR; 4.0-1 Amendment No. 146 Monticello Monticello 4.0-1 Amendment No. 146

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued)

c. keff < 0.90 for original fuel rack if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 10.2.1 of the USAR; and

d. A nominal 6.563 inch center to center distance between fuel assemblies placed in the high density storage racks, a 6.625 inch center to center distance between fuel assemblies placed in the original storage rack, and a two inch gap between the high density racks and the original rack.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum k-infinity of 1.31 in the normal reactor core configuration at cold conditions;

b. keff < 0.90 if dry; C. keff < 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 10.2.1 of the USAR;

d. keff < 0.98 under optimum moderator conditions, which includes an allowance for uncertainties as described in Section 10.2.1 of the USAR; and

e. A minimum 6.5 inch center to center distance between fuel assemblies placed in storage racks within a row and a minimum 10 inch center to center distance between fuel assemblies placed in storage racks between rows.

4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 1003 ft 7.25 inches.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 2237 fuel assemblies.

Monticello 4.0-2 Amendment No. 146

Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The plant manager shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The plant manager or his designee shall approve, prior to implementation, each proposed test, experiment, or modification to systems or equipment that affects nuclear safety.

5.1.2 The shift supervisor shall be responsible for the control room command function.

During any absence of the shift supervisor from the control room complex while the unit is in MODE 1, 2, or 3, an individual with an active Senior Operator license shall be designated to assume the control room command function.

During any absence of the shift supervisor from the control room complex while the unit is in MODE 4 or 5, an individual with an active Senior Operator license or Operator license shall be designated to assume the control room command function.

Monticello . 5.1-1 Amendment No. 146

Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements including the plant-specific titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications shall be documented in the USAR or Quality Assurance Topical Report.

b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. A specified corporate officer shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a. A non-licensed operator shall be assigned to each reactor containing fuel and an additional non-licensed operator shall be assigned for each control room from which a reactor is operating in MODES 1, 2, or 3.

b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months in order to accommodate unexpected absence of on-*duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements.

5.2-1 Amendment No. 146 Monticello Monticello 5.2-1 Amendment No. 146

Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

c. A radiation protection technician shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. Administrative procedures shall be developed and implemented to limit the working hours of personnel who perform safety related functions (e.g.,

licensed Senior Operators, licensed Operators, health physicists, non-licensed operators, and key maintenance personnel).

The controls shall include guidelines on working hours that ensure adequate shift coverage shall be maintained without routine heavy use of overtime.

Any deviation from the above guidelines shall be authorized in advance by the plant manager or the plant manager's designee, in accordahce with approved administrative procedures, and with documentation of the basis for granting the deviation. Routine deviation from the working hour guidelines shall not be authorized.

Controls shall be included in the procedures to require a periodic independent review be conducted to ensure that excessive hours have not been assigned.

e. The operations manager shall hold a Senior Operator license or shall formerly have held a Senior Operator license. If the operations manager does not hold a Senior Operator license, another member of plant management shall hold a Senior Operator license and shall be assigned to the plant operations group on a long term basis (approximately 2 years).

This individual shall not be assigned to a rotating shift.

f. An individual shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

Monticello 5.2-2 Amendment No. 146

Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications 5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the radiation protection manager. The radiation protection manager shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. In addition, the operations manager shall be qualified as required by Specification 5.2.2.e.

5.3.2 For the purpose of 10 CFR 55.4, a licensed Senior Operator and a licensed Operator are those individuals who, in addition to meeting the requirements of Specification 5.3.1, perform the functions described in 10 CFR 50.54(m).

Monticello 5.3-1 Amendment No. 146

Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures 5.4.1 Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in Generic Letter 82-33;

c. Quality assurance for effluent and environmental monitoring;

d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.5.

Monticello 5.4-1 Amendment No. 146

Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.

5.5.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the radiological environmental monitoring program; and

b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release Reports required by Specification 5.6.1 and Specification 5.6.2.

c. Licensee initiated changes to the ODCM:

1. Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

a) Sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s);

and b) A determination that the change(s) maintain the levels of radioactive effluent control required by 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

2. Shall become effective after the approval of the plant manager; and

3. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5-1 Amendment No. 146 Monticello 5.5-1 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include Core Spray, High Pressure Coolant Injection, Residual Heat Removal, Reactor Core Isolation Cooling, process sampling, and Standby Gas Treatment. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at least once per 24 months.

The provisions of SR 3.0.2 are applicable.

5.5.3 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to ten times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2402;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days.

Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the ODCM at least every .31 days; Monticello 5.5-2 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.3 Radioactive Effluent Controls Program (continued)

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I;

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents from the site to areas at or beyond the site boundary shall be in accordance with the following:

1. For noble gases: a dose rate _ 500 mrem/yr to the whole body and a dose rate _< 3000 mrem/yr to the skin; and

2. For iodine-131, iodine-1 33, tritium, and all radionuclides in particulate form with half-lives greater than 8 days: a dose rate _*1500 mrem/yr to any organ;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

j. Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190; and

k. Limitations on venting and purging of the primary containment through the Standby Gas Treatment System to maintain releases as low as reasonably achievable.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.

5.5.4 Component Cyclic or Transient Limit This program provides controls to track the USAR Table 4.2-1, cyclic and transient occurrences to ensure that components are maintained within the design limits.

5.5-3 Amendment No. 146 Monticello 5.5-3 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.5 Inservice Testina Proaram This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 pumps and valves.

a. Testing Frequencies specified in the ASME Operation and Maintenance (OM) Code and applicable Addenda as follows:

ASME OM Code and applicable Required Frequencies for Addenda terminology for performing inservice testing inservice testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Biquarterly At least once per 46 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly, every 12 months, or At least once per 366 days annually Biennially, every 24 months, or At least once per 731 days every 2 years Every 48 months At least once per 1461 days Every 5 years At least once per 1827 days Every 8 years At least once per 2922 days Every 10 years At least once per 3653 days

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities.

c. The provisions of SR 3.0.3 are applicable to inservice testing activities.

d. Nothing in the ASME OM Code shall be construed to supersede the requirements of any TS.

5.5.6 Ventilation Filter Testinq Pro-gram (VFTP)

A program shall establish the required testing of Engineered Safety Feature (ESF) filter ventilation systems. Tests described in Specifications 5.5.6.a and 5.5.6.b shall be performed once per 24 months and following painting, fire, or chemical release in any ventilation zone communicating with the subsystem while it is in operation that could adversely affect the high efficiency particulate air (HEPA) filters or charcoal adsorber capability.

Monticello 5.5-4 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Ventilation Filter Testing Program (VFTP) (continued)

The test described in Specification 5.5.6.a shall be performed after any maintenance or testing that could affect the leak tight integrity of the HEPA filters.

The test described in Specification 5.5.6.b shall be performed after any maintenance or testing that could affect the leak tight integrity of the charcoal adsorber banks.

Tests described in Specification 5.5.6.c shall be performed once per 24 months; at least once per 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of system operation; following painting, fire, or chemical release in any ventilation zone communicating with the subsystem while it is in operation that could adversely affect the charcoal adsorber capability.

The tests described in Specification 5.5.6.d shall be performed once per 92 days for the Standby Gas Treatment (SGT) System and once per 24 months for the Control Room Emergency Filtration (CREF) System.

The test described in Specification 5.5.6.e shall be performed once per 24 months.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

a. Demonstrate for each of the ESF systems that an inplace test of the HEPA filters shows a penetration and system bypass specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1989 at the system flowrate specified below.

ESF Ventilation System Penetration (%) Flowrate (cfm)

SGT System < 1.0 > 3,150 and <_3,850 CREF System < 1.0 for each individual Ž900 and < 1,100 HEPA filter and < 0.05 for each pair of HEPA filters 5.5-5 Amendment No. 146 Monticello 5.5-5 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Ventilation Filter Testing Program (VFTP) (continued)

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1989 at the system flowrate specified below.

ESF Ventilation System Penetration (%M Flowrate (cfm)

SGT System

1.0 2!3,150 and* 3,850 CREF System _<1.0 for each individual >_900 and

1,100 charcoal adsorber section and < 0.05 for each pair of charcoal adsorber sections

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration specified below when tested in accordance with ASTM D3803-1989 at a temperature of 300C (86 0 F) and the relative humidity specified below.

E.:SF Ventilation System Penetration (%) RH M%

SGT System _<5.0 95 CREF System < 0.5 95

d. Demonstrate for each of the ESF systems that the pressure drop across the combined filters is as specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1989 at the system flowrate specified below.

ESF Ventilation Delta P (inches water System gauge) Flowrate (cfm)

- SGT System <6 Ž3,150 and <_3,850 CREF System *8 Ž>900 and *1,100 Monticello 5.5-6 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Ventilation Filter Testing Program (VFTP) (continued)

e. Demonstrate that the heaters for each of the ESF systems dissipate the value specified below when tested in accordance with ANSI N510-1989.

ESF Ventilation System Nominal Watta-ge (kW)

SGT System >18 CREF System _4.5 and < 5.5 5.5.7 Explosive Gas and Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Offgas Treatment System, the quantity of radioactivity contained in gas storage tanks or fed into the Offgas Treatment System, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. The quantity of radioactivity after 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months holdup contained in each gas storage tank shall be

< 22,000 Ci of noble gases (considered as dose equivalent Xe-133). The quantity of liquid radioactive waste contained in each unprotected outdoor liquid storage tank shall be < 10 Ci, excluding tritium and dissolved or entrained noble gases.

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Offgas Treatment System and a Surveillance program to ensure the limits are maintained. Such limits shall be appropriate to the system's design criteria (i.e., whether or not the system is designed to withstand a hydrogen explosion);

b. A Surveillance program to ensure that the quantity of radioactivity contained in each gas storage tank and fed into the Offgas Treatment System is less than the amount that would result in a whole body exposure of _ 0.5 rem. to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and

c. A Surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the Liquid Radwaste Treatment System is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks' contents.

Monticello 5.5-7 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.7 Explosive Gas and Storage Tank Radioactivity Monitoring Program (continued)

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program Surveillance Frequencies.

5.5.8 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to the storage tank by determining that the fuel oil has:

1. An API gravity within limit;

2. A flash point and saybolt viscosity within limits; and

3. A water and sediment content within limits;

b. Within 31 days following addition of the new fuel oil to the storage tank, verify that the properties of the new fuel oil, other than those addressed in Specification 5.5.8.a above, are within limits; and

c. Total particulate concentration of the fuel oil is < 10 mg/l when tested every 31 days.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test Frequencies.

5.5.9 Technical Specifications (TS) Bases Control Program This program provides a means for processing changes to the Bases of these Technical Specifications.

a. Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:

1. A change in the TS incorporated in the license; or

2. A change to the USAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.

5.5-8 Amendment No. 146 Monticello Monticello 5.5-8 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Technical Specifications (TS) Bases Control Program (continued)

c. The TS Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the USAR.

d. Proposed changes that meet the criteria of Specification 5.5.9.b above shall be reviewed and approved by the NRC prior to implementation. Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e).

5.5.10 Safety Function Determination Program (SFDP)

This program ensures loss of safety function is detected and appropriate actions taken. Upon entry into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate actions may be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.

a. The SFDP shall contain the following:

1. Provisions for cross train checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

2. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

3. Provisions to ensure that an inoperable supported system's Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

4. Other appropriate limitations and remedial or compensatory actions.

b. A loss of safety function exists when, assuming no concurrent single failure, no concurrent loss of offsite power, or no concurrent loss of onsite emergency'diesel generator(s), a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

1. A required system redundant to the system(s) supported by the inoperable support system is also inoperable;

2. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or 5.5-9 Amendment No. 146 Monticello

.Monticello 5.5-9 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.10 Safety Function Determination Program (SFDP) (continued)

3. A required system redundant to the support system(s) for the supported systems described in Specifications 5.5.10.b.1 and 5.5.10.b.2 above is also inoperable.

c. The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered. When a loss of safety function is caused by the inoperability of a single Technical Specification support system, the appropriate Conditions and Required Actions to enter are those of the support system.

5.5.11 Primary Containment Leakage Rate Testing Program

a. A program shall establish the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program," dated September, 1995, as modified by the following exception:

1. The Type A testing Frequency specified in NEI 94-01, Revision 0, Paragraph 9.2.3, as "at least once per 10 years based on acceptable performance history" is modified to be "at least once per 15 years based on acceptable performance history." This change applies only to the interval following the Type A test performed in March 1993.

b. The calculated peak containment internal pressure for the design basis loss of coolant accident, Pa, is 42 psig. The containment design pressure is 56 psig.

c. The maximum allowable containment leakage rate, La, at Pa, shall be 1.2%

of containment air weight per day.

d. Leakage rate acceptance criteria are:

1. Containment leakage rate acceptance criterion is < 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and C tests and < 0.75 La for Type A tests.

Monticello 5.5-10 Amendment No. 146

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Primary Containment Leakage Rate Testing Program (continued)

2. Air lock testing acceptance criteria are:

a) Overall air lock leakage rate is < 0.05 L, when tested at _ Pa.

b) For each door, leakage rate is _ 0.007 La when pressurized to

> 10 psig.

e. The resilient seals of each 18 inch primary containment purge and vent valve shall be replaced at least once every 9 years. The provisions of SR 3.0.2 are applicable to this requirement. If a common mode failure attributable to the resilient seals is identified based on the results of SR 3.6.1.3.11, the resilient seals of all 18 inch primary containment purge and vent valves shall be replaced.

f. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.12 Battery Monitoring and Maintenance Program This Program provides for battery restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," or of the battery manufacturer of the following:

a. Actions to restore battery cells with float voltage < 2.13 V; and

b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.

Monticello 5.5-11 Amendment No. 146

Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Annual Radiological Environmental Operating Report The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.2 Radiological Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 15 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR Part 50, Appendix I, Section IV.B.1.

5.6.3 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

1. The APLHGR for Specification 3.2.1;

2. The MCPR for Specification 3.2.2;

3. The LHGR for Specification 3.2.3; Monticello 5.6-1 Amendment No. 146

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.3 CORE OPERATING LIMITS REPORT (COLR) (continued)

4. Control Rod Block Instrumentation Allowable Value for the Table 3.3.2.1-1 Rod Block Monitor Functions 1.a, 1.b, and 1.c and associated Applicability RTP levels; and

5. The Normal Region, the Stability Exclusion Region, and the Stability Buffer Region of the power to flow map, and the power distribution controls for Specification 3.4.1.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

1. NEDE-2401 1-P-A, "General Electric Standard Application for Reactor Fuel";

2. NSPNAD-8608-A, "Reload Safety Evaluation Methods for Application to the Monticello Nuclear Generating Plant";

3. NSPNAD-8609-A, "Qualification of Reactor Physics Methods for Application to Monticello"; and

4. NEDO-31960, "BWR Owners' Group Long-Term Stability Solutions Licensing Methodology."

The COLR will contain the complete identification for each of the Technical Specification referenced topical reports used to prepare the COLR (i.e.,

report number, title, revision, date, and any supplements).

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.4 Post Accident Monitoring Report When a report is required by Condition B or F of LCO 3.3.3.1, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

Monticello 5.6-2 Amendment No. 146

High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area As provided in paragraph 20.1601(c) of 10 CFR Part 20, the following controls shall be applied to high radiation areas in place of the controls required by paragraph 20.1601 (a) and (b) of 10 CFR Part 20:

5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be barricaded and conspicuously posted as a high radiation area. Such barricades may be opened as necessary to permit entry or exit of personnel or equipment.

b. Access to, and activities in, each such area shall be controlled by means of Radiation Work Permit (RWP) or equivalent that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiationprotection equipment and measures.

c. Individuals qualified in radiation protection procedures and personnel continuously escorted by such individuals may be exempted from the requirement for an RWP or equivalent while performing their assigned duties provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess one of the following:

1. A radiation monitoring device that continuously displays radiation dose rates in the area;

2. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint;

3. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area; or

4. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, Monticello 5.7-1 Amendment No. 146

High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 High Radiation Areas with Dose Rates Not Exceeding 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

(i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with individuals in the area who are covered by such surveillance.

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation

a. Each entryway to such an area shall be conspicuously posted as a high radiation area and shall be provided with a locked or continuously guarded door or gate that prevents unauthorized entry, and, in addition:.

1. All such door and gate keys shall be maintained under the administrative control of the shift supervisor, radiation protection manager, or his or her designee; and

2. Doors and gates shall remain locked except during periods of personnel or equipment entry or exit.

b. Access to, and activities in, each such area shall be controlled by means of an RWP or equivalent that includes specification of radiation does rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.

Monticello 5.7-2 Amendment No. 146

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 Hiqh Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

c. Individuals qualified in radiation protection procedures may be exempted from the requirement for an RWP or equivalent while performing radiation surveys in such areas provided that they are otherwise following plant radiation protection procedures for entry to, exit from, and work in such areas.

d. Each individual or group entering such an area shall possess one of the following:

1. A radiation monitoring device that continuously integrates the radiation dose rates in the area and alarms when the device's dose alarm setpoint is reached, with an appropriate alarm setpoint;

2. A radiation monitoring device that continuously transmits dose rate and cumulative dose information to a remote receiver monitored by radiation protection personnel responsible for controlling personnel radiation exposure within the area with the means to communicate with and control every individual in the area;

3. A self-reading dosimeter (e.g., pocket ionization chamber or electronic dosimeter) and, (i) Be under the surveillance, as specified in the RWP or equivalent, while in the area, of an individual qualified in radiation protection procedures, equipped with a radiation monitoring device that continuously displays radiation dose rates in the area; who is responsible for controlling personnel exposure within the area, or (ii) Be under the surveillance, as specified in the RWP or equivalent, while in the area, by means of closed circuit television, of personnel qualified in radiation protection procedures, responsible for controlling personnel radiation exposure in the area, and with the means to communicate with and control every individual in the area; or

4. In those cases where Specifications 5.7.2.d.2 and 5.7.2.d.3, above, are impractical or determined to be inconsistent with the "As Low As is Reasonably Achievable" principle, a radiation monitoring device that continuously displays radiation dose rates in the area.

5.7-3 Amendment No. 146 Monticello Monticello 5.7-3 Amendment No. 146

High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 High Radiation Areas with Dose Rates Greater than 1.0 rem/hour at 30 Centimeters from the Radiation Source or from any Surface Penetrated by the Radiation, but less than 500 rads/hour at 1 Meter from the Radiation Source or from any Surface Penetrated by the Radiation (continued)

e. Except for individuals qualified in radiation protection procedures, or personnel continuously escorted by such individuals, entry into such areas shall be made only after dose rates in the area have been determined and entry personnel are knowledgeable of them. These continuously escorted personnel will receive a pre-job briefing prior to entry into such areas. This dose rate determination, knowledge, and pre-job briefing does not require documentation prior to initial entry.

f. Such individual areas that are within a larger area where no enclosure exists for the purpose of locking and where no enclosure can reasonably be constructed around the individual area need not be controlled by a locked door or gate, nor continuously guarded, but shall be barricaded, conspicuously posted, and a clearly visible flashing light shall be activated at the area as a warning device.

Monticello 5.7-4 Amendment No. 146

LICE1NSE AUTHoRITY RILE G-OP~tj 00 ~

APPENDIX B TO FACILITY OPERATING LICENSE DPR-22 MONTICELLO NUCLEAR GENERATING PLANT UNIT 1 NORTHERN STATES POWER COMPANY DOCKET NO. 50-263 L

~L

.~ ~.f'j~

_-'k*' ..

I t-Date:

APPENDIX C ADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. DPR-22 Nuclear Management Company, LLC shall comply with the following conditions on the I schedules noted below:

Amendment Implementation Number Additional Condition DAtM 98 The emergency operating procedures (EOPs) shall Prior to starting be changed to require manual isolation of torus and up from the drywell sprays prior to the point where primary current containment pressure would not provide adequate maintenance net positive suction head (NPSH) for the emergency outage, or core cooling system (ECCS) pumps, change the August 1, 1997, caution statement regarding NPSH in the Primary whichever is Containment Pressure EOP to include the core spray later.

pumps, and add a caution statement regarding NPSH considerations for pressure control while venting to control primary containment pressure.

98 Finalize the additional containment analysis and Prior to starting associated NPSH evaluation which extends the up from the existing long-term cause evaluation to the time when current the required containment overpressure returns to maintenance atmospheric conditions. Changes to the requested outage, or long-term containment overpressure, if any, shall be August 1, 1997, promptly reported to the NRC prior to starting up the whichever is unit from the current maintenance outage. later.

results of the additional containment Within.90 days 98 analysisthe Submit and associated NPSH evaluation discussed from the date of above. the plant startup from the current maintenance outage, or November 1, 1997, whichever is later.

C-1 Amendment No. 98, 110

APPENDIX C---continued Amendment Implementation Number Additional Condition Date 98 Update Section 5.2 of the Updated Safety Within 90 days from the Analysis Report by incorporating Figure E.2 date of plant startup of the NSP submittal dated July 16, 1997. from the current maintenance outage, or November 1, 1997, whichever is later.

98 Process a 10 CFR 50.59 evaluation to Within 180 days from the change the EOP definition of adequate date of plant startup core cooling to 2/3 core height. The from the current corresponding EOP changes and the maintenance outage, or required operator training shall also be February 1, 1998, completed. Final implementations shall be whichever is later.

completed when all the 10 CFR 50.59 evaluation requirements are satisfied.

101 Conduct an independent evaluation of the Within 9 months of the testing methodology and the testing date of issuance of configuration of the EFT [emergency Amendment No. 1.01.

filtration testing] system by HEPA and charcoal filter testing experts. This evaluation shall include review of the exceptions to the ASME N510-1989 testing standard listed in Exhibit F of NSP's June 19, 1998, letter. The evaluation results shall be reported to the NRC.

101 Initiate appropriate modifications to the Within 24 months of the EFT system to comply with the ASME date of issuance of N510-1989 testing standard or obtain NRC Amendment No. 101.

approval for continued use of the exceptions.

102 All affected environmental qualification' Prior to implementation files, including service life and maintenance of Amendment No. 102 intervals if necessary, shall be revised to (prior to exceeding 1670 reflect the new environmental profile MWt).

changes associated with power uprate.

102 All affected process computer and SPDS Prior to implementation data points shall be changed to reflect of Amendment No. 102 uprate operating conditions. (prior to exceeding 1670 MWt).

. C-2 Amendment No. 102

APPENDIX C - continued Amendment Implementation Number Additional Condition Date 102 All affected process computer and SPDS data Prior to implementation points shall be changed to reflect uprate of Amendment No. 102 operating conditions (prior to exceeding 1670 MWt).

102 Control room simulator changes shall be Prior to implementation completed in accordance with ANSI/ANS of Amendment No. 102 3.5-1985 Section 5.4.1, Simulator Performance (prior to exceeding 1670 Testing, and Monticello simulator configuration MWt).

control procedures.

102 Classroom and simulator training on new Prior to implementation knowledge and abilities associated with the of Amendment No. 102 power uprate shall be provided in accordance (prior to exceeding 1670 with Monticello Training Center procedures. MWt).

102 NMC shall monitor plant operational parameters During and after the I for uprate impacts on the PRA models power uprate ascension test program.

102 Control room simulator changes shall be verified Within 3 months of against actual plant startup data. completion of the power uprate ascension test program.

102 The applicable training programs and the Within 6 months of simulator shall be modified, or appropriate completion of the power compensatory actions shall be taken, in uprate ascension test accordance with the Monticello Training program.

Center procedures to reflect issues and discrepancies identified during startup testing.

102 The MNGP USAR shall be updated to reflect Within 9 months of the changes associated with power uprate completion of the power operation. This update shall not include credit for uprate ascension test suppression pool scrubbing in the MSIV leakage program.

pathway in the revised LOCA analysis.

C-3 Amendment No. 4-02, 110

APPENDIX C - continued Amendment Implementation Number Additional Condition Date 102 NSP* shall evaluate whether MO-2034 and By the end of the next I MO-4229 are capable of allowing a subsequent scheduled refueling operation after the required isolation safety outage from the date of functions are completed. This evaluation may Amendment No. 102.

include an examination of assumptions and methodologies, additional administrative controls, and modifications. The evaluation shall be completed in order to institute the corrective actions, if any, by the end of the next scheduled refueling outage.

102 NSP* shall evaluate the capacity margins of By the end of the next I MO-2398 and MO-2034. This evaluation may scheduled refueling include an examination of assumptions and outage from the date of methodologies, additional administrative controls, Amendment No. 102.

and modifications. The evaluation shall be completed in order to institute the corrective actions.

Reference to NSP is maintained for historical purposes. I It C-4 Amendment No. 4-.02, 110

ML063070072

Text

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