ML17250A871: Difference between revisions
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1.2-1 1.3 Completion Times | 1.2-1 1.3 Completion Times | ||
................................................................................................ | ................................................................................................ | ||
1.3-1 1.4 Frequency | 1.3-1 1.4 Frequency ........................................................................................................... | ||
1.4-1 2.0 SAFETY LIMITS (SLs) | 1.4-1 2.0 SAFETY LIMITS (SLs) | ||
.............................................................................................. | .............................................................................................. | ||
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3.3.8.2-1 TABLE OF CONTENTS Page Number 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating | 3.3.8.2-1 TABLE OF CONTENTS Page Number 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating | ||
.................................................................... | .................................................................... | ||
3.4.1-1 3.4.2 Jet Pumps | 3.4.1-1 3.4.2 Jet Pumps ................................................................................................... | ||
3.4.2-1 3.4.3 Safety/Relief Valves (S/RVs) | 3.4.2-1 3.4.3 Safety/Relief Valves (S/RVs) | ||
...................................................................... | ...................................................................... | ||
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3.4.9-1 3.4.10 Reactor Steam Dome Pressure | 3.4.9-1 3.4.10 Reactor Steam Dome Pressure | ||
................................................................ | ................................................................ | ||
3.4.10-1 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating | 3.4.10-1 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating ....................................................................................... | ||
3.5.1-1 3.5.2 RPV Water Inventory ControlECCS - Shutdown ......................................... | 3.5.1-1 3.5.2 RPV Water Inventory ControlECCS - Shutdown ......................................... | ||
3.5.2-1 3.5.3 RCIC System | 3.5.2-1 3.5.3 RCIC System | ||
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3.7.7-1 3.7.8 Spent Fuel Storage Pool Water Level | 3.7.7-1 3.7.8 Spent Fuel Storage Pool Water Level | ||
......................................................... | ......................................................... | ||
3.7.8-1 Monticello iii Revision 0 TABLE OF CONTENTS Page Number 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating | 3.7.8-1 Monticello iii Revision 0 TABLE OF CONTENTS Page Number 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating .............................................................................. | ||
3.8.1-1 3.8.2 AC Sources - Shutdown .............................................................................. | 3.8.1-1 3.8.2 AC Sources - Shutdown .............................................................................. | ||
3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air | 3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air | ||
................................................... | ................................................... | ||
3.8.3-1 3.8.4 DC Sources - Operating | 3.8.3-1 3.8.4 DC Sources - Operating .............................................................................. | ||
3.8.4-1 3.8.5 DC Sources - Shutdown .............................................................................. | 3.8.4-1 3.8.5 DC Sources - Shutdown .............................................................................. | ||
3.8.5-1 3.8.6 Battery Parameters | 3.8.5-1 3.8.6 Battery Parameters | ||
..................................................................................... | ..................................................................................... | ||
3.8.6-1 3.8.7 Distribution Systems - Operating | 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 | 3.8.8-1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks | ||
................................................................... | ................................................................... | ||
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3.9.3-1 3.9.4 Control Rod Position Indication | 3.9.3-1 3.9.4 Control Rod Position Indication | ||
................................................................... | ................................................................... | ||
3.9.4-1 3.9.5 Control Rod OPERABILITY - Refueling | 3.9.4-1 3.9.5 Control Rod OPERABILITY - Refueling ...................................................... | ||
3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water Level | 3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water Level | ||
.............................................. | .............................................. | ||
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3.10.3-1 3.10.4 Single Control Rod Withdrawal - Cold Shutdown | 3.10.3-1 3.10.4 Single Control Rod Withdrawal - Cold Shutdown | ||
...................................... | ...................................... | ||
3.10.4-1 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling | 3.10.4-1 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ............................... | ||
3.10.5-1 3.10.6 Multiple Control Rod Withdrawal - Refueling ............................................. | |||
3.10.5-1 3.10.6 Multiple Control Rod Withdrawal - Refueling | 3.10.6-1 3.10.7 Control Rod Testing - Operating ............................................................... | ||
3.10.7-1 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling ........................................ | |||
3.10.6-1 3.10.7 Control Rod Testing - Operating | |||
3.10.7-1 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling | |||
3.10.8-1 4.0 DESIGN FEATURES | 3.10.8-1 4.0 DESIGN FEATURES | ||
................................................................................................. 4.0-1 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage | ................................................................................................. 4.0-1 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage | ||
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-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) | -131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) | ||
-11, "Limiting Values of Radionuclide Intake and Air Concentration Factors for Inhalation, Submersion and Ingestion," September 1988, and FGR | -11, "Limiting Values of Radionuclide Intake and Air Concentration Factors for Inhalation, Submersion and Ingestion," September 1988, and FGR | ||
-12, "External Exposure to Radionuclides in Air, Water and Soil," | -12, "External Exposure to Radionuclides in Air, Water and Soil," September 1993 | ||
September 1993 | . DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming: a) The water inventory above the TAF is divided by the limiting drain rate; b) The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single Definitions | ||
. DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming: | |||
a) The water inventory above the TAF is divided by the limiting drain rate; b) The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single Definitions | |||
===1.1 Monticello=== | ===1.1 Monticello=== | ||
1.1-3 Amendment No. | 1.1-3 Amendment No. | ||
146 148, XXX human error), for all penetration flow paths below the TAF except: | 146 148, XXX human error), for all penetration flow paths below the TAF except: | ||
: 1. Penetration flow path s connected to an intact closed system, or isolated by manual or automatic | : 1. Penetration flow path s connected to an intact closed system, or isolated by manual or automatic valve s that are locked, sealed, or otherwise secured in the closed position, blank flange s, or other device s that prevent flow of reactor coolant through the penetration flow paths; 2. Penetration flow path s capable of being isolated by valve s that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or | ||
: 3. Penetration flow path s with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power. | : 3. Penetration flow path s with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power. | ||
c) The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory; d) No additional draining events occur; and e) Realistic cross-sectional areas and drain rates are used. | c) The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory; d) No additional draining events occur; and e) Realistic cross-sectional areas and drain rates are used. | ||
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===1.1 Monticello=== | ===1.1 Monticello=== | ||
1.1-5 Amendment No. | 1.1-5 Amendment No. | ||
146, | 146, 1 72, 175 , 176, 179 1.1 Definitions OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s). | ||
PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with | PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with | ||
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===1.1 Monticello=== | ===1.1 Monticello=== | ||
1.1-6 Amendment No. | 1.1-6 Amendment No. | ||
14 6, 175 1.1 Definitions STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function. | |||
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. | THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant. | ||
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MODE | MODE | ||
TITLE REACTOR MODE SWITCH POSITION AVERAGE REACTOR COOLANT TEMPERATURE (F) 1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot Standby NA 3 Hot Shutdown(a) Shutdown > 212 4 Cold Shutdown(a) Shutdown 212 5 Refueling(b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned. | TITLE REACTOR MODE SWITCH POSITION AVERAGE REACTOR COOLANT TEMPERATURE | ||
( F) 1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot Standby NA 3 Hot Shutdown(a) Shutdown > 212 4 Cold Shutdown(a) Shutdown 212 5 Refueling(b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned. | |||
(b) One or more reactor vessel head closure bolts less than fully tensioned. | (b) One or more reactor vessel head closure bolts less than fully tensioned. | ||
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-1 Amendment No. | ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-1 Amendment No. | ||
146, | 146 , X XX 3.3 INSTRUMENTATION | ||
3.3.5.1 Emergency Core Cooling System (ECCS) 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. | LCO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE. | ||
APPLICABILITY: | APPLICABILITY: | ||
According to Table 3.3.5.1-1. | According to Table 3.3.5.1-1. | ||
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Separate Condition entry is allowed for each channel. | Separate Condition entry is allowed for each channel. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable. | ||
A.1 Enter the Condition referenced in Table 3.3.5.1-1 for the channel. Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. B.1 -------------- | A.1 Enter the Condition referenced in Table 3.3.5.1-1 for the channel. Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. B.1 --------------NOTE S------------- | ||
: 1. Only applicable in MODES 1, 2, and | : 1. Only applicable in MODES 1, 2, and 3. 2. Only applicable for Functions 1.a, 1.b, 2.a, 2.b, 2.f, 2.h, and 2.k. ------------------------------------- | ||
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable. | Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable. | ||
AND 1 hour from discovery of loss of initiation capability for feature(s) in both divisions | AND 1 hour from discovery of loss of initiation capability for feature(s) in both divisions ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-2 Amendment No. | ||
146 , X XX ACTIONS (continued) | |||
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-2 Amendment No. | CONDITION REQUIRED ACTION COMPLETION TIME B.2 ---------------NOTE-------------- | ||
146, | |||
CONDITION REQUIRED ACTION COMPLETION TIME B.2 ---------------NOTE-------------- | |||
Only applicable for Functions 3.a and 3.b. ------------------------------------- | Only applicable for Functions 3.a and 3.b. ------------------------------------- | ||
Declare High Pressure Coolant Injection (HPCI) System inoperable. | Declare High Pressure Coolant Injection (HPCI) System inoperable. | ||
| Line 362: | Line 346: | ||
1 hour from discovery of loss of HPCI initiation capability | 1 hour from discovery of loss of HPCI initiation capability | ||
24 hours C. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. C.1 -------------- | 24 hours C. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. C.1 --------------NOTE S------------- | ||
: 1. Only applicable in MODES 1, 2, and | : 1. Only applicable in MODES 1, 2, and 3. 2. Only applicable for Functions 1.c, 1.d, 1.e, 1.f, 2.c, 2.d, 2.e, 2.i, 2.j, 2.l, and 2.m. ------------------------------------- | ||
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable. | Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable. | ||
AND C.2 Restore channel to OPERABLE status. | AND C.2 Restore channel to OPERABLE status. | ||
1 hour from discovery of loss of initiation capability for feature(s) in both divisions 24 hours ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-3 Amendment No. | 1 hour from discovery of loss of initiation capability for feature(s) in both divisions 24 hours ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-3 Amendment No. | ||
146, | 146 , X XX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. D.1 ---------------NOTE-------------- | CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. D.1 ---------------NOTE-------------- | ||
Only applicable if HPCI pump suction is not aligned to the suppression pool. | Only applicable if HPCI pump suction is not aligned to the suppression pool. | ||
------------------------------------- | ------------------------------------- | ||
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1 hour from discovery of loss of HPCI initiation capability | 1 hour from discovery of loss of HPCI initiation capability | ||
24 hours 24 hours E. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. E.1 -------------- | 24 hours 24 hours E. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. E.1 --------------NOTE S------------- | ||
: 1. Only applicable in MODES 1, 2, and | : 1. Only applicable in MODES 1, 2, and 3. 2. Only applicable for Function 2.g. | ||
------------------------------------- | ------------------------------------- | ||
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable. | Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable. | ||
AND E.2 Restore channel to OPERABLE status. | AND E.2 Restore channel to OPERABLE status. | ||
1 hour from discovery of loss of initiation capability for subsystems in both divisions 7 days ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-4 Amendment No. | 1 hour from discovery of loss of initiation capability for subsystems in both divisions 7 days ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-4 Amendment No. | ||
146 CTIONS (continued) | 146 CTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. F.1 Declare Automatic Depressurization System (ADS) valves inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. F.1 Declare Automatic Depressurization System (ADS) valves inoperable. | ||
AND F.2 Place channel in trip. | AND F.2 Place channel in trip. | ||
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: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability. | : 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 3.c and 3.f; and (b) for up to 6 hours for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. | SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. | ||
12 hours SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST. | 12 hours 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 3.3.5.1.3 Calibrate the trip unit. | ||
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24 months SR 3.3.5.1.9 Perform CHANNEL FUNCTIONAL TEST. | 24 months SR 3.3.5.1.9 Perform CHANNEL FUNCTIONAL TEST. | ||
24 months ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-6 Amendment No. | 24 months ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-6 Amendment No. | ||
146, 151, 170 | 146, 151, 170 , 176, XXX Table 3.3.5.1-1 (page 1 of 6) Emergency Core Cooling System Instrumentation | ||
, 176, XXX Table 3.3.5.1-1 (page 1 of 6) Emergency Core Cooling System Instrumentation | |||
FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 | FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 | ||
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ALLOWABLE VALUE 1. Core Spray System | ALLOWABLE VALUE 1. Core Spray System | ||
: a. Reactor Vessel Water Level | : a. Reactor Vessel Water Level - Low Low 1, 2, 3 , 4(a), 5(a) 4 (ab) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Drywell Pressure - High 1, 2, 3 4 (ab) B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig c. Reactor Steam Dome Pressure - | ||
- Low Low 1, 2, 3, 4(a), 5(a) 4(ab) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 | Low (Injection Permissive) 1, 2, 3 2 C SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 397 psig and 440 psig 4(a), 5(a) 2 B SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d) SR 3.3.5.1.8 397 psig and 440 psig d. Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 1, 2, 3 4(a), 5 (a) 2 2 C B SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d) SR 3.3.5.1.8 397 psig 397 psig e. Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5 (a) 2 2 C B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes 18 minutes (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown." (ab) Also required to initiate the associated emergency diesel generator (EDG). | ||
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | |||
- | |||
Low (Injection Permissive) 1, 2, 3 2 C SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)( | |||
SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes 18 minutes (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, "ECCS | |||
- Shutdown." | |||
(bc) If the as | |||
-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | |||
(cd) The instrument channel setpoint shall be reset to a value that is within the as | (cd) The instrument channel setpoint shall be reset to a value that is within the as | ||
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as | -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 | ||
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SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System | SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System | ||
: f. Core Spray Pump Start - Time Delay Relay 1, 2, 3 4(a), 5(a) 1 per pump C SR 3.3.5.1.7 SR 3.3.5.1.8 15.86 seconds 2. Low Pressure Coolant Injection (LPCI) System | : f. Core Spray Pump Start - Time Delay Relay 1, 2, 3 4(a), 5(a) 1 per pump C SR 3.3.5.1.7 SR 3.3.5.1.8 15.86 seconds 2. Low Pressure Coolant Injection (LPCI) System | ||
: a. Reactor Vessel Water Level | : a. Reactor Vessel Water Level - Low Low 1, 2, 3, 4(a), 5(a) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Drywell Pressure - High 1, 2, 3 4 B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive) 1, 2, 3 2 C SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 397 psig and 440 psig 4(a), 5(a) 2 B SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d) SR 3.3.5.1.8 397 psig and 440 psig d. Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 1, 2, 3 2 C SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 397 psig 4(a), 5(a) 2 B SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d) SR 3.3.5.1.8 397 psig (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2. | ||
- Low Low 1, 2, 3, 4(a), 5(a) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 | (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | ||
- Low (Injection Permissive) 1, 2, 3 2 C SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)( | |||
(bc) If the as | |||
-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | |||
(cd) The instrument channel setpoint shall be reset to a value that is within the as | (cd) The instrument channel setpoint shall be reset to a value that is within the as | ||
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as | -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 | ||
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SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System | SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System | ||
: e. Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2 C B SR 3.3.5.1.7 SR 3.3.5.1.8 | : e. Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2 C B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes | ||
18 minutes f. Low Pressure Coolant Injection Pump Start - Time Delay Relay 1, 2, 3, 4(a), 5(a) 4 per pump B SR 3.3.5.1.7 SR 3.3.5.1.8 Pumps A, B 5.33 seconds Pumps C, D 10.59 seconds g. Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2, 3, 4(a), 5(a) 1 per pump E SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 360 gpm and 745 gpm h. Reactor Steam Dome Pressure - | |||
Low (Break Detection) 1, 2, 3 4 B SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 873.6 psig and 923.4 psig i. Recirculation Pump Differential Pressure | |||
18 minutes f. Low Pressure Coolant Injection Pump Start | - High (Break Detection) 1, 2, 3 4 per pump C SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 63.5 inches wc j. Recirculation Riser Differential Pressure - High (Break Detection) 1, 2, 3 4 C SR 3.3.5.1.2 SR 3.3.5.1.7 (bc)(cd) SR 3.3.5.1.8 100.0 inches wc (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2. | ||
- Time Delay Relay 1, 2, 3, 4(a), 5(a) 4 per pump B SR 3.3.5.1.7 SR 3.3.5.1.8 Pumps A, B 5.33 seconds Pumps C, D 10.59 seconds g. Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2, 3, 4(a), 5(a) 1 per pump E SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 360 gpm and 745 gpm h. Reactor Steam Dome Pressure | (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | ||
- | |||
Low (Break Detection) 1, 2, 3 4 B SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 873.6 psig and 923.4 psig i. Recirculation Pump Differential Pressure | |||
- High (Break Detection) 1, 2, 3 4 per pump C SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 63.5 inches wc j. Recirculation Riser Differential Pressure | |||
- High (Break Detection) 1, 2, 3 4 C SR 3.3.5.1.2 SR 3.3.5.1.7(bc)(cd) SR 3.3.5.1.8 100.0 inches wc (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2. | |||
(bc) If the as | |||
-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | |||
(cd) The instrument channel setpoint shall be reset to a value that is within the as | (cd) The instrument channel setpoint shall be reset to a value that is within the as | ||
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as | -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 | ||
| Line 484: | Line 445: | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System | SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System | ||
: k. Recirculation Steam Dome Pressure | : k. Recirculation Steam Dome Pressure - Time Delay Relay (Break Detection) 1, 2, 3 2 B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 2.97 seconds l. Recirculation Pump Differential Pressure - Time Delay Relay (Break Detection) 1, 2, 3 2 C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds m. Recirculation Riser Differential Pressure | ||
- Time Delay Relay (Break Detection) 1, 2, 3 2 B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 2.97 seconds l. Recirculation Pump Differential Pressure | |||
- Time Delay Relay (Break Detection) 1, 2, 3 2 C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds m. Recirculation Riser Differential Pressure | |||
- Time Delay Relay (Break Detection) 1, 2, 3 2 C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds 3. High Pressure Coolant Injection (HPCI) System | - Time Delay Relay (Break Detection) 1, 2, 3 2 C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds 3. High Pressure Coolant Injection (HPCI) System | ||
: a. Reactor Vessel Water Level | : a. Reactor Vessel Water Level - Low Low 1, 2 (de), 3 (de) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Drywell Pressure - High 1, 2 (de), 3 (de) 4 B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig c. Reactor Vessel Water Level - High 1, 2 (de), 3 (de) 2 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 48 inches d. Condensate Storage Tank Level | ||
- Low Low 1, 2(de), 3(de) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 | - Low 1, 2 (de), 3 (de) 2 D SR 3.3.5.1.7 SR 3.3.5.1.8 29.3 inches e. Suppression Pool Water Level - High 1, 2 (de), 3 (de) 2 D SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 3.0 inches f. High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2 (de), 3 (de) 1 E SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 362 gpm and 849 gpm (de) With reactor steam dome pressure > | ||
- High 1, 2(de), 3(de) 2 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 48 inches d. Condensate Storage Tank Level | |||
- Low 1, 2(de), 3(de) 2 D SR 3.3.5.1.7 SR 3.3.5.1.8 29.3 inches e. Suppression Pool Water Level | |||
- High 1, 2(de), 3(de) 2 D SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 3.0 inches f. High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2(de), 3(de) 1 E SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 362 gpm and 849 gpm (de) With reactor steam dome pressure > | |||
150 psig. | 150 psig. | ||
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-10 Amendment No. | ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-10 Amendment No. | ||
146, XXX Table 3.3.5.1-1 (page 5 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 | 146, XXX Table 3.3.5.1-1 (page 5 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4. Automatic Depressurization System (ADS) Trip System A a. Reactor Vessel Water Level | SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4. Automatic Depressurization System (ADS) Trip System A a. Reactor Vessel Water Level - Low Low 1, 2 (de), 3 (de) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Automatic Depressurization System Initiation Timer 1, 2 (de), 3 (de) 1 G SR 3.3.5.1.7 SR 3.3.5.1.8 120 seconds c. Core Spray Pump Discharge Pressure - High 1, 2 (de), 3 (de) 2 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 75 psig and 125 psig d. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2 (de), 3 (de) 4 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 75 psig and 125 psig 5. ADS Trip System B a. Reactor Vessel Water Level - Low Low 1, 2 (de), 3 (de) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Automatic Depressurization System Initiation Timer 1, 2 (de), 3 (de) 1 G SR 3.3.5.1.7 SR 3.3.5.1.8 120 seconds (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | ||
- Low Low 1, 2(de), 3(de) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 | |||
- High 1, 2(de), 3(de) 2 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)( | |||
- High 1, 2(de), 3(de) 4 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)( | |||
- Low Low 1, 2(de), 3(de) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 | |||
-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | |||
(cd) The instrument channel setpoint shall be reset to a value that is within the as | (cd) The instrument channel setpoint shall be reset to a value that is within the as | ||
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as | -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 | ||
| Line 516: | Line 463: | ||
146, XXX Table 3.3.5.1-1 (page 6 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 | 146, XXX Table 3.3.5.1-1 (page 6 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. ADS Trip System B c. Core Spray Pump Discharge Pressure | SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. ADS Trip System B c. Core Spray Pump Discharge Pressure - High 1, 2 (de), 3 (de) 2 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 75 psig and 125 psig d. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2 (de), 3 (de) 4 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 75 psig and 125 psig (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | ||
- High 1, 2(de), 3(de) 2 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)( | |||
- High 1, 2(de), 3(de) 4 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)( | |||
-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service. | |||
(cd) The instrument channel setpoint shall be reset to a value that is within the as | (cd) The instrument channel setpoint shall be reset to a value that is within the as | ||
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as | -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 | ||
| Line 535: | Line 479: | ||
Separate Condition entry is allowed for each channel. | Separate Condition entry is allowed for each channel. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable. | ||
A.1 Enter the Condition referenced in Table 3.3.5.3-1 for the channel. Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.3-1. B.1 Declare associated penetration flow path(s) incapable of automatic isolation. | A.1 Enter the Condition referenced in Table 3.3.5.3-1 for the channel. Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.3-1. B.1 Declare associated penetration flow path(s) incapable of automatic isolation. | ||
AND B.2 Calculate DRAIN TIME. Immediately | AND B.2 Calculate DRAIN TIME. Immediately | ||
| Line 543: | Line 487: | ||
24 hours RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-2 Amendment No. | 24 hours RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-2 Amendment No. | ||
XXX ACTIONS (continued) | XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met. E.1 Declare associated low pressure ECCS injection/spray subsystem inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met. E.1 Declare associated low pressure ECCS injection/spray subsystem inoperable. | ||
Immediately | Immediately | ||
| Line 550: | Line 494: | ||
Refer to Table 3.3.5.3-1 to determine which SRs apply for each ECCS Function. | Refer to Table 3.3.5.3-1 to determine which SRs apply for each ECCS Function. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
SURVEILLANCE FREQUENCY SR 3.3.5.3.1 Perform CHANNEL CHECK. | SURVEILLANCE FREQUENCY SR 3.3.5.3.1 Perform CHANNEL CHECK. | ||
12 hours SR 3.3.5.3.2 Perform CHANNEL FUNCTIONAL TEST. | 12 hours SR 3.3.5.3.2 Perform CHANNEL FUNCTIONAL TEST. | ||
92 days RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-3 Amendment No. | 92 days RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-3 Amendment No. | ||
| Line 556: | Line 500: | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System | SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System | ||
: a. Reactor Steam Dome Pressure - Low (Injection Permissive) 4, 5 2 C SR 3.3.5.3.2 397 psig and 440psig 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Steam Dome Pressure | : a. Reactor Steam Dome Pressure - Low (Injection Permissive) 4, 5 2 C SR 3.3.5.3.2 397 psig and 440psig 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Steam Dome Pressure - | ||
- | |||
Low (Injection Permissive) 4, 5 2 C SR 3.3.5.3.2 397 psig and 440 psig b. Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 4, 5 1 per pump(a) D SR 3.3.5.3.2 360 gpm and 745 gpm 3. RHR System Isolation | Low (Injection Permissive) 4, 5 2 C SR 3.3.5.3.2 397 psig and 440 psig b. Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 4, 5 1 per pump(a) D SR 3.3.5.3.2 360 gpm and 745 gpm 3. RHR System Isolation | ||
: a. Reactor Vessel Water Level | : a. Reactor Vessel Water Level - Low (b) 2 B SR 3.3.5.3.1 SR 3.3.5.3.2 7 inches 4. Reactor Water Cleanup (RWCU) System Isolation a. Reactor Vessel Water Level - Low Low (b) 2 B SR 3.3.5.3.1 SR 3.3.5.3.2 -48 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control." (b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME. | ||
- Low (b) 2 B SR 3.3.5.3.1 SR 3.3.5.3.2 7 inches 4. Reactor Water Cleanup (RWCU) System Isolation | |||
- Low Low (b) 2 B SR 3.3.5.3.1 SR 3.3.5.3.2 -48 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control." | |||
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-1 Amendment No. | Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-1 Amendment No. | ||
146 XXX 3.3 INSTRUMENTATION | 146 XXX 3.3 INSTRUMENTATION | ||
| Line 576: | Line 515: | ||
: 2. Separate Condition entry is allowed for each channel. | : 2. Separate Condition entry is allowed for each channel. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required channels inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required channels inoperable. | ||
A.1 Place channel in trip. | A.1 Place channel in trip. | ||
12 hours for Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND 24 hours for Functions other than Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b B. One or more Functions with primary containment isolation capability not maintained. | 12 hours for Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND 24 hours for Functions other than Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b B. One or more Functions with primary containment isolation capability not maintained. | ||
| Line 584: | Line 523: | ||
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-2 Amendment No. | Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-2 Amendment No. | ||
146 XXX ACTIONS (continued) | 146 XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. D.1 Isolate associated main steam line (MSL). | CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. D.1 Isolate associated main steam line (MSL). | ||
OR D.2.1 Be in MODE | OR D.2.1 Be in MODE | ||
: 3. AND D.2.2 Be in MODE | : 3. AND D.2.2 Be in MODE | ||
| Line 596: | Line 535: | ||
1 hour Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-3 Amendment No. | 1 hour Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-3 Amendment No. | ||
146 XXX ACTIONS (continued) | 146 XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. I.1 Initiate action to restore channel to OPERABLE status. OR I.2 Initiate action to isolate the Residual Heat Removal (RHR) Shutdown Cooling System. Immediately | CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. I.1 Initiate action to restore channel to OPERABLE status. OR I.2 Initiate action to isolate the Residual Heat Removal (RHR) Shutdown Cooling System. Immediately | ||
Immediately | Immediately | ||
| Line 605: | Line 544: | ||
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains primary containment isolation capability. | : 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains primary containment isolation capability. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. | SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. | ||
12 hours SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. | 12 hours SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. | ||
92 days SR 3.3.6.1.3 Calibrate the trip unit. | 92 days SR 3.3.6.1.3 Calibrate the trip unit. | ||
92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. | 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. | ||
92 days Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-4 Amendment No. 146 SURVEILLANCE REQUIREMENTS (continued) | 92 days Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-4 Amendment No. 146 SURVEILLANCE REQUIREMENTS (continued) | ||
SURVEILLANCE FREQUENCY SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. | 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 SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. | ||
24 months | 24 months | ||
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-5 Amendment No. | Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-5 Amendment No. | ||
146, 176 Table 3.3.6.1-1 (page 1 of 3) Primary Containment Isolation Instrumentation | 146 , 176 Table 3.3.6.1-1 (page 1 of 3) Primary Containment Isolation Instrumentation | ||
FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 | FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 | ||
| Line 621: | Line 560: | ||
SURVEILLANCE REQUIREMENTS | SURVEILLANCE REQUIREMENTS | ||
ALLOWABLE VALUE 1. Main Steam Line Isolation | ALLOWABLE VALUE 1. Main Steam Line Isolation a. Reactor Vessel Water Level - Low Low 1, 2, 3 2 D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 -48 inches b. Main Steam Line Pressure - Low 1 2 E SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 815 psig c. Main Steam Line Flow - High 1, 2, 3 2 per MSL D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 116.9% rated steam flow | ||
- Low Low 1, 2, 3 2 D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 | |||
: d. Main Steam Line Tunnel Temperature | : d. Main Steam Line Tunnel Temperature | ||
- High 1, 2, 3 2 per trip string D SR 3.3.6.1.5 SR 3.3.6.1.6 209F 2. Primary Containment Isolation | - High 1, 2, 3 2 per trip string D SR 3.3.6.1.5 SR 3.3.6.1.6 209F 2. Primary Containment Isolation a. Reactor Vessel Water Level - Low 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches b. Drywell Pressure - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig 3. High Pressure Coolant Injection (HPCI) System Isolation a. HPCI Steam Line Flow - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 300,000 lb/hour with 5.58 second time delay | ||
- Low 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches b. Drywell Pressure - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig 3. High Pressure Coolant Injection (HPCI) System Isolation | |||
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-6 Amendment No. | Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-6 Amendment No. | ||
| Line 635: | Line 568: | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3. HPCI System Isolation | SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3. HPCI System Isolation | ||
: b. HPCI Steam Supply Line Pressure - Low 1, 2, 3 4 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 95.5 psig c. HPCI Steam Line Area Temperature | : b. HPCI Steam Supply Line Pressure - Low 1, 2, 3 4 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 95.5 psig c. HPCI Steam Line Area Temperature - High 1, 2, 3 16 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196F 4. Reactor Core Isolation Cooling (RCIC) System Isolation a. RCIC Steam Line Flow - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 45,903 lb/hour with 7.16 second time delay | ||
- High 1, 2, 3 16 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196F 4. Reactor Core Isolation Cooling (RCIC) System Isolation | : b. RCIC Steam Supply Line Pressure - Low 1, 2, 3 4 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 54 psig c. RCIC Steam Line Area Temperature - High 1, 2, 3 16 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196F 5. Reactor Water Cleanup (RWCU) System Isolation a. RWCU Flow - High 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 500 gpm with 11.4 second time delay | ||
: b. RWCU Room Temperature - High 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188F c. Drywell Pressure - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-7 Amendment No. | |||
: b. RCIC Steam Supply Line Pressure - Low 1, 2, 3 4 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 54 psig c. RCIC Steam Line Area Temperature | 146 , 164, XXX Table 3.3.6.1-1 (page 3 of 3) Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 | ||
- High 1, 2, 3 16 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196F 5. Reactor Water Cleanup (RWCU) System Isolation | |||
- High 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 500 gpm with 11.4 second time delay | |||
: b. RWCU Room Temperature | |||
- High 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188F c. Drywell Pressure - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-7 Amendment No. | |||
146, 164, XXX Table 3.3.6.1-1 (page 3 of 3) Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1 | |||
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. RWCU System Isolation | SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. RWCU System Isolation | ||
: d. SLC System Initiation 1, 2, 3 1 H SR 3.3.6.1.6 NA e. Reactor Vessel Water Level - Low Low 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 | : d. SLC System Initiation 1, 2, 3 1 H SR 3.3.6.1.6 NA e. Reactor Vessel Water Level - Low Low 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 -48 inches 6. Shutdown Cooling System Isolation | ||
: a. Reactor Steam Dome Pressure - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 81.8 psig b. Reactor Vessel Water Level - Low 3, 4, 5 2(a) I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches 7. Traversing Incore Probe System Isolation | |||
: a. Reactor Steam Dome Pressure | : a. Reactor Vessel Water Level - Low 1, 2, 3 2 G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches b. Drywell Pressure - | ||
- High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 81.8 psig b. Reactor Vessel Water Level | High 1, 2, 3 2 G SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig (a) Only one channel per trip system, with an isolation signal available to one shutdown cooling supply isolation valve, is required in MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained. | ||
- Low 3, 4, 5 2(a) I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches 7. Traversing Incore Probe System Isolation | |||
: a. Reactor Vessel Water Level - Low 1, 2, 3 2 G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches b. Drywell Pressure - | |||
High 1, 2, 3 2 G SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig (a) Only one channel per trip system, with an isolation signal available to one shutdown cooling supply isolation valve, is required in MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained. | |||
Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-1 Amendment No. 146 | Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-1 Amendment No. 146 | ||
| Line 668: | Line 592: | ||
Separate Condition entry is allowed for each channel. | Separate Condition entry is allowed for each channel. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable. | ||
A.1 Place channel in trip. | A.1 Place channel in trip. | ||
12 hours for Functions 1 and 2 AND 24 hours for Functions other than Functions 1 and 2 B. One or more Functions with secondary containment isolation capability not maintained. | 12 hours for Functions 1 and 2 AND 24 hours for Functions other than Functions 1 and 2 B. One or more Functions with secondary containment isolation capability not maintained. | ||
| Line 676: | Line 600: | ||
OR C.1.2 Declare associated secondary containment isolation valves inoperable. | OR C.1.2 Declare associated secondary containment isolation valves inoperable. | ||
AND 1 hour 1 hour Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-2 Amendment No. 146 ACTIONS (continued) | AND 1 hour 1 hour Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-2 Amendment No. 146 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME C.2.1 Place the associated standby gas treatment (SGT) subsystem in operation. | CONDITION REQUIRED ACTION COMPLETION TIME C.2.1 Place the associated standby gas treatment (SGT) subsystem in operation. | ||
OR C.2.2 Declare associated SGT subsystem inoperable. | OR C.2.2 Declare associated SGT subsystem inoperable. | ||
1 hour | 1 hour | ||
| Line 685: | Line 609: | ||
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains secondary containment isolation capability. | : 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains secondary containment isolation capability. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. | SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK. | ||
12 hours SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. | 12 hours SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST. | ||
92 days SR 3.3.6.2.3 Calibrate the trip unit. | 92 days SR 3.3.6.2.3 Calibrate the trip unit. | ||
| Line 696: | Line 620: | ||
FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS | FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS | ||
ALLOWABLE VALUE 1. Reactor Vessel Water Level | ALLOWABLE VALUE 1. Reactor Vessel Water Level - Low Low 1, 2, 3, (a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6 -48 inches 2. Drywell Pressure - High 1, 2, 3 2 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 2 psig 3. Reactor Building Ventilation Exhaust Radiation - High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr 4. Refueling Floor Radiation - High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr (a) During operations with a potential for draining the reactor vessel. | ||
- Low Low 1, 2, 3, (a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6 | |||
- High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr 4. Refueling Floor Radiation | |||
- High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr (a) During operations with a potential for draining the reactor vessel. | |||
(ab) During movement of recently irradiated fuel assemblies in secondary containment. | (ab) During movement of recently irradiated fuel assemblies in secondary containment. | ||
| Line 711: | Line 631: | ||
Separate Condition entry is allowed for each channel. | Separate Condition entry is allowed for each channel. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable. | ||
B. Required Action and associated Completion Time not met. | B. Required Action and associated Completion Time not met. | ||
A.1 Declare associated CREF subsystem inoperable. | A.1 Declare associated CREF subsystem inoperable. | ||
| Line 726: | Line 646: | ||
SURVEILLANCE REQUIREMENTS | SURVEILLANCE REQUIREMENTS | ||
----------------------------------------------------------- | -----------------------------------------------------------NOTE S---------------------------------------------------------- | ||
: 1. Refer to Table 3.3.7.1 | : 1. Refer to Table 3.3.7.1 | ||
-1 to determine which SRs apply for each CREF System Function. | -1 to determine which SRs apply for each CREF System Function. | ||
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREF System initiation capability. | : 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours provided the associated Function maintains CREF System initiation capability. | ||
----------------------------------------------------------------------------------------------------------------------------- | ----------------------------------------------------------------------------------------------------------------------------- | ||
SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. | SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. | ||
12 hours SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. | 12 hours SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. | ||
92 days SR 3.3.7.1.3 Calibrate the trip unit. | 92 days SR 3.3.7.1.3 Calibrate the trip unit. | ||
| Line 738: | Line 658: | ||
24 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. | 24 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. | ||
24 months CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-3 Amendment No. | 24 months CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-3 Amendment No. | ||
146, 148, XXX Table 3.3.7.1 | 146 , 148, XXX Table 3.3.7.1 | ||
-1 (Page 1 of 1) | -1 (Page 1 of 1) | ||
Control Room Emergency Filtration System Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE 1. Reactor Vessel Water 1, 2, 3, (a) 2 SR 3.3.7.1.1 | Control Room Emergency Filtration System Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE 1. Reactor Vessel Water 1, 2, 3, (a) 2 SR 3.3.7.1.1 | ||
- 48 inches Level - Low Low SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.5 SR 3.3.7.1.6 | - 48 inches Level - Low Low SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.5 SR 3.3.7.1.6 | ||
: 2. Drywell Pressure - 1, 2, 3 2 SR 3.3.7.1.2 2 psig High SR 3.3.7.1.4 SR 3.3.7.1.6 | : 2. Drywell Pressure - 1, 2, 3 2 SR 3.3.7.1.2 2 psig High SR 3.3.7.1.4 SR 3.3.7.1.6 | ||
: 3. Reactor Building 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Ventilation Exhaust SR 3.3.7.1.2 Radiation | : 3. Reactor Building 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Ventilation Exhaust SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.6 | ||
- High SR 3.3.7.1.4 SR 3.3.7.1.6 | : 4. Refueling Floor 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Radiation - High SR 3.3.7.1.2 SR 3.3.7.1.4 SR 3.3.7.1.6 (a) During operations with a potential for draining the reactor vessel. | ||
: 4. Refueling Floor 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Radiation | |||
- High SR 3.3.7.1.2 SR 3.3.7.1.4 SR 3.3.7.1.6 (a) During operations with a potential for draining the reactor vessel. | |||
(b)(a) During movement of recently irradiated fuel assemblies in the secondary containment. | (b)(a) During movement of recently irradiated fuel assemblies in the secondary containment. | ||
ECCS - Operating | ECCS - Operating 3.5.1 Monticello 3.5.1-1 Amendment No. | ||
146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of three safety/relief valves shall be OPERABLE. | |||
3.5.1-1 Amendment No. | |||
146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.1 ECCS - Operating | |||
LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of three safety/relief valves shall be OPERABLE. | |||
---------------------------------------------NOTE-------------------------------------------- | ---------------------------------------------NOTE-------------------------------------------- | ||
| Line 765: | Line 678: | ||
LCO 3.0.4.b is not applicable to HPCI. | LCO 3.0.4.b is not applicable to HPCI. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One LPCI pump inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One LPCI pump inoperable. | ||
A.1 Restore LPCI pump to OPERABLE status. | A.1 Restore LPCI pump to OPERABLE status. | ||
30 days B. One LPCI subsystem inoperable for reasons other than Condition A. | 30 days B. One LPCI subsystem inoperable for reasons other than Condition A. | ||
OR One Core Spray subsystem inoperable. | OR One Core Spray subsystem inoperable. | ||
B.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status. 7 days ECCS - Operating | B.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status. 7 days ECCS - Operating 3.5.1 Monticello 3.5.1-2 Amendment No. | ||
146, 162 , 184 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME C. One LPCI pump in both LPCI subsystems inoperable. | |||
3.5.1-2 Amendment No. | |||
146, 162, 184 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME C. One LPCI pump in both LPCI subsystems inoperable. | |||
C.1 Restore one LPCI pump to OPERABLE status. | C.1 Restore one LPCI pump to OPERABLE status. | ||
7 days D. Two LPCI subsystems inoperable for reasons other than Condition C or G. D.1 Restore one LPCI subsystem to OPERABLE status. 72 hours E. One Core Spray subsystem inoperable. | 7 days D. Two LPCI subsystems inoperable for reasons other than Condition C or G. D.1 Restore one LPCI subsystem to OPERABLE status. 72 hours E. One Core Spray subsystem inoperable. | ||
| Line 790: | Line 700: | ||
: 3. AND F.2 Be in MODE | : 3. AND F.2 Be in MODE | ||
: 4. 12 hours 36 hours G. Two LPCI subsystems inoperable due to open RHR intertie return line isolation valve(s). | : 4. 12 hours 36 hours G. Two LPCI subsystems inoperable due to open RHR intertie return line isolation valve(s). | ||
G.1 Isolate the RHR intertie line. 18 hours ECCS - Operating | G.1 Isolate the RHR intertie line. 18 hours ECCS - Operating 3.5.1 Monticello 3.5.1-3 Amendment No. 146, 162, 176 , 184 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and associated Completion Time of Condition G not met. H.1 Be in MODE | |||
3.5.1-3 Amendment No. 146, 162, 176, 184 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and associated Completion Time of Condition G not met. H.1 Be in MODE | |||
: 2. 6 hours I. HPCI System inoperable. | : 2. 6 hours I. HPCI System inoperable. | ||
I.1 Verify by administrative means RCIC System is OPERABLE. | I.1 Verify by administrative means RCIC System is OPERABLE. AND I.2 Restore HPCI System to OPERABLE status. | ||
AND I.2 Restore HPCI System to OPERABLE status. | |||
Immediately | Immediately | ||
| Line 805: | Line 711: | ||
72 hours 72 hours K. One ADS valve inoperable. | 72 hours 72 hours K. One ADS valve inoperable. | ||
K.1 Restore ADS valve to OPERABLE status. | K.1 Restore ADS valve to OPERABLE status. | ||
14 days ECCS - Operating | 14 days ECCS - Operating 3.5.1 Monticello 3.5.1-4 Amendment No. 146, 162, 176 , 184 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME L. Required Action and associated Completion Time of Condition I, J, or K not met. | |||
3.5.1-4 Amendment No. 146, 162, 176, 184 ACTIONS (continued) | |||
CONDITION REQUIRED ACTION COMPLETION TIME L. Required Action and associated Completion Time of Condition I, J, or K not met. | |||
OR One ADS valve inoperable and Condition A, B, C, D, or G entered. OR Two or more ADS valves inoperable. | OR One ADS valve inoperable and Condition A, B, C, D, or G entered. OR Two or more ADS valves inoperable. | ||
OR HPCI System inoperable and Condition D, E, or G entered. L.1 Be in MODE | OR HPCI System inoperable and Condition D, E, or G entered. L.1 Be in MODE | ||
| Line 815: | Line 718: | ||
M.1 Enter LCO 3.0.3. Immediately | M.1 Enter LCO 3.0.3. Immediately | ||
ECCS - Operating | ECCS - Operating 3.5.1 Monticello 3.5.1-5 Amendment No. | ||
14 6, 15 5 , 162 , 189, 190 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water. 31 days SR 3.5.1.2 -------------------------------NOTE------------------------------ Not required to be met for system vent flow paths opened under administrative control. --------------------------------------------------------------------- | |||
3.5.1-5 Amendment No. | |||
Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. | Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. | ||
31 days SR 3.5.1.3 Verify ADS pneumatic pressure is as follows for each required ADS pneumatic supply: | 31 days SR 3.5.1.3 Verify ADS pneumatic pressure is as follows for each required ADS pneumatic supply: | ||
: a. S/RV Accumulator Bank header pressure 88.3 psig; and | : a. S/RV Accumulator Bank header pressure 88.3 psig; and | ||
| Line 833: | Line 732: | ||
In accordance with the Inservice Testing Program | In accordance with the Inservice Testing Program | ||
ECCS - Operating | ECCS - Operating 3.5.1 Monticello 3.5.1-6 Amendment No. | ||
14 6 , 162 , 167 SURVEILLANCE REQUIREMENTS (continued) | |||
SURVEILLANCE FREQUENCY SR 3.5.1.7 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor to containment pressure. | |||
3.5.1-6 Amendment No. | |||
SURVEILLANCE FREQUENCY SR 3.5.1.7 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor to containment pressure. | |||
System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of | System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of | ||
| Line 853: | Line 749: | ||
Verify, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure. | Verify, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure. | ||
24 months ECCS - Operating | 24 months ECCS - Operating 3.5.1 Monticello 3.5.1-7 Amendment No. | ||
3.5.1-7 Amendment No. | |||
146, 162, 168 SURVEILLANCE REQUIREMENTS (continued) | 146, 162, 168 SURVEILLANCE REQUIREMENTS (continued) | ||
SURVEILLANCE FREQUENCY SR 3.5.1.10 -------------------------------NOTE------------------------------ | SURVEILLANCE FREQUENCY SR 3.5.1.10 -------------------------------NOTE------------------------------ | ||
Vessel injection/spray may be excluded. | Vessel injection/spray may be excluded. | ||
--------------------------------------------------------------------- | --------------------------------------------------------------------- | ||
| Line 876: | Line 769: | ||
In accordance with the Inservice Testing Program SR 3.5.1.13 Verify automatic transfer capability of the LPCI swing bus power supply from the normal source to the backup source. | In accordance with the Inservice Testing Program SR 3.5.1.13 Verify automatic transfer capability of the LPCI swing bus power supply from the normal source to the backup source. | ||
24 months ECCS - Shutdown 3.5.2 Monticello 3.5.2-1 Amendment No. | 24 months ECCS - Shutdown 3.5.2 Monticello 3.5.2-1 Amendment No. | ||
146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.2 RPV Water Inventory Control ECCS - Shutdown LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours. AND OneTwo low pressure ECCS injection/spray subsystem s shall be OPERABLE. | 146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.2 RPV Water Inventory Control ECCS - Shutdown LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours. AND OneTwo low pressure ECCS injection/spray subsystem s shall be OPERABLE. ---------------------------------------------NOTE-------------------------------------------- | ||
A One Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable. | A One Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable. | ||
-------------------------------------------------------------------------------------------------- | -------------------------------------------------------------------------------------------------- | ||
| Line 883: | Line 775: | ||
APPLICABILITY: | APPLICABILITY: | ||
MODE 4 , MODE and 5, except with the spent fuel storage pool gates removed and water level 21 ft 11 inches over the top of the reactor pressure vessel flange. | MODE 4 , MODE and 5, except with the spent fuel storage pool gates removed and water level 21 ft 11 inches over the top of the reactor pressure vessel flange. | ||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One | ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One r Required ECCS injection/spray subsystem inoperable. | ||
A.1 Restore required ECCS injection/spray subsystem to OPERABLE status. | A.1 Restore required ECCS injection/spray subsystem to OPERABLE status. | ||
4 hours B. Required Action and associated Completion Time of Condition A not met. B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power. Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs). | 4 hours B. Required Action and associated Completion Time of Condition A not met. B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power. Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs). | ||
Immediately C. DRAIN TIME < 36 hours C.1 Verify secondary 4 | Immediately C. DRAIN TIME < 36 hours C.1 Verify secondary 4 hour s ECCS - Shutdown 3.5.2 ACTIONS (continued) | ||
Monticello 3.5.2-2 Amendment No. | Monticello 3.5.2-2 Amendment No. | ||
146, XXX 8 hours. C. Two required ECCS injection/spray subsystems inoperable. | 146, XXX 8 hours. C. Two required ECCS injection/spray subsystems inoperable. | ||
| Line 896: | Line 788: | ||
ECCS - Shutdown 3.5.2 ACTIONS (continued) | ECCS - Shutdown 3.5.2 ACTIONS (continued) | ||
Monticello 3.5.2-3 Amendment No. | Monticello 3.5.2-3 Amendment No. | ||
146, XXX AND D.2 Initiate action to establish secondary containment boundary. | 146, XXX AND D.2 Initiate action to establish secondary containment boundary. AND D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room. AND D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation. | ||
AND D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room. AND D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation. | |||
Immediately Immediately Immediately E. Required Action and associated Completion Time of Condition C or D not met. OR DRAIN TIME < 1 hour. E.1 Initiate action to restore DRAIN TIME to 36 hours. Immediately | Immediately Immediately Immediately E. Required Action and associated Completion Time of Condition C or D not met. OR DRAIN TIME < 1 hour. E.1 Initiate action to restore DRAIN TIME to 36 hours. Immediately | ||
| Line 903: | Line 794: | ||
Monticello 3.5.2-4 Amendment No. | Monticello 3.5.2-4 Amendment No. | ||
146, XXX ACTIONS (continued) | 146, XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and associated Completion Time not met. | CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and associated Completion Time not met. | ||
D.1Initiate action to restore secondary containment to OPERABLE status. AND D.2 Initiate action to restore one standby gas treatment subsystem to OPERABLE status. AND D.3 Initiate action to restore isolation capability in each required secondary containment penetration flow path not isolated. | D.1Initiate action to restore secondary containment to OPERABLE status. AND D.2 Initiate action to restore one standby gas treatment subsystem to OPERABLE status. AND D.3 Initiate action to restore isolation capability in each required secondary containment penetration flow path not isolated. | ||
Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours. 12 hours SR 3.5.2.21 Verify, for each a required ECCS injection/spray subsystem, the: | Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours. 12 hours SR 3.5.2.21 Verify, for each a required ECCS injection/spray subsystem, the: | ||
: a. Suppression pool water level is -3 ft; or b. ---------------------------NOTE---------------------------- Only one required ECCS injection/spray subsystem may take credit for this option during OPDRVs. ---------------------------------------------------------------- | : 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. | Condensate storage tank(s) water level is 7 ft for one tank operation and 4 ft for two tank operation. | ||
12 hours ECCS - Shutdown 3.5.2 ACTIONS (continued) | 12 hours ECCS - Shutdown 3.5.2 ACTIONS (continued) | ||
Monticello 3.5.2-5 Amendment No. | Monticello 3.5.2-5 Amendment No. | ||
146, XXX SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water. | 146, XXX SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water. | ||
31 days ECCS - Shutdown 3.5.2 Monticello 3.5.2-6 Amendment No. | 31 days ECCS - Shutdown 3.5.2 Monticello 3.5.2-6 Amendment No. | ||
146, 167, 189, 194, XXX SURVEILLANCE REQUIREMENTS (continued) | 146, 167 , 189, 194, XXX SURVEILLANCE REQUIREMENTS (continued) | ||
SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water. | SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water. | ||
31 days SR 3.5.2.43 -------------------------------NOTE------------------------------ | 31 days SR 3.5.2.43 -------------------------------NOTE------------------------------ | ||
Not required to be met for system vent flow paths opened under administrative control. --------------------------------------------------------------------- | Not required to be met for system vent flow paths opened under administrative control. --------------------------------------------------------------------- | ||
Verify for each the required ECCS injection/spray subsystem | Verify for each the required ECCS injection/spray subsystem , each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. | ||
, each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position. | |||
31 days SR 3.5.2.54 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes. | 31 days SR 3.5.2.54 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes. | ||
| Line 928: | Line 818: | ||
ECCS - Shutdown 3.5.2 Monticello 3.5.2-7 Amendment No. | ECCS - Shutdown 3.5.2 Monticello 3.5.2-7 Amendment No. | ||
146, 167, 189, 194, XXX SURVEILLANCE FREQUENCY subsystem operates actuates on a manual an actual or simulated automatic initiation signal. | 146, 167 , 189, 194, XXX SURVEILLANCE FREQUENCY subsystem operates actuates on a manual an actual or simulated automatic initiation signal. | ||
24 months RCIC System | 24 months RCIC System | ||
| Line 942: | Line 832: | ||
LCO 3.0.4.b is not applicable to the RCIC System. | LCO 3.0.4.b is not applicable to the RCIC System. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable. | ||
A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE. | A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE. AND A.2 Restore RCIC System to OPERABLE status. | ||
AND A.2 Restore RCIC System to OPERABLE status. | |||
Immediately | Immediately | ||
| Line 955: | Line 844: | ||
====3.5.3 Monticello==== | ====3.5.3 Monticello==== | ||
3.5.3-2 Amendment No. | 3.5.3-2 Amendment No. | ||
146, 189 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 -------------------------------NOTE------------------------------ | 146 , 189 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 -------------------------------NOTE------------------------------ | ||
Not required to be met for system vent flow paths opened under administrative control. --------------------------------------------------------------------- | Not required to be met for system vent flow paths opened under administrative control. --------------------------------------------------------------------- | ||
| Line 971: | Line 860: | ||
24 months SR 3.5.3.4 -------------------------------NOTE------------------------------ | 24 months SR 3.5.3.4 -------------------------------NOTE------------------------------ | ||
Vessel injection may be excluded. | Vessel injection may be excluded. --------------------------------------------------------------------- | ||
Verify the RCIC System actuates on an actual or simulated automatic initiation signal. | Verify the RCIC System actuates on an actual or simulated automatic initiation signal. | ||
| Line 984: | Line 872: | ||
APPLICABILITY: | APPLICABILITY: | ||
MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation." | 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---------------------------------------------------------- | ||
ACTIONS -----------------------------------------------------------NOTES---------------------------------------------------------- | : 1. Penetration flow paths may be unisolated intermittently under administrative controls. 2. Separate Condition entry is allowed for each penetration flow path. | ||
: 1. Penetration flow paths may be unisolated intermittently under administrative controls. | |||
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs. | : 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. | : 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------------ | |||
CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ | |||
Only applicable to penetration flow paths with two PCIVs. | Only applicable to penetration flow paths with two PCIVs. | ||
--------------------------------- | --------------------------------- | ||
| Line 1,000: | Line 885: | ||
PCIVs 3.6.1.3 Monticello 3.6.1.3-2 Amendment No. 146 ACTIONS (continued) | PCIVs 3.6.1.3 Monticello 3.6.1.3-2 Amendment No. 146 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTES------------- | CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTES------------- | ||
: 1. Isolation devices in high radiation areas may be verified by use of administrative means. | : 1. Isolation devices in high radiation areas may be verified by use of administrative means. | ||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | : 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | ||
------------------------------------- | ------------------------------------- | ||
Verify the affected penetration flow path is isolated. | Verify the affected penetration flow path is isolated. | ||
Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de | Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de | ||
| Line 1,013: | Line 898: | ||
PCIVs 3.6.1.3 Monticello 3.6.1.3-3 Amendment No. | PCIVs 3.6.1.3 Monticello 3.6.1.3-3 Amendment No. | ||
146 148 ACTIONS (continued) | 146 148 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------ | CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------ | ||
Only applicable to penetration flow paths with two PCIVs. | Only applicable to penetration flow paths with two PCIVs. | ||
--------------------------------- | --------------------------------- | ||
| Line 1,027: | Line 912: | ||
PCIVs 3.6.1.3 Monticello 3.6.1.3-4 Amendment No. | PCIVs 3.6.1.3 Monticello 3.6.1.3-4 Amendment No. | ||
146 ACTIONS (continued) | 146 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME C.2 --------------NOTES------------- | CONDITION REQUIRED ACTION COMPLETION TIME C.2 --------------NOTES------------- | ||
: 1. Isolation devices in high radiation areas may be verified by use of administrative means. | : 1. Isolation devices in high radiation areas may be verified by use of administrative means. | ||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | : 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | ||
------------------------------------- | ------------------------------------- | ||
Verify the affected penetration flow path is isolated. | Verify the affected penetration flow path is isolated. | ||
Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was | Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was | ||
| Line 1,040: | Line 925: | ||
PCIVs 3.6.1.3 Monticello 3.6.1.3-5 Amendment No. | PCIVs 3.6.1.3 Monticello 3.6.1.3-5 Amendment No. | ||
146 148 ACTIONS (continued) | 146 148 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration flow paths with one or more 18 inch primary containment purge and vent valves not within purge and vent valve leakage limits. | CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration flow paths with one or more 18 inch primary containment purge and vent valves not within purge and vent valve leakage limits. | ||
D.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. | D.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange. | ||
AND D.2 --------------NOTES------------- | AND D.2 --------------NOTES------------- | ||
| Line 1,046: | Line 931: | ||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | : 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | ||
------------------------------------- | ------------------------------------- | ||
Verify the affected penetration flow path is isolated. | Verify the affected penetration flow path is isolated. 24 hours | ||
24 hours | |||
Once per 31 days for isolation devices outside containment E. One or more MSIVs with leakage rate not within limits. E.1 Restore leakage rate to within limits. 8 hours F. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3. | Once per 31 days for isolation devices outside containment E. One or more MSIVs with leakage rate not within limits. E.1 Restore leakage rate to within limits. 8 hours F. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3. | ||
| Line 1,057: | Line 941: | ||
PCIVs 3.6.1.3 Monticello 3.6.1.3-6 Amendment No. | PCIVs 3.6.1.3 Monticello 3.6.1.3-6 Amendment No. | ||
146, 148, XXX ACTIONS (continued) | 146 , 148, XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and associated Completion Time of Condition A or B not met for PCIV(s) required to be OPERABLE during MODE 4 or 5. G.1 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs). | CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and associated Completion Time of Condition A or B not met for PCIV(s) required to be OPERABLE during MODE 4 or 5. G.1 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs). | ||
OR G.12 Initiate action to restore valve(s) to OPERABLE status. Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 | OR G.12 Initiate action to restore valve(s) to OPERABLE status. Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 ------------------------------NOTE------------------------------ | ||
Not required to be met when the 18 inch primary containment purge and vent valves are open for inerting, de | 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. | -inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open. | ||
| Line 1,069: | Line 952: | ||
31 days PCIVs 3.6.1.3 Monticello 3.6.1.3-7 Amendment No. | 31 days PCIVs 3.6.1.3 Monticello 3.6.1.3-7 Amendment No. | ||
146 SURVEILLANCE REQUIREMENTS (continued) | 146 SURVEILLANCE REQUIREMENTS (continued) | ||
SURVEILLANCE FREQUENCY SR 3.6.1.3.2 | 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. | : 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means. | ||
: 2. Not required to be met for PCIVs that are open under administrative controls. | : 2. Not required to be met for PCIVs that are open under administrative controls. | ||
| Line 1,086: | Line 968: | ||
Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge. | Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge. | ||
31 days SR 3.6.1.3.5 Verify the isolation time of each power operated automatic PCIV, except for MSIVs, is within limits. | 31 days SR 3.6.1.3.5 Verify the isolation time of each power operated automatic PCIV, except for MSIVs, is within limits. | ||
24 months PCIVs 3.6.1.3 Monticello 3.6.1.3-8 Amendment No. 146 148 | 24 months PCIVs 3.6.1.3 Monticello 3.6.1.3-8 Amendment No. 146 148 , 176 SURVEILLANCE REQUIREMENTS (continued) | ||
, 176 SURVEILLANCE REQUIREMENTS (continued) | SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is 3 seconds and 9.9 seconds. 24 months SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation position on an actual or simulated isolation signal. | ||
SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is 3 seconds and 9.9 seconds. 24 months SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation position on an actual or simulated isolation signal. | 24 months SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV actuates on a simulated instrument line break to restrict flow to 2 gpm. 24 months SR 3.6.1.3.9 Verify each 18 inch primary containment purge and vent valve is blocked to restrict the valve from opening > 40. 24 months SR 3.6.1.3.10 Remove and test the explosive squib from each shear isolation valve of the TIP System. | ||
24 months SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV actuates on a simulated instrument line break to restrict flow to 2 gpm. 24 months SR 3.6.1.3.9 Verify each 18 inch primary containment purge and vent valve is blocked to restrict the valve from opening > | |||
24 months on a STAGGERED TEST BASIS SR 3.6.1.3.11 Perform leakage rate testing for each 18 inch primary containment purge and vent valve with resilient seals. | 24 months on a STAGGERED TEST BASIS SR 3.6.1.3.11 Perform leakage rate testing for each 18 inch primary containment purge and vent valve with resilient seals. | ||
In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify leakage rate through each MSIV is: | In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify leakage rate through each MSIV is: | ||
| Line 1,102: | Line 982: | ||
LCO 3.6.4.1 The secondary containment shall be OPERABLE. | LCO 3.6.4.1 The secondary containment shall be OPERABLE. | ||
APPLICABILITY: | APPLICABILITY: | ||
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment inoperable in MODE 1, 2, or 3. A.1 Restore secondary containment to OPERABLE status. 4 hours B. Required Action and associated Completion Time of Condition A not met. B.1 Be in MODE | MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment inoperable in MODE 1, 2, or 3. A.1 Restore secondary containment to OPERABLE status. 4 hours B. Required Action and associated Completion Time of Condition A not met. B.1 Be in MODE | ||
: 3. AND B.2 Be in MODE | : 3. AND B.2 Be in MODE | ||
: 4. 12 hours 36 hours C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. C.1 ---------------NOTE-------------- | : 4. 12 hours 36 hours C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. C.1 ---------------NOTE-------------- | ||
| Line 1,114: | Line 994: | ||
Secondary Containment 3.6.4.1 Monticello 3.6.4.1-2 Amendment No. | Secondary Containment 3.6.4.1 Monticello 3.6.4.1-2 Amendment No. | ||
146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge. | 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge. | ||
24 hours SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed. | 24 hours SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed. | ||
31 days SR 3.6.4.1.3 Verify one secondary containment access door in each access opening is closed. | 31 days SR 3.6.4.1.3 Verify one secondary containment access door in each access opening is closed. | ||
31 days SR 3.6.4.1.4 Verify the secondary containment can be maintained 0.25 inch of vacuum water gauge for 1 hour using one SGT subsystem at a flow rate 4000 cfm. 24 months on a STAGGERED TEST BASIS for each SGT subsystem | 31 days SR 3.6.4.1.4 Verify the secondary containment can be maintained 0.25 inch of vacuum water gauge for 1 hour using one SGT subsystem at a flow rate 4000 cfm. 24 months on a STAGGERED TEST BASIS for each SGT subsystem SCIVs 3.6.4.2 Monticello 3.6.4.2-1 Amendment No. | ||
SCIVs 3.6.4.2 Monticello 3.6.4.2-1 Amendment No. | |||
146, XXX 3.6 CONTAINMENT SYSTEMS | 146, XXX 3.6 CONTAINMENT SYSTEMS | ||
| Line 1,132: | Line 1,010: | ||
: 3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs. | : 3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration flow paths with one SCIV inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration flow paths with one SCIV inoperable. | ||
A.1 Isolate the affected penetration flow path by use of at least one closed | A.1 Isolate the affected penetration flow path by use of at least one closed | ||
and de-activated automatic valve, closed manual valve, or blind flange. | and de-activated automatic valve, closed manual valve, or blind flange. | ||
AND 8 hours SCIVs 3.6.4.2 Monticello 3.6.4.2-2 Amendment No. 146 ACTIONS (continued) | AND 8 hours SCIVs 3.6.4.2 Monticello 3.6.4.2-2 Amendment No. 146 ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTES------------- | CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTES------------- | ||
: 1. Isolation devices in high radiation areas may be verified by use of administrative means. | : 1. Isolation devices in high radiation areas may be verified by use of administrative means. | ||
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | : 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means. | ||
------------------------------------- | ------------------------------------- | ||
Verify the affected penetration flow path is isolated. | Verify the affected penetration flow path is isolated. | ||
Once per 31 days B. ------------NOTE------------ | Once per 31 days B. ------------NOTE------------ | ||
| Line 1,152: | Line 1,030: | ||
: 3. AND C.2 Be in MODE 4. 12 hours 36 hours SCIVs 3.6.4.2 Monticello 3.6.4.2-3 Amendment No. | : 3. AND C.2 Be in MODE 4. 12 hours 36 hours SCIVs 3.6.4.2 Monticello 3.6.4.2-3 Amendment No. | ||
146, XXX ACTIONS (continued) | 146, XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. D.1 ---------------NOTE-------------- | CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. D.1 ---------------NOTE-------------- | ||
LCO 3.0.3 is not applicable. | LCO 3.0.3 is not applicable. | ||
------------------------------------- | ------------------------------------- | ||
| Line 1,159: | Line 1,037: | ||
AND D.2 Initiate action to suspend OPDRVs. Immediately Immediately | AND D.2 Initiate action to suspend OPDRVs. Immediately Immediately | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 | ||
------------------------------NOTES----------------------------- | ------------------------------NOTES----------------------------- | ||
: 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means. | : 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means. | ||
| Line 1,176: | Line 1,054: | ||
LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE. | LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE. | ||
APPLICABILITY: | APPLICABILITY: | ||
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable. | MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable. | ||
A.1 Restore SGT subsystem to OPERABLE status. | A.1 Restore SGT subsystem to OPERABLE status. | ||
7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3. B.1 Be in MODE | 7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3. B.1 Be in MODE | ||
| Line 1,192: | Line 1,070: | ||
SGT System 3.6.4.3 Monticello 3.6.4.3-2 Amendment No. | SGT System 3.6.4.3 Monticello 3.6.4.3-2 Amendment No. | ||
146, 181, XXX ACTIONS (continued) | 146, 181, XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME C.2.2 Initiate action to suspend OPDRVs. Immediately D. Two SGT subsystems inoperable in MODE 1, 2, or 3. D.1 Enter LCO | CONDITION REQUIRED ACTION COMPLETION TIME C.2.2 Initiate action to suspend OPDRVs. Immediately D. Two SGT subsystems inoperable in MODE 1, 2, or 3. D.1 Enter LCO 3.0.3. Immediately E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. E.1 ---------------NOTE-------------- | ||
E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. E.1 ---------------NOTE-------------- | |||
LCO 3.0.3 is not applicable. | LCO 3.0.3 is not applicable. | ||
------------------------------------- | ------------------------------------- | ||
| Line 1,201: | Line 1,076: | ||
AND E.2 Initiate action to suspend OPDRVs. Immediately Immediately | AND E.2 Initiate action to suspend OPDRVs. Immediately Immediately | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes. 31 days SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP). | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes. 31 days SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP). | ||
In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal. | In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal. | ||
24 months CREF System | 24 months CREF System | ||
| Line 1,216: | Line 1,091: | ||
APPLICABILITY: | 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). | MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment., During operations with a potential for draining the reactor vessel (OPDRVs). | ||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREF subsystem inoperable for reasons other than Condition B. A.1 Restore CREF subsystem to OPERABLE status. | |||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREF subsystem inoperable for reasons other than Condition B. A.1 Restore CREF subsystem to OPERABLE status. | |||
7 days B. One or more CREF subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3. B.1 Initiate action to implement mitigating actions. | 7 days B. One or more CREF subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3. B.1 Initiate action to implement mitigating actions. | ||
AND B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical and smoke hazards will not exceed limits. AND B.3 Restore CRE boundary to OPERABLE status. | AND B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical and smoke hazards will not exceed limits. AND B.3 Restore CRE boundary to OPERABLE status. | ||
| Line 1,234: | Line 1,108: | ||
3.7.4-3 Amendment No. | 3.7.4-3 Amendment No. | ||
146, 160, XXX ACTIONS (continued) | 146, 160, XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1 Be in MODE | CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1 Be in MODE | ||
: 3. AND C.2 Be in MODE | : 3. AND C.2 Be in MODE | ||
: 4. 12 hours 36 hours D. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------------NOTE------------------- | : 4. 12 hours 36 hours D. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------------NOTE------------------- | ||
| Line 1,242: | Line 1,116: | ||
AND D.2.2 Initiate action to suspend OPDRVs. | AND D.2.2 Initiate action to suspend OPDRVs. | ||
Immediately Immediately Immediately E. Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B. | Immediately Immediately Immediately E. Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B. | ||
E.1 Enter LCO | E.1 Enter LCO 3.0.3. Immediately | ||
CREF System | CREF System | ||
| Line 1,251: | Line 1,123: | ||
3.7.4-4 Amendment No. | 3.7.4-4 Amendment No. | ||
146, 160, 175, 181, XXX ACTIONS (continued) | 146, 160, 175, 181, XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREF subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. OR One or more CREF subsystems inoperable due to an inoperable CRE boundary during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs | CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREF subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. OR One or more CREF subsystems inoperable due to an inoperable CRE boundary during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs | ||
. --------------------NOTE------------------- | . --------------------NOTE------------------- | ||
LCO 3.0.3 is not applicable. | LCO 3.0.3 is not applicable. | ||
| Line 1,258: | Line 1,130: | ||
AND F.2 Initiate action to suspend OPDRVs. Immediately Immediately | AND F.2 Initiate action to suspend OPDRVs. Immediately Immediately | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each CREF subsystem for 15 continuous minutes. 31 days SR 3.7.4.2 Perform required CREF filter testing in accordance with the Ventilation Filter Testing Program (VFTP). | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each CREF subsystem for 15 continuous minutes. 31 days SR 3.7.4.2 Perform required CREF filter testing in accordance with the Ventilation Filter Testing Program (VFTP). | ||
In accordance with the VFTP SR 3.7.4.3 Verify each CREF subsystem actuates on an actual or simulated initiation signal. | In accordance with the VFTP SR 3.7.4.3 Verify each CREF subsystem actuates on an actual or simulated initiation signal. | ||
24 months SR 3.7.4.4 Perform required CRE unfiltered air in | 24 months SR 3.7.4.4 Perform required CRE unfiltered air in | ||
-leakage testing in accordance with the Control Room Envelope Habitability Program. | -leakage testing in accordance with the Control Room Envelope Habitability Program. | ||
In accordance with the Control Room Envelope Habitability Program Control Room Ventilation System | In accordance with the Control Room Envelope Habitability Program Control Room Ventilation System | ||
| Line 1,272: | Line 1,144: | ||
LCO 3.7.5 Two control room ventilation subsystems shall be OPERABLE. | LCO 3.7.5 Two control room ventilation subsystems shall be OPERABLE. | ||
APPLICABILITY: | 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). | MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment,. During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room ventilation subsystem inoperable. | ||
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room ventilation subsystem inoperable. | |||
A.1 Restore control room ventilation subsystem to OPERABLE status. | A.1 Restore control room ventilation subsystem to OPERABLE status. | ||
30 days B. Two control room ventilation subsystems inoperable. | 30 days B. Two control room ventilation subsystems inoperable. | ||
| Line 1,296: | Line 1,167: | ||
3.7.5-2 Amendment No. | 3.7.5-2 Amendment No. | ||
146, 148, 154, XXX ACTIONS (continued) | 146, 148, 154, XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment. | CONDITION REQUIRED ACTION COMPLETION TIME D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment. | ||
AND D.2.2 Initiate action to suspend OPDRVs. Immediately Immediately E. Required Action and associated Completion Time of Condition B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------------NOTE------------------- | AND D.2.2 Initiate action to suspend OPDRVs. Immediately Immediately E. Required Action and associated Completion Time of Condition B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------------NOTE------------------- | ||
LCO 3.0.3 is not applicable. | LCO 3.0.3 is not applicable. | ||
| Line 1,306: | Line 1,177: | ||
Immediately | Immediately | ||
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each control room ventilation subsystem has the capability to remove the assumed heat load. | Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each control room ventilation subsystem has the capability to remove the assumed heat load. | ||
24 months AC Sources - Shutdown 3.8.2 Monticello 3.8.2-1 Amendment No. | 24 months AC Sources - Shutdown 3.8.2 Monticello 3.8.2-1 Amendment No. | ||
146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS | 146 , 148 , XXX 3.8 ELECTRICAL POWER SYSTEMS | ||
3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE: | 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE: | ||
| Line 1,319: | Line 1,190: | ||
LCO 3.0.3 is not applicable. | LCO 3.0.3 is not applicable. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit inoperable. | ||
--------------------NOTE------------------- | --------------------NOTE------------------- | ||
Enter applicable Condition and Required Actions of LCO 3.8.8, with one required division de | Enter applicable Condition and Required Actions of LCO 3.8.8, with one required division de | ||
| Line 1,330: | Line 1,201: | ||
AC Sources - Shutdown 3.8.2 Monticello 3.8.2-2 Amendment No. | AC Sources - Shutdown 3.8.2 Monticello 3.8.2-2 Amendment No. | ||
146, 148, XXX ACTIONS (continued) | 146 , 148 , XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME A.2.1 Suspend CORE ALTERATIONS. | CONDITION REQUIRED ACTION COMPLETION TIME A.2.1 Suspend CORE ALTERATIONS. | ||
AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment. | AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment. | ||
AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs). | AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs). | ||
| Line 1,344: | Line 1,215: | ||
Immediately Immediately | Immediately Immediately | ||
AC Sources - Shutdown 3.8.2 Monticello 3.8.2-3 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 | AC Sources - Shutdown 3.8.2 Monticello 3.8.2-3 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 | ||
------------------------------NOTES----------------------------- | ------------------------------NOTES----------------------------- | ||
: 1. The following SRs are not required to be performed: | : 1. The following SRs are not required to be performed: | ||
SR 3.8.1.3, SR 3.8.1.7, and SR 3.8.1.8 through SR 3.8.1.13. | SR 3.8.1.3, SR 3.8.1.7, and SR 3.8.1.8 through SR 3.8.1.13. | ||
: 2. SR 3.8.1.8 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown." | : 2. SR 3.8.1.8 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown." --------------------------------------------------------------------- | ||
For AC sources required to be OPERABLE the SRs of Specification 3.8.1, except SR 3.8.1.6, are applicable. | For AC sources required to be OPERABLE the SRs of Specification 3.8.1, except SR 3.8.1.6, are applicable. | ||
In accordance with applicable SRs DC Sources - Shutdown 3.8.5 Monticello 3.8.5-1 Amendment No. | In accordance with applicable SRs DC Sources - Shutdown 3.8.5 Monticello 3.8.5-1 Amendment No. | ||
146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS | 146 , 148, XXX 3.8 ELECTRICAL POWER SYSTEMS | ||
3.8.5 DC Sources - Shutdown LCO 3.8.5 Division 1 or Division 2 125 VDC electrical power subsystem shall be OPERABLE to support one division of the DC Electrical Power Distribution System required by LCO 3.8.8, "Distribution Systems - Shutdown." | 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: | APPLICABILITY: | ||
MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment. | MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment. | ||
| Line 1,363: | Line 1,232: | ||
LCO 3.0.3 is not applicable. | LCO 3.0.3 is not applicable. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable. | ||
A.1 Suspend CORE ALTERATIONS. | A.1 Suspend CORE ALTERATIONS. | ||
AND A.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment. | AND A.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment. | ||
| Line 1,374: | Line 1,243: | ||
DC Sources - Shutdown 3.8.5 Monticello 3.8.5-2 Amendment No. | DC Sources - Shutdown 3.8.5 Monticello 3.8.5-2 Amendment No. | ||
146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 | 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 | ||
-------------------------------NOTE------------------------------ | -------------------------------NOTE------------------------------ | ||
The following SR is not required to be performed: | The following SR is not required to be performed: | ||
| Line 1,384: | Line 1,253: | ||
In accordance with applicable SRs Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-1 Amendment No. | In accordance with applicable SRs Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-1 Amendment No. | ||
146, 148, XXX 3.8 ELECTRICAL POWER SYSTEMS | 146 , 148, XXX 3.8 ELECTRICAL POWER SYSTEMS | ||
3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE. | 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: | APPLICABILITY: | ||
MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment. | MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment. | ||
| Line 1,393: | Line 1,261: | ||
LCO 3.0.3 is not applicable. | LCO 3.0.3 is not applicable. | ||
------------------------------------------------------------------------------------------------------------------------------- | ------------------------------------------------------------------------------------------------------------------------------- | ||
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC or DC electrical power distribution subsystems inoperable. | CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC or DC electrical power distribution subsystems inoperable. | ||
A.1 Declare associated supported required feature(s) inoperable. | A.1 Declare associated supported required feature(s) inoperable. | ||
OR A.2.1 Suspend CORE ALTERATIONS. | OR A.2.1 Suspend CORE ALTERATIONS. | ||
| Line 1,403: | Line 1,271: | ||
Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-2 Amendment No. | Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-2 Amendment No. | ||
146, XXX ACTIONS (continued) | 146, XXX ACTIONS (continued) | ||
CONDITION REQUIRED ACTION COMPLETION TIME A.2.34 Initiate actions to restore required AC and DC electrical power distribution subsystems to OPERABLE status. AND A.2.45 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation. | CONDITION REQUIRED ACTION COMPLETION TIME A.2.34 Initiate actions to restore required AC and DC electrical power distribution subsystems to OPERABLE status. AND A.2.45 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation. | ||
Immediately | Immediately | ||
Immediately | Immediately | ||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage to required AC and DC electrical power distribution subsystems. | SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage to required AC and DC electrical power distribution subsystems. | ||
7 days}} | 7 days}} | ||
Revision as of 15:54, 7 July 2018
| ML17250A871 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 09/07/2017 |
| From: | Kuntz R F Plant Licensing Branch III |
| To: | |
| Kuntz R F, NRR/DORL/LPLIII, | |
| References | |
| Download: ML17250A871 (83) | |
Text
Monticello i Revision 0 TABLE OF CONTENTS Page Number 1.0 USE AND APPLICATION
1.1 Definitions
............................................................................................................
1.1-1 1.2 Logical Connectors
..............................................................................................
1.2-1 1.3 Completion Times
................................................................................................
1.3-1 1.4 Frequency ...........................................................................................................
1.4-1 2.0 SAFETY LIMITS (SLs)
..............................................................................................
2.0-1 2.1 Safety Limits 2.2 SL Violations
3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY
..........................
3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
.........................................
3.0-4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)
....................................................................
3.1.1-1 3.1.2 Reactivity Anomalies
...................................................................................
3.1.2-1 3.1.3 Control Rod OPERABILITY
........................................................................
3.1.3-1 3.1.4 Control Rod Scram Times
...........................................................................
3.1.4-1 3.1.5 Control Rod Scram Accumulators
...............................................................
3.1.5-1 3.1.6 Rod Pattern Control
....................................................................................
3.1.6-1 3.1.7 Standby Liquid Control (SLC) System
.........................................................
3.1.7-1 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves
.............................
3.1.8-1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) .............................................................................................
3.2.1-1 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)
...........................................
3.2.2-1 3.2.3 LINEAR HEAT GENERATION RATE (LHGR) (Optional)
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3.2.3-1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation
...................................
3.3.1.1-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation
.........................................
3.3.1.2-1 3.3.2.1 Control Rod Block Instrumentation
...........................................................
3.3.2.1-1 3.3.2.2 Feedwater Pump and Main Turbine High Water Level Trip Instrumentation
..................................................................................
3.3.2.2-1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation
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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
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3.3.5.1-1 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation
..............
3.3.5.2-1 3.3.5.3 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation-------------------------3.3.5.3-1 3.3.6.1 Primary Containment Isolation Instrumentation
........................................
3.3.6.1-1 3.3.6.2 Secondary Containment Isolation Instrumentation
...................................
3.3.6.2-1 3.3.6.3 Low-Low Set (LLS) Instrumentation
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3.3.6.3-1 3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation
..................................................................................
3.3.7.1-1 3.3.7.2 Mechanical Vacuum Pump Isolation Instrumentation
...............................
3.3.7.2-1 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 ii Revision 01 TABLE OF CONTENTS Page Number 3.3.8.1 Loss of Power (LOP) Instrumentation
......................................................
3.3.8.1-1 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring
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3.3.8.2-1 TABLE OF CONTENTS Page Number 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating
....................................................................
3.4.1-1 3.4.2 Jet Pumps ...................................................................................................
3.4.2-1 3.4.3 Safety/Relief Valves (S/RVs)
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3.4.3-1 3.4.4 RCS Operational LEAKAGE
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3.4.4-1 3.4.5 RCS Leakage Detection Instrumentation
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3.4.5-1 3.4.6 RCS Specific Activity
..................................................................................
3.4.6-1 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..............................................................................................
3.4.7-1 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ..............................................................................................
3.4.8-1 3.4.9 RCS Pressure and Temperature (P/T) Limits
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3.4.9-1 3.4.10 Reactor Steam Dome Pressure
................................................................
3.4.10-1 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS - Operating .......................................................................................
3.5.1-1 3.5.2 RPV Water Inventory ControlECCS - Shutdown .........................................
3.5.2-1 3.5.3 RCIC System
..............................................................................................
3.5.3-1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment
...............................................................................
3.6.1.1-1 3.6.1.2 Primary Containment Air Lock..................................................................
3.6.1.2-1 3.6.1.3 Primary Containment Isolation Valves (PCIVs)
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3.6.1.3-1 3.6.1.4 Drywell Air Temperature
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3.6.1.4-1 3.6.1.5 Low-Low Set (LLS) Valves
.......................................................................
3.6.1.5-1 3.6.1.6 Reactor Building
-to-Suppression Chamber Vacuum Breakers
.................
3.6.1.6-1 3.6.1.7 Suppression Chamber
-to-Drywell Vacuum Breakers
...............................
3.6.1.7-1 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray
..........................................
3.6.1.8-1 3.6.2.1 Suppression Pool Average Temperature
.................................................
3.6.2.1-1 3.6.2.2 Suppression Pool Water Level
................................................................. 3.6.2.2-1 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling .......................
3.6.2.3-1 3.6.3.1 Primary Containment Oxygen Concentration
...........................................
3.6.3.1-1 3.6.4.1 Secondary Containment...........................................................................
3.6.4.1-1 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)
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3.6.4.2-1 3.6.4.3 Standby Gas Treatment (SGT) System
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3.6.4.3-1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System
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3.7.1-1 3.7.2 Emergency Service Water (ESW) System and Ultimate Heat Sink (UHS)
............................................................................................
3.7.2-1 3.7.3 Emergency Diesel Generator Emergency Service Water (EDG-ESW) System
..............................................................................
3.7.3-1 3.7.4 Control Room Emergency Filtration (CREF) System
...................................
3.7.4-1 3.7.5 Control Room Ventilation System
...............................................................
3.7.5-1 Monticello ii Revision 1 3.7.6 Main Condenser Offgas
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3.7.6-1 3.7.7 Main Turbine Bypass System
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3.7.7-1 3.7.8 Spent Fuel Storage Pool Water Level
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3.7.8-1 Monticello iii Revision 0 TABLE OF CONTENTS Page Number 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating ..............................................................................
3.8.1-1 3.8.2 AC Sources - Shutdown ..............................................................................
3.8.2-1 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air
...................................................
3.8.3-1 3.8.4 DC Sources - Operating ..............................................................................
3.8.4-1 3.8.5 DC Sources - Shutdown ..............................................................................
3.8.5-1 3.8.6 Battery Parameters
.....................................................................................
3.8.6-1 3.8.7 Distribution Systems - Operating ................................................................. 3.8.7-1 3.8.8 Distribution Systems - Shutdown ................................................................
3.8.8-1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks
...................................................................
3.9.1-1 3.9.2 Refuel Position One
-Rod-Out Interlock
.......................................................
3.9.2-1 3.9.3 Control Rod Position
...................................................................................
3.9.3-1 3.9.4 Control Rod Position Indication
...................................................................
3.9.4-1 3.9.5 Control Rod OPERABILITY - Refueling ......................................................
3.9.5-1 3.9.6 Reactor Pressure Vessel (RPV) Water Level
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3.9.6-1 3.9.7 Residual Heat Removal (RHR) - High Water Level
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3.9.7-1 3.9.8 Residual Heat Removal (RHR) - Low Water Level
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3.9.8-1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation
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3.10.1-1 3.10.2 Reactor Mode Switch Interlock Testing
.....................................................
3.10.2-1 3.10.3 Single Control Rod Withdrawal - Hot Shutdown
........................................
3.10.3-1 3.10.4 Single Control Rod Withdrawal - Cold Shutdown
......................................
3.10.4-1 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling ...............................
3.10.5-1 3.10.6 Multiple Control Rod Withdrawal - Refueling .............................................
3.10.6-1 3.10.7 Control Rod Testing - Operating ...............................................................
3.10.7-1 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling ........................................
3.10.8-1 4.0 DESIGN FEATURES
................................................................................................. 4.0-1 4.1 Site Location 4.2 Reactor Core 4.3 Fuel Storage
5.0 ADMINISTRATIVE CONTROLS
5.1 Responsibility
......................................................................................................
5.1-1 5.2 Organization
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5.2-1 5.3 Unit Staff Qualifications
.......................................................................................
5.3-1 5.4 Procedures
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5.4-1 5.5 Programs and Manuals
........................................................................................
5.5-1 5.6 Reporting Requirements
......................................................................................
5.6-1 5.7 High Radiation Area
.............................................................................................
5.7-1
Definitions
1.1 Monticello
1.1-1 Amendment No.
146 1.0 USE AND APPLICATION
1.1 Definitions
NOTE-----------------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition
ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific planar height HEAT GENERATION RATE and is equal to the sum of the LHGRs for all the fuel rods in (APLHGR) the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass all devices in the channel required for channel OPERABILITY and the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel. The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST shall be the injection of a TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.
Definitions
1.1 Monticello
1.1-2 Amendment No.
146 148, XXX 1.1 Definitions CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. The following exceptions are not considered to be CORE ALTERATIONS:
- a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
- b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT I
-131 DOSE EQUIVALENT I
-131 shall be that concentration of I
-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of I
-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR)
-11, "Limiting Values of Radionuclide Intake and Air Concentration Factors for Inhalation, Submersion and Ingestion," September 1988, and FGR
-12, "External Exposure to Radionuclides in Air, Water and Soil," September 1993
. DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming: a) The water inventory above the TAF is divided by the limiting drain rate; b) The limiting drain rate is the larger of the drain rate through a single penetration flow path with the highest flow rate, or the sum of the drain rates through multiple penetration flow paths susceptible to a common mode failure (e.g., seismic event, loss of normal power, single Definitions
1.1 Monticello
1.1-3 Amendment No.
146 148, XXX human error), for all penetration flow paths below the TAF except:
- 1. Penetration flow path s connected to an intact closed system, or isolated by manual or automatic valve s that are locked, sealed, or otherwise secured in the closed position, blank flange s, or other device s that prevent flow of reactor coolant through the penetration flow paths; 2. Penetration flow path s capable of being isolated by valve s that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or
- 3. Penetration flow path s with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power.
c) The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory; d) No additional draining events occur; and e) Realistic cross-sectional areas and drain rates are used.
A bounding DRAIN TIME may be used in lieu of a calculated value. LEAKAGE LEAKAGE shall be:
- a. Identified LEAKAGE
- 1. LEAKAGE into the drywell, such as that from pump seals or valve packing that is captured and conducted to a sump or collecting tank; or
- 2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;
Definitions
1.1 Monticello
1.1-4 Amendment No. 146
1.1 Definitions
LEAKAGE (continued)
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.
Definitions
1.1 Monticello
1.1-5 Amendment No.
146, 1 72, 175 , 176, 179 1.1 Definitions OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).
PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with
Specification 5.6.5.
RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2004 MWt. REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval from SYSTEM (RPS) RESPONSE initiation of any RPS channel trip to the de-energization of the TIME scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
SDM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:
- a. The reactor is xenon free;
- b. The moderator temperature is 68F corresponding to the most reactive state; and c. All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn. With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.
Definitions
1.1 Monticello
1.1-6 Amendment No.
14 6, 175 1.1 Definitions STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME shall be RESPONSE TIME that time interval from when the main turbine trip solenoid is activated until 80% of the turbine bypass capacity is established. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
Definitions
1.1 Monticello
1.1-7 Amendment No. 146 Table 1.1-1 (page 1 of 1) MODES
MODE
TITLE REACTOR MODE SWITCH POSITION AVERAGE REACTOR COOLANT TEMPERATURE
( F) 1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot Standby NA 3 Hot Shutdown(a) Shutdown > 212 4 Cold Shutdown(a) Shutdown 212 5 Refueling(b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.
(b) One or more reactor vessel head closure bolts less than fully tensioned.
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-1 Amendment No.
146 , X XX 3.3 INSTRUMENTATION
3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation
LCO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.5.1-1.
ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
A.1 Enter the Condition referenced in Table 3.3.5.1-1 for the channel. Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. B.1 --------------NOTE S-------------
- 1. Only applicable in MODES 1, 2, and 3. 2. Only applicable for Functions 1.a, 1.b, 2.a, 2.b, 2.f, 2.h, and 2.k. -------------------------------------
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-2 Amendment No.
146 , X XX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B.2 ---------------NOTE--------------
Only applicable for Functions 3.a and 3.b. -------------------------------------
Declare High Pressure Coolant Injection (HPCI) System inoperable.
AND B.3 Place channel in trip.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCI initiation capability
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. C.1 --------------NOTE S-------------
- 1. Only applicable in MODES 1, 2, and 3. 2. Only applicable for Functions 1.c, 1.d, 1.e, 1.f, 2.c, 2.d, 2.e, 2.i, 2.j, 2.l, and 2.m. -------------------------------------
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
AND C.2 Restore channel to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for feature(s) in both divisions 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-3 Amendment No.
146 , X XX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. D.1 ---------------NOTE--------------
Only applicable if HPCI pump suction is not aligned to the suppression pool.
Declare HPCI System inoperable.
AND D.2.1 Place channel in trip.
OR D.2.2 Align the HPCI pump suction to the suppression pool.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of HPCI initiation capability
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours E. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. E.1 --------------NOTE S-------------
- 1. Only applicable in MODES 1, 2, and 3. 2. Only applicable for Function 2.g.
Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
AND E.2 Restore channel to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of initiation capability for subsystems in both divisions 7 days ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-4 Amendment No.
146 CTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. F.1 Declare Automatic Depressurization System (ADS) valves inoperable.
AND F.2 Place channel in trip.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems
96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable AND 8 days G. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. G.1 Declare ADS valves inoperable.
AND G.2 Restore channel to OPERABLE status.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of ADS initiation capability in both trip systems 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from discovery of inoperable channel concurrent with HPCI or RCIC inoperable AND 8 days H. Required Action and associated Completion Time of Condition B, C, D, E, F, or G not met.
H.1 Declare associated supported feature(s) inoperable.
Immediately
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-5 Amendment No.
146, 151 SURVEILLANCE REQUIREMENTS
NOTES----------------------------------------------------------
- 1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c and 3.f; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c and 3.f provided the associated Function or the redundant Function maintains ECCS initiation capability.
SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.5.1.3 Calibrate the trip unit.
92 days SR 3.3.5.1.4 Perform CHANNEL CALIBRATION.
92 days SR 3.3.5.1.5 Perform CHANNEL FUNCTIONAL TEST.
12 months SR 3.3.5.1.6 Perform CHANNEL CALIBRATION.
12 months SR 3.3.5.1.7 Perform CHANNEL CALIBRATION.
24 months SR 3.3.5.1.8 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months SR 3.3.5.1.9 Perform CHANNEL FUNCTIONAL TEST.
24 months ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-6 Amendment No.
146, 151, 170 , 176, XXX Table 3.3.5.1-1 (page 1 of 6) Emergency Core Cooling System Instrumentation
FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1
SURVEILLANCE REQUIREMENTS
ALLOWABLE VALUE 1. Core Spray System
- a. Reactor Vessel Water Level - Low Low 1, 2, 3 , 4(a), 5(a) 4 (ab) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Drywell Pressure - High 1, 2, 3 4 (ab) B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig c. Reactor Steam Dome Pressure -
Low (Injection Permissive) 1, 2, 3 2 C SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 397 psig and 440 psig 4(a), 5(a) 2 B SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d) SR 3.3.5.1.8 397 psig and 440 psig d. Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 1, 2, 3 4(a), 5 (a) 2 2 C B SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d) SR 3.3.5.1.8 397 psig 397 psig e. Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5 (a) 2 2 C B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes 18 minutes (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown." (ab) Also required to initiate the associated emergency diesel generator (EDG).
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as
-found tolerance and the as
-left tolerance are specified in the Technical Requirements Manual (TRM).
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-7 Amendment No.
146, XXX Table 3.3.5.1-1 (page 2 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System
- f. Core Spray Pump Start - Time Delay Relay 1, 2, 3 4(a), 5(a) 1 per pump C SR 3.3.5.1.7 SR 3.3.5.1.8 15.86 seconds 2. Low Pressure Coolant Injection (LPCI) System
- a. Reactor Vessel Water Level - Low Low 1, 2, 3, 4(a), 5(a) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Drywell Pressure - High 1, 2, 3 4 B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig c. Reactor Steam Dome Pressure - Low (Injection Permissive) 1, 2, 3 2 C SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 397 psig and 440 psig 4(a), 5(a) 2 B SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d) SR 3.3.5.1.8 397 psig and 440 psig d. Reactor Steam Dome Pressure Permissive - Low (Pump Permissive) 1, 2, 3 2 C SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 397 psig 4(a), 5(a) 2 B SR 3.3.5.1.2 SR 3.3.5.1.4(c)(d) SR 3.3.5.1.8 397 psig (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as
-found tolerance and the as
-left tolerance are specified in the TRM.
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-8 Correction letter of 10/12/06 Amendment No. 146, 149, 151, 161, 170 176, XXX Table 3.3.5.1-1 (page 3 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System
- e. Reactor Steam Dome Pressure Permissive - Bypass Timer (Pump Permissive) 1, 2, 3 4(a), 5(a) 2 2 C B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.7 SR 3.3.5.1.8 18 minutes
18 minutes f. Low Pressure Coolant Injection Pump Start - Time Delay Relay 1, 2, 3, 4(a), 5(a) 4 per pump B SR 3.3.5.1.7 SR 3.3.5.1.8 Pumps A, B 5.33 seconds Pumps C, D 10.59 seconds g. Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2, 3, 4(a), 5(a) 1 per pump E SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 360 gpm and 745 gpm h. Reactor Steam Dome Pressure -
Low (Break Detection) 1, 2, 3 4 B SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 873.6 psig and 923.4 psig i. Recirculation Pump Differential Pressure
- High (Break Detection) 1, 2, 3 4 per pump C SR 3.3.5.1.2 SR 3.3.5.1.7 SR 3.3.5.1.8 63.5 inches wc j. Recirculation Riser Differential Pressure - High (Break Detection) 1, 2, 3 4 C SR 3.3.5.1.2 SR 3.3.5.1.7 (bc)(cd) SR 3.3.5.1.8 100.0 inches wc (a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
(bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as
-found tolerance and the as
-left tolerance are specified in the TRM.
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-9 Amendment No.
146, 149, 151, 161, XXX Table 3.3.5.1-1 (page 4 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2. LPCI System
- k. Recirculation Steam Dome Pressure - Time Delay Relay (Break Detection) 1, 2, 3 2 B SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 2.97 seconds l. Recirculation Pump Differential Pressure - Time Delay Relay (Break Detection) 1, 2, 3 2 C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds m. Recirculation Riser Differential Pressure
- Time Delay Relay (Break Detection) 1, 2, 3 2 C SR 3.3.5.1.7 SR 3.3.5.1.8 SR 3.3.5.1.9 0.75 seconds 3. High Pressure Coolant Injection (HPCI) System
- a. Reactor Vessel Water Level - Low Low 1, 2 (de), 3 (de) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Drywell Pressure - High 1, 2 (de), 3 (de) 4 B SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.8 2 psig c. Reactor Vessel Water Level - High 1, 2 (de), 3 (de) 2 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 48 inches d. Condensate Storage Tank Level
- Low 1, 2 (de), 3 (de) 2 D SR 3.3.5.1.7 SR 3.3.5.1.8 29.3 inches e. Suppression Pool Water Level - High 1, 2 (de), 3 (de) 2 D SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 3.0 inches f. High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 1, 2 (de), 3 (de) 1 E SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.8 362 gpm and 849 gpm (de) With reactor steam dome pressure >
150 psig.
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-10 Amendment No.
146, XXX Table 3.3.5.1-1 (page 5 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4. Automatic Depressurization System (ADS) Trip System A a. Reactor Vessel Water Level - Low Low 1, 2 (de), 3 (de) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Automatic Depressurization System Initiation Timer 1, 2 (de), 3 (de) 1 G SR 3.3.5.1.7 SR 3.3.5.1.8 120 seconds c. Core Spray Pump Discharge Pressure - High 1, 2 (de), 3 (de) 2 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 75 psig and 125 psig d. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2 (de), 3 (de) 4 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 75 psig and 125 psig 5. ADS Trip System B a. Reactor Vessel Water Level - Low Low 1, 2 (de), 3 (de) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.7 SR 3.3.5.1.8 -48 inches b. Automatic Depressurization System Initiation Timer 1, 2 (de), 3 (de) 1 G SR 3.3.5.1.7 SR 3.3.5.1.8 120 seconds (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as
-found tolerance and the as
-left tolerance are specified in the TRM.
(de) With reactor steam dome pressure >
150 psig.
ECCS Instrumentation 3.3.5.1 Monticello 3.3.5.1-11 Amendment No.
146, XXX Table 3.3.5.1-1 (page 6 of 6) Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. ADS Trip System B c. Core Spray Pump Discharge Pressure - High 1, 2 (de), 3 (de) 2 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 75 psig and 125 psig d. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2 (de), 3 (de) 4 G SR 3.3.5.1.2 SR 3.3.5.1.4 (bc)(c d) SR 3.3.5.1.8 75 psig and 125 psig (bc) If the as-found channel setpoint is conservative with respect to the Allowable Value but outside its predefined as-found tolerance, then the channel shall be evaluated to verify that it is functioning as required before returning the channel to service.
(cd) The instrument channel setpoint shall be reset to a value that is within the as
-left tolerance of the nominal trip setpoint; otherwise, the channel shall be declared inoperable. The nominal trip setpoint and the methodology used to determine the as
-found tolerance and the as
-left tolerance are specified in the TRM.
(de) With reactor steam dome pressure >
150 psig.
RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-1 Amendment No.
XXX 3.3 INSTRUMENTATION
3.3.5.3 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.3 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.3-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.5.3-1. ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
A.1 Enter the Condition referenced in Table 3.3.5.3-1 for the channel. Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.3-1. B.1 Declare associated penetration flow path(s) incapable of automatic isolation.
AND B.2 Calculate DRAIN TIME. Immediately
Immediately C. As required by Required Action A.1 and referenced in Table 3.3.5.3-1. C.1 Place channel in trip.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> D. As required by Required Action A.1 and referenced in Table 3.3.5.3-1. D.1 Restore channel to OPERABLE status.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-2 Amendment No.
XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and associated Completion Time of Condition C or D not met. E.1 Declare associated low pressure ECCS injection/spray subsystem inoperable.
Immediately
SURVEILLANCE REQUIREMENTS
NOTE-----------------------------------------------------------
Refer to Table 3.3.5.3-1 to determine which SRs apply for each ECCS Function.
SURVEILLANCE FREQUENCY SR 3.3.5.3.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.3.2 Perform CHANNEL FUNCTIONAL TEST.
92 days RPV Water Inventory Control Instrumentation 3.3.5.3 Monticello 3.3.5.3-3 Amendment No.
XXX Table 3.3.5.3-1 (page 1 of 1) RPV Water Inventory Control Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Core Spray System
- a. Reactor Steam Dome Pressure - Low (Injection Permissive) 4, 5 2 C SR 3.3.5.3.2 397 psig and 440psig 2. Low Pressure Coolant Injection (LPCI) System a. Reactor Steam Dome Pressure -
Low (Injection Permissive) 4, 5 2 C SR 3.3.5.3.2 397 psig and 440 psig b. Low Pressure Coolant Injection Pump Discharge Flow - Low (Bypass) 4, 5 1 per pump(a) D SR 3.3.5.3.2 360 gpm and 745 gpm 3. RHR System Isolation
- a. Reactor Vessel Water Level - Low (b) 2 B SR 3.3.5.3.1 SR 3.3.5.3.2 7 inches 4. Reactor Water Cleanup (RWCU) System Isolation a. Reactor Vessel Water Level - Low Low (b) 2 B SR 3.3.5.3.1 SR 3.3.5.3.2 -48 inches (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, "Reactor Pressure Vessel Water Inventory Control." (b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-1 Amendment No.
146 XXX 3.3 INSTRUMENTATION
3.3.6.1 Primary Containment Isolation Instrumentation
LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.6.1-1.
ACTIONS -----------------------------------------------------------NOTES----------------------------------------------------------
- 1. Penetration flow paths may be unisolated intermittently under administrative controls.
- 2. Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required channels inoperable.
A.1 Place channel in trip.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.a, 2.b, 5.c, 6.b, 7.a, and 7.b B. One or more Functions with primary containment isolation capability not maintained.
B.1 Restore primary containment isolation capability.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Required Action and associated Completion Time of Condition A or B not met. C.1 Enter the Condition referenced in Table 3.3.6.1-1 for the channel. Immediately
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-2 Amendment No.
146 XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. D.1 Isolate associated main steam line (MSL).
OR D.2.1 Be in MODE
- 3. AND D.2.2 Be in MODE
- 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. E.1 Be in MODE
- 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> F. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. F.1 Isolate the affected penetration flow path(s).
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> G. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. G.1 Isolate the affected penetration flow path(s).
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> H. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. H.1 Declare associated standby liquid control (SLC) subsystem inoperable.
OR H.2 Isolate the Reactor Water Cleanup System.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-3 Amendment No.
146 XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME I. As required by Required Action C.1 and referenced in Table 3.3.6.1-1. I.1 Initiate action to restore channel to OPERABLE status. OR I.2 Initiate action to isolate the Residual Heat Removal (RHR) Shutdown Cooling System. Immediately
Immediately
SURVEILLANCE REQUIREMENTS
NOTES----------------------------------------------------------
- 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains primary containment isolation capability.
SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.6.1.3 Calibrate the trip unit.
92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION.
92 days Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-4 Amendment No. 146 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
24 months SR 3.3.6.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-5 Amendment No.
146 , 176 Table 3.3.6.1-1 (page 1 of 3) Primary Containment Isolation Instrumentation
FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1
SURVEILLANCE REQUIREMENTS
ALLOWABLE VALUE 1. Main Steam Line Isolation a. Reactor Vessel Water Level - Low Low 1, 2, 3 2 D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 -48 inches b. Main Steam Line Pressure - Low 1 2 E SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 815 psig c. Main Steam Line Flow - High 1, 2, 3 2 per MSL D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 116.9% rated steam flow
- d. Main Steam Line Tunnel Temperature
- High 1, 2, 3 2 per trip string D SR 3.3.6.1.5 SR 3.3.6.1.6 209F 2. Primary Containment Isolation a. Reactor Vessel Water Level - Low 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches b. Drywell Pressure - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig 3. High Pressure Coolant Injection (HPCI) System Isolation a. HPCI Steam Line Flow - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 300,000 lb/hour with 5.58 second time delay
Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-6 Amendment No.
146 Table 3.3.6.1-1 (page 2 of 3) Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 3. HPCI System Isolation
- b. HPCI Steam Supply Line Pressure - Low 1, 2, 3 4 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 95.5 psig c. HPCI Steam Line Area Temperature - High 1, 2, 3 16 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196F 4. Reactor Core Isolation Cooling (RCIC) System Isolation a. RCIC Steam Line Flow - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 45,903 lb/hour with 7.16 second time delay
- b. RCIC Steam Supply Line Pressure - Low 1, 2, 3 4 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 54 psig c. RCIC Steam Line Area Temperature - High 1, 2, 3 16 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 196F 5. Reactor Water Cleanup (RWCU) System Isolation a. RWCU Flow - High 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 500 gpm with 11.4 second time delay
- b. RWCU Room Temperature - High 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 188F c. Drywell Pressure - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig Primary Containment Isolation Instrumentation 3.3.6.1 Monticello 3.3.6.1-7 Amendment No.
146 , 164, XXX Table 3.3.6.1-1 (page 3 of 3) Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.1
SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 5. RWCU System Isolation
- d. SLC System Initiation 1, 2, 3 1 H SR 3.3.6.1.6 NA e. Reactor Vessel Water Level - Low Low 1, 2, 3 2 F SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 -48 inches 6. Shutdown Cooling System Isolation
- a. Reactor Steam Dome Pressure - High 1, 2, 3 2 F SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 81.8 psig b. Reactor Vessel Water Level - Low 3, 4, 5 2(a) I SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches 7. Traversing Incore Probe System Isolation
- a. Reactor Vessel Water Level - Low 1, 2, 3 2 G SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.5 SR 3.3.6.1.6 7 inches b. Drywell Pressure -
High 1, 2, 3 2 G SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 2.0 psig (a) Only one channel per trip system, with an isolation signal available to one shutdown cooling supply isolation valve, is required in MODES 4 and 5, provided RHR Shutdown Cooling System integrity is maintained.
Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-1 Amendment No. 146
3.3 INSTRUMENTATION
3.3.6.2 Secondary Containment Isolation Instrumentation
LCO 3.3.6.2 The secondary containment isolation instrumentation for each Function in Table 3.3.6.2-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.6.2
-1.
ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
A.1 Place channel in trip.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for Functions 1 and 2 AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 1 and 2 B. One or more Functions with secondary containment isolation capability not maintained.
B.1 Restore secondary containment isolation capability.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. Required Action and associated Completion Time not met.
C.1.1 Isolate the associated penetration flow path(s).
OR C.1.2 Declare associated secondary containment isolation valves inoperable.
AND 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-2 Amendment No. 146 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.2.1 Place the associated standby gas treatment (SGT) subsystem in operation.
OR C.2.2 Declare associated SGT subsystem inoperable.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> SURVEILLANCE REQUIREMENTS
NOTES----------------------------------------------------------
- 1. Refer to Table 3.3.6.2-1 to determine which SRs apply for each Secondary Containment Isolation Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains secondary containment isolation capability.
SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.2.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.6.2.3 Calibrate the trip unit.
92 days SR 3.3.6.2.4 Perform CHANNEL CALIBRATION.
92 days SR 3.3.6.2.5 Perform CHANNEL CALIBRATION.
24 months SR 3.3.6.2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months Secondary Containment Isolation Instrumentation 3.3.6.2 Monticello 3.3.6.2-3 Amendment No.
146, XXX Table 3.3.6.2-1 (page 1 of 1) Secondary Containment Isolation Instrumentation
FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS
ALLOWABLE VALUE 1. Reactor Vessel Water Level - Low Low 1, 2, 3, (a) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6 -48 inches 2. Drywell Pressure - High 1, 2, 3 2 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 2 psig 3. Reactor Building Ventilation Exhaust Radiation - High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr 4. Refueling Floor Radiation - High 1, 2, 3, (a), (b) 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6 100 mR/hr (a) During operations with a potential for draining the reactor vessel.
(ab) During movement of recently irradiated fuel assemblies in secondary containment.
CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-1 Amendment No.
146 148 3.3 INSTRUMENTATION
3.3.7.1 Control Room Emergency Filtration (CREF) System Instrumentation LCO 3.3.7.1 The CREF System instrumentation for each Function in Table 3.3.7.1
-1 shall be OPERABLE. APPLICABILITY:
According to Table 3.3.7.1-1 ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable.
B. Required Action and associated Completion Time not met.
A.1 Declare associated CREF subsystem inoperable.
AND A.2 Place channel in trip.
B.1 Place the associated CREF subsystem in the pressurization mode of operation.
OR B.2 Declare associated CREF subsystem inoperable.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from discovery of loss of CREF initiation capability in both trip systems
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 1 hour 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-2 Amendment No.
146 148
SURVEILLANCE REQUIREMENTS
NOTE S----------------------------------------------------------
- 1. Refer to Table 3.3.7.1
-1 to determine which SRs apply for each CREF System Function.
- 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains CREF System initiation capability.
SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST.
92 days SR 3.3.7.1.3 Calibrate the trip unit.
92 days SR 3.3.7.1.4 Perform CHANNEL CALIBRATION.
92 days SR 3.3.7.1.5 Perform CHANNEL CALIBRATION.
24 months SR 3.3.7.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
24 months CREF System Instrumentation 3.3.7.1 Monticello 3.3.7.1-3 Amendment No.
146 , 148, XXX Table 3.3.7.1
-1 (Page 1 of 1)
Control Room Emergency Filtration System Instrumentation APPLICABLE MODES OR REQUIRED OTHER CHANNELS SPECIFIED PER TRIP SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM REQUIREMENTS VALUE 1. Reactor Vessel Water 1, 2, 3, (a) 2 SR 3.3.7.1.1
- 48 inches Level - Low Low SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.5 SR 3.3.7.1.6
- 2. Drywell Pressure - 1, 2, 3 2 SR 3.3.7.1.2 2 psig High SR 3.3.7.1.4 SR 3.3.7.1.6
- 3. Reactor Building 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Ventilation Exhaust SR 3.3.7.1.2 Radiation - High SR 3.3.7.1.4 SR 3.3.7.1.6
- 4. Refueling Floor 1, 2, 3, (a), (b) 2 SR 3.3.7.1.1 100 mR/hr Radiation - High SR 3.3.7.1.2 SR 3.3.7.1.4 SR 3.3.7.1.6 (a) During operations with a potential for draining the reactor vessel.
(b)(a) During movement of recently irradiated fuel assemblies in the secondary containment.
ECCS - Operating 3.5.1 Monticello 3.5.1-1 Amendment No.
146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of three safety/relief valves shall be OPERABLE.
NOTE--------------------------------------------
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) shutdown cooling supply isolation interlock in MODE 3, if capable of being manually realigned and not otherwise inoperable.
APPLICABILITY:
MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure 150 psig. ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A. One LPCI pump inoperable.
A.1 Restore LPCI pump to OPERABLE status.
30 days B. One LPCI subsystem inoperable for reasons other than Condition A.
OR One Core Spray subsystem inoperable.
B.1 Restore low pressure ECCS injection/spray subsystem to OPERABLE status. 7 days ECCS - Operating 3.5.1 Monticello 3.5.1-2 Amendment No.
146, 162 , 184 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. One LPCI pump in both LPCI subsystems inoperable.
C.1 Restore one LPCI pump to OPERABLE status.
7 days D. Two LPCI subsystems inoperable for reasons other than Condition C or G. D.1 Restore one LPCI subsystem to OPERABLE status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> E. One Core Spray subsystem inoperable.
AND One LPCI subsystem inoperable.
OR One or two LPCI pump(s) inoperable.
E.1 Restore Core Spray subsystem to OPERABLE status. OR E.2 Restore LPCI subsystem to OPERABLE status.
OR E.3 Restore LPCI pump(s) to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met.
F.1 Be in MODE
- 3. AND F.2 Be in MODE
- 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours G. Two LPCI subsystems inoperable due to open RHR intertie return line isolation valve(s).
G.1 Isolate the RHR intertie line. 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> ECCS - Operating 3.5.1 Monticello 3.5.1-3 Amendment No. 146, 162, 176 , 184 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and associated Completion Time of Condition G not met. H.1 Be in MODE
- 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> I. HPCI System inoperable.
I.1 Verify by administrative means RCIC System is OPERABLE. AND I.2 Restore HPCI System to OPERABLE status.
Immediately
14 days J. HPCI System inoperable.
AND Condition A, B, or C entered. J.1 Restore HPCI System to OPERABLE status.
OR J.2 Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours K. One ADS valve inoperable.
K.1 Restore ADS valve to OPERABLE status.
14 days ECCS - Operating 3.5.1 Monticello 3.5.1-4 Amendment No. 146, 162, 176 , 184 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME L. Required Action and associated Completion Time of Condition I, J, or K not met.
OR One ADS valve inoperable and Condition A, B, C, D, or G entered. OR Two or more ADS valves inoperable.
OR HPCI System inoperable and Condition D, E, or G entered. L.1 Be in MODE
- 3. AND L.2 Reduce reactor steam dome pressure to 150 psig. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> M. Two or more low pressure ECCS injection/spray subsystems inoperable for reasons other than Condition C, D, E, or G. OR HPCI System and one or more ADS valves inoperable.
M.1 Enter LCO 3.0.3. Immediately
ECCS - Operating 3.5.1 Monticello 3.5.1-5 Amendment No.
14 6, 15 5 , 162 , 189, 190 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water. 31 days SR 3.5.1.2 -------------------------------NOTE------------------------------ Not required to be met for system vent flow paths opened under administrative control. ---------------------------------------------------------------------
Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
31 days SR 3.5.1.3 Verify ADS pneumatic pressure is as follows for each required ADS pneumatic supply:
- a. S/RV Accumulator Bank header pressure 88.3 psig; and
- b. Alternate Nitrogen System pressure is 1060 psig. 31 days SR 3.5.1.4 -------------------------------NOTE------------------------------
Only required to be met in MODE 1.
Verify the RHR System intertie return line isolation valves are closed.
31 days SR 3.5.1.5 Verify correct breaker alignment to the LPCI swing bus. 31 days SR 3.5.1.6 Verify each recirculation pump discharge valve cycles through one complete cycle of full travel or is de-energized in the closed position.
In accordance with the Inservice Testing Program
ECCS - Operating 3.5.1 Monticello 3.5.1-6 Amendment No.
14 6 , 162 , 167 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.7 Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor to containment pressure.
System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of
Core Spray 2835 gpm 1 130 psi LPCI 3870 gpm 1 20 psi In accordance with the Inservice Testing Program SR 3.5.1.8 -------------------------------NOTE------------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor steam dome pressure 1025.3 psig and 950 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.
In accordance with the Inservice Testing Program SR 3.5.1.9 -------------------------------NOTE------------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure 165 psig, the HPCI pump can develop a flow rate 2700 gpm against a system head corresponding to reactor pressure.
24 months ECCS - Operating 3.5.1 Monticello 3.5.1-7 Amendment No.
146, 162, 168 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.1.10 -------------------------------NOTE------------------------------
Vessel injection/spray may be excluded.
Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.
24 months SR 3.5.1.11 -------------------------------NOTE------------------------------
Valve actuation may be excluded.
Verify the ADS actuates on an actual or simulated automatic initiation signal.
24 months SR 3.5.1.12 -------------------------------NOTE------------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam flow is adequate to perform the test.
Verify each ADS valve is capable of being opened.
In accordance with the Inservice Testing Program SR 3.5.1.13 Verify automatic transfer capability of the LPCI swing bus power supply from the normal source to the backup source.
24 months ECCS - Shutdown 3.5.2 Monticello 3.5.2-1 Amendment No.
146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.2 RPV Water Inventory Control ECCS - Shutdown LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. AND OneTwo low pressure ECCS injection/spray subsystem s shall be OPERABLE. ---------------------------------------------NOTE--------------------------------------------
A One Low Pressure Coolant Injection (LPCI) subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
APPLICABILITY:
MODE 4 , MODE and 5, except with the spent fuel storage pool gates removed and water level 21 ft 11 inches over the top of the reactor pressure vessel flange.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One r Required ECCS injection/spray subsystem inoperable.
A.1 Restore required ECCS injection/spray subsystem to OPERABLE status.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Action and associated Completion Time of Condition A not met. B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power. Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
Immediately C. DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.1 Verify secondary 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> s ECCS - Shutdown 3.5.2 ACTIONS (continued)
Monticello 3.5.2-2 Amendment No.
146, XXX 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. C. Two required ECCS injection/spray subsystems inoperable.
containment boundary is capable of being established in less than the DRAIN TIME. AND C.2 Verify each secondary containment penetration flow path is capable of being isolated in less than the DRAIN TIME. AND C.3 Verify one standby gas treatment subsystem is capable of being placed in operation in less than the DRAIN TIME. C.1 Initiate action to suspend OPDRVs. AND C.2 Restore one required ECCS injection/spray subsystem to OPERABLE status. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D. DRAIN TIME < 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. D.1 -----------
NOTE ---------------
Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power. ------------------------------------
Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water Immediately
ECCS - Shutdown 3.5.2 ACTIONS (continued)
Monticello 3.5.2-3 Amendment No.
146, XXX AND D.2 Initiate action to establish secondary containment boundary. AND D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room. AND D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.
Immediately Immediately Immediately E. Required Action and associated Completion Time of Condition C or D not met. OR DRAIN TIME < 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. E.1 Initiate action to restore DRAIN TIME to 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. Immediately
ECCS - Shutdown 3.5.2 ACTIONS (continued)
Monticello 3.5.2-4 Amendment No.
146, XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and associated Completion Time not met.
D.1Initiate action to restore secondary containment to OPERABLE status. AND D.2 Initiate action to restore one standby gas treatment subsystem to OPERABLE status. AND D.3 Initiate action to restore isolation capability in each required secondary containment penetration flow path not isolated.
Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify DRAIN TIME 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.5.2.21 Verify, for each a required ECCS injection/spray subsystem, the:
- a. Suppression pool water level is -3 ft; or b. ---------------------------NOTE---------------------------- Only one required ECCS injection/spray subsystem may take credit for this option during OPDRVs. ----------------------------------------------------------------
Condensate storage tank(s) water level is 7 ft for one tank operation and 4 ft for two tank operation.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> ECCS - Shutdown 3.5.2 ACTIONS (continued)
Monticello 3.5.2-5 Amendment No.
146, XXX SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for the required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
31 days ECCS - Shutdown 3.5.2 Monticello 3.5.2-6 Amendment No.
146, 167 , 189, 194, XXX SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.5.2.2 Verify, for each required ECCS injection/spray subsystem, locations susceptible to gas accumulation are sufficiently filled with water.
31 days SR 3.5.2.43 -------------------------------NOTE------------------------------
Not required to be met for system vent flow paths opened under administrative control. ---------------------------------------------------------------------
Verify for each the required ECCS injection/spray subsystem , each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
31 days SR 3.5.2.54 Operate the required ECCS injection/spray subsystem through the recirculation line for 10 minutes.
Verify each required ECCS pump develops the specified flow rate against a system head corresponding to the specified reactor to containment pressure.
System Head Corresponding to a Reactor to No. of Containment System Flow Rate Pumps Pressure of Core Spray 2835 gpm 1 130 psi LPCI 3870 gpm 1 20 psi In accordance with the INSERVICE TESTING PROGRAM 92 days SR 3.5.2.6 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.
24 months SR 3.5.2.75 -------------------------------NOTE------------------------------
Vessel injection/spray may be excluded.
Verify the each required ECCS injection/spray
ECCS - Shutdown 3.5.2 Monticello 3.5.2-7 Amendment No.
146, 167 , 189, 194, XXX SURVEILLANCE FREQUENCY subsystem operates actuates on a manual an actual or simulated automatic initiation signal.
24 months RCIC System
3.5.3 Monticello
3.5.3-1 Amendment No.
146, XXX 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) 3.5.3 RCIC System
LCO 3.5.3 The RCIC System shall be OPERABLE.
APPLICABILITY:
MODE 1, MODES 2 and 3 with reactor steam dome pressure >
150 psig.
ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
LCO 3.0.4.b is not applicable to the RCIC System.
CONDITION REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.
A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE. AND A.2 Restore RCIC System to OPERABLE status.
Immediately
14 days B. Required Action and associated Completion Time not met.
B.1 Be in MODE
- 3. AND B.2 Reduce reactor steam dome pressure to 150 psig. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
RCIC System
3.5.3 Monticello
3.5.3-2 Amendment No.
146 , 189 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 -------------------------------NOTE------------------------------
Not required to be met for system vent flow paths opened under administrative control. ---------------------------------------------------------------------
Verify each RCIC System manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
31 days SR 3.5.3.2 -------------------------------NOTE------------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure 1025.3 psig and 950 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.
In accordance with the Inservice Testing Program SR 3.5.3.3 -------------------------------NOTE------------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure 165 psig, the RCIC pump can develop a flow rate 400 gpm against a system head corresponding to reactor pressure.
24 months SR 3.5.3.4 -------------------------------NOTE------------------------------
Vessel injection may be excluded. ---------------------------------------------------------------------
Verify the RCIC System actuates on an actual or simulated automatic initiation signal.
24 months SR 3.5.3.5 Verify the RCIC System locations susceptible to gas accumulation are sufficiently filled with water.
31 days PCIVs 3.6.1.3 Monticello 3.6.1.3-1 Amendment No.
146 148 3.6 CONTAINMENT SYSTEMS
3.6.1.3 Primary Containment Isolation Valves (PCIVs)
LCO 3.6.1.3 Each PCIV, except reactor building-to-suppression chamber vacuum breakers, shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.6.1, "Primary Containment Isolation Instrumentation." ACTIONS -----------------------------------------------------------NOTES----------------------------------------------------------
- 1. Penetration flow paths may be unisolated intermittently under administrative controls. 2. Separate Condition entry is allowed for each penetration flow path.
- 3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.
- 4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment," when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria. -------------------------------------------------------------------------------------------------------------------------------
CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------
Only applicable to penetration flow paths with two PCIVs.
One or more penetration flow paths with one PCIV inoperable for reasons other than Condition D or E. A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured. AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except for main steam line
AND 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for main steam line
PCIVs 3.6.1.3 Monticello 3.6.1.3-2 Amendment No. 146 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTES-------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected penetration flow path is isolated.
Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de
-
inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment
PCIVs 3.6.1.3 Monticello 3.6.1.3-3 Amendment No.
146 148 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------
Only applicable to penetration flow paths with two PCIVs.
One or more penetration flow paths with two PCIVs inoperable for reasons other than Condition D or E. B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> C. ------------NOTE------------
Only applicable to penetration flow paths with only one PCIV.
One or more penetration flow paths with one PCIV inoperable.
C.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> except for excess flow check valves (EFCVs) and penetrations with a closed system AND 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for EFCVs and penetrations with a closed system
PCIVs 3.6.1.3 Monticello 3.6.1.3-4 Amendment No.
146 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.2 --------------NOTES-------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected penetration flow path is isolated.
Once per 31 days for isolation devices outside primary containment AND Prior to entering MODE 2 or 3 from MODE 4 if primary containment was
de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment
PCIVs 3.6.1.3 Monticello 3.6.1.3-5 Amendment No.
146 148 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration flow paths with one or more 18 inch primary containment purge and vent valves not within purge and vent valve leakage limits.
D.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
AND D.2 --------------NOTES-------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected penetration flow path is isolated. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Once per 31 days for isolation devices outside containment E. One or more MSIVs with leakage rate not within limits. E.1 Restore leakage rate to within limits. 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> F. Required Action and associated Completion Time of Condition A, B, C, or D not met in MODE 1, 2, or 3.
F.1 Be in MODE
- 3. AND F.2 Be in MODE
- 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
PCIVs 3.6.1.3 Monticello 3.6.1.3-6 Amendment No.
146 , 148, XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and associated Completion Time of Condition A or B not met for PCIV(s) required to be OPERABLE during MODE 4 or 5. G.1 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
OR G.12 Initiate action to restore valve(s) to OPERABLE status. Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 ------------------------------NOTE------------------------------
Not required to be met when the 18 inch primary containment purge and vent valves are open for inerting, de
-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.
Verify each 18 inch primary containment purge and vent valve is closed.
31 days PCIVs 3.6.1.3 Monticello 3.6.1.3-7 Amendment No.
146 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.2 ------------------------------NOTES-----------------------------
- 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
- 2. Not required to be met for PCIVs that are open under administrative controls.
Verify each primary containment isolation manual valve and blind flange that is located outside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.
31 days SR 3.6.1.3.3
NOTES-----------------------------
- 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
- 2. Not required to be met for PCIVs that are open under administrative controls.
Verify each primary containment manual isolation valve and blind flange that is located inside primary containment and not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.
Prior to entering MODE 2 or 3 from MODE 4 if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.4 Verify continuity of the traversing incore probe (TIP) shear isolation valve explosive charge.
31 days SR 3.6.1.3.5 Verify the isolation time of each power operated automatic PCIV, except for MSIVs, is within limits.
24 months PCIVs 3.6.1.3 Monticello 3.6.1.3-8 Amendment No. 146 148 , 176 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3.6.1.3.6 Verify the isolation time of each MSIV is 3 seconds and 9.9 seconds. 24 months SR 3.6.1.3.7 Verify each automatic PCIV actuates to the isolation position on an actual or simulated isolation signal.
24 months SR 3.6.1.3.8 Verify each reactor instrumentation line EFCV actuates on a simulated instrument line break to restrict flow to 2 gpm. 24 months SR 3.6.1.3.9 Verify each 18 inch primary containment purge and vent valve is blocked to restrict the valve from opening > 40. 24 months SR 3.6.1.3.10 Remove and test the explosive squib from each shear isolation valve of the TIP System.
24 months on a STAGGERED TEST BASIS SR 3.6.1.3.11 Perform leakage rate testing for each 18 inch primary containment purge and vent valve with resilient seals.
In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.12 Verify leakage rate through each MSIV is:
(a) 100 scfh when tested at 44.1 psig (P a); or (b) 75.3 25 psig. In accordance with the Primary Containment Leakage Rate Testing Program SR 3.6.1.3.13 Verify leakage rate through the main steam pathway is: (a) 200 scfh when tested at 44.1 psig (P a); or (b) 150.6 25 psig. In accordance with the Primary Containment Leakage Rate Testing Program
Secondary Containment 3.6.4.1 Monticello 3.6.4.1-1 Amendment No.
146, XXX 3.6 CONTAINMENT SYSTEMS
3.6.4.1 Secondary Containment
LCO 3.6.4.1 The secondary containment shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment inoperable in MODE 1, 2, or 3. A.1 Restore secondary containment to OPERABLE status. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Action and associated Completion Time of Condition A not met. B.1 Be in MODE
- 3. AND B.2 Be in MODE
- 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. C.1 ---------------NOTE--------------
LCO 3.0.3 is not applicable.
Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND C.2 Initiate action to suspend OPDRVs.
Immediately
Immediately
Secondary Containment 3.6.4.1 Monticello 3.6.4.1-2 Amendment No.
146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch of vacuum water gauge.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.
31 days SR 3.6.4.1.3 Verify one secondary containment access door in each access opening is closed.
31 days SR 3.6.4.1.4 Verify the secondary containment can be maintained 0.25 inch of vacuum water gauge for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using one SGT subsystem at a flow rate 4000 cfm. 24 months on a STAGGERED TEST BASIS for each SGT subsystem SCIVs 3.6.4.2 Monticello 3.6.4.2-1 Amendment No.
146, XXX 3.6 CONTAINMENT SYSTEMS
3.6.4.2 Secondary Containment Isolation Valves (SCIVs)
LCO 3.6.4.2 Each SCIV shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS -----------------------------------------------------------
NOTES----------------------------------------------------------
- 1. Penetration flow paths may be unisolated intermittently under administrative controls.
- 2. Separate Condition entry is allowed for each penetration flow path.
- 3. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration flow paths with one SCIV inoperable.
A.1 Isolate the affected penetration flow path by use of at least one closed
and de-activated automatic valve, closed manual valve, or blind flange.
AND 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> SCIVs 3.6.4.2 Monticello 3.6.4.2-2 Amendment No. 146 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A.2 --------------NOTES-------------
- 1. Isolation devices in high radiation areas may be verified by use of administrative means.
- 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of administrative means.
Verify the affected penetration flow path is isolated.
Once per 31 days B. ------------NOTE------------
Only applicable to penetration flow paths with two isolation valves.
One or more penetration flow paths with two SCIVs inoperable.
B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1 Be in MODE
- 3. AND C.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours SCIVs 3.6.4.2 Monticello 3.6.4.2-3 Amendment No.
146, XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. D.1 ---------------NOTE--------------
LCO 3.0.3 is not applicable.
Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND D.2 Initiate action to suspend OPDRVs. Immediately Immediately
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1
NOTES-----------------------------
- 1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.
- 2. Not required to be met for SCIVs that are open under administrative controls.
Verify each secondary containment isolation manual valve and blind flange that is not locked, sealed, or otherwise secured and is required to be closed during accident conditions is closed.
31 days SR 3.6.4.2.2 Verify the isolation time of each power operated, automatic SCIV is within limits.
92 days SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation position on an actual or simulated actuation signal.
24 months SGT System 3.6.4.3 Monticello 3.6.4.3-1 Amendment No.
146, XXX 3.6 CONTAINMENT SYSTEMS
3.6.4.3 Standby Gas Treatment (SGT) System
LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable.
A.1 Restore SGT subsystem to OPERABLE status.
7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3. B.1 Be in MODE
- 3. AND B.2 Be in MODE
- 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------------NOTE-------------------
LCO 3.0.3 is not applicable.
C.1 Place OPERABLE SGT subsystem in operation.
OR C.2.1 Suspend movement of recently irradiated fuel assemblies in secondary containment.
AND Immediately
Immediately
SGT System 3.6.4.3 Monticello 3.6.4.3-2 Amendment No.
146, 181, XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C.2.2 Initiate action to suspend OPDRVs. Immediately D. Two SGT subsystems inoperable in MODE 1, 2, or 3. D.1 Enter LCO 3.0.3. Immediately E. Two SGT subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. E.1 ---------------NOTE--------------
LCO 3.0.3 is not applicable.
Suspend movement of recently irradiated fuel assemblies in secondary containment.
AND E.2 Initiate action to suspend OPDRVs. Immediately Immediately
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 15 continuous minutes. 31 days SR 3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.6.4.3.3 Verify each SGT subsystem actuates on an actual or simulated initiation signal.
24 months CREF System
3.7.4 Monticello
3.7.4-1 Amendment No. 146, 160, 175, XXX 3.7 PLANT SYSTEMS
3.7.4 Control Room Emergency Filtration (CREF) System
LCO 3.7.4 Two CREF subsystems shall be OPERABLE.
NOTE--------------------------------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY:
MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment., During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREF subsystem inoperable for reasons other than Condition B. A.1 Restore CREF subsystem to OPERABLE status.
7 days B. One or more CREF subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3. B.1 Initiate action to implement mitigating actions.
AND B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical and smoke hazards will not exceed limits. AND B.3 Restore CRE boundary to OPERABLE status.
Immediately
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
90 days CREF System
3.7.4 Monticello
3.7.4-2 Amendment No.
146, 160, XXX CREF System
3.7.4 Monticello
3.7.4-3 Amendment No.
146, 160, XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1 Be in MODE
- 3. AND C.2 Be in MODE
- 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours D. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------------NOTE-------------------
LCO 3.0.3 is not applicable.
D.1 Place OPERABLE CREF subsystem in pressurization mode. OR D.2.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND D.2.2 Initiate action to suspend OPDRVs.
Immediately Immediately Immediately E. Two CREF subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.
E.1 Enter LCO 3.0.3. Immediately
CREF System
3.7.4 Monticello
3.7.4-4 Amendment No.
146, 160, 175, 181, XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREF subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. OR One or more CREF subsystems inoperable due to an inoperable CRE boundary during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs
. --------------------NOTE-------------------
LCO 3.0.3 is not applicable.
F.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND F.2 Initiate action to suspend OPDRVs. Immediately Immediately
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each CREF subsystem for 15 continuous minutes. 31 days SR 3.7.4.2 Perform required CREF filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP SR 3.7.4.3 Verify each CREF subsystem actuates on an actual or simulated initiation signal.
24 months SR 3.7.4.4 Perform required CRE unfiltered air in
-leakage testing in accordance with the Control Room Envelope Habitability Program.
In accordance with the Control Room Envelope Habitability Program Control Room Ventilation System
3.7.5 Monticello
3.7.5-1 Amendment No.
146, 148, 154, XXX 3.7 PLANT SYSTEMS
3.7.5 Control Room Ventilation System
LCO 3.7.5 Two control room ventilation subsystems shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment,. During operations with a potential for draining the reactor vessel (OPDRVs). ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room ventilation subsystem inoperable.
A.1 Restore control room ventilation subsystem to OPERABLE status.
30 days B. Two control room ventilation subsystems inoperable.
B.1 Verify control room area temperature < 90
°F. AND B.2 Restore one control room ventilation subsystem to OPERABLE status.
Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1 Be in MODE 3.
AND C.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours D. Required Action and associated Completion Time of Condition A not met during movement of irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------------NOTE-------------------
LCO 3.0.3 is not applicable.
D.1 Place OPERABLE control room ventilation subsystem in operation.
Immediately
Control Room Ventilation System
3.7.5 Monticello
3.7.5-2 Amendment No.
146, 148, 154, XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.2.1 Suspend movement of irradiated fuel assemblies in the secondary containment.
AND D.2.2 Initiate action to suspend OPDRVs. Immediately Immediately E. Required Action and associated Completion Time of Condition B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------------NOTE-------------------
LCO 3.0.3 is not applicable.
E.1 Suspend movement of irradiated fuel assemblies in the secondary containment.
AND E.2 Initiate actions to suspend OPDRVs.
Immediately
Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each control room ventilation subsystem has the capability to remove the assumed heat load.
24 months AC Sources - Shutdown 3.8.2 Monticello 3.8.2-1 Amendment No.
146 , 148 , XXX 3.8 ELECTRICAL POWER SYSTEMS
3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:
- a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown;" and
- b. One emergency diesel generator (EDG) capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO
3.8.8. APPLICABILITY
MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One required offsite circuit inoperable.
NOTE-------------------
Enter applicable Condition and Required Actions of LCO 3.8.8, with one required division de
-energized as a result of Condition A. ------------------------------------------------
A.1 Declare affected required feature(s), with no offsite power available, inoperable.
Immediately
AC Sources - Shutdown 3.8.2 Monticello 3.8.2-2 Amendment No.
146 , 148 , XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A.2.1 Suspend CORE ALTERATIONS.
AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs).
AND A.2.34 Initiate action to restore required offsite power circuit to OPERABLE status. Immediately Immediately Immediately Immediately B. One required EDG inoperable.
B.1 Suspend CORE ALTERATIONS.
AND B.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND B.3 Initiate action to suspend OPDRVs. AND B.34 Initiate action to restore required EDG to OPERABLE status.
Immediately
Immediately
Immediately Immediately
AC Sources - Shutdown 3.8.2 Monticello 3.8.2-3 Amendment No. 146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1
NOTES-----------------------------
- 1. The following SRs are not required to be performed:
SR 3.8.1.3, SR 3.8.1.7, and SR 3.8.1.8 through SR 3.8.1.13.
- 2. SR 3.8.1.8 and SR 3.8.1.12 are not required to be met when associated ECCS subsystem(s) are not required to be OPERABLE per LCO 3.5.2, "ECCS - Shutdown." ---------------------------------------------------------------------
For AC sources required to be OPERABLE the SRs of Specification 3.8.1, except SR 3.8.1.6, are applicable.
In accordance with applicable SRs DC Sources - Shutdown 3.8.5 Monticello 3.8.5-1 Amendment No.
146 , 148, XXX 3.8 ELECTRICAL POWER SYSTEMS
3.8.5 DC Sources - Shutdown LCO 3.8.5 Division 1 or Division 2 125 VDC electrical power subsystem shall be OPERABLE to support one division of the DC Electrical Power Distribution System required by LCO 3.8.8, "Distribution Systems - Shutdown."
APPLICABILITY:
MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable.
A.1 Suspend CORE ALTERATIONS.
AND A.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND A.3 Initiate action to suspend operations with a potential for draining the reactor vessel. AND A.34 Initiate action to restore required DC electrical power subsystem to OPERABLE status.
Immediately
Immediately
Immediately Immediately
DC Sources - Shutdown 3.8.5 Monticello 3.8.5-2 Amendment No.
146 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1
NOTE------------------------------
The following SR is not required to be performed:
SR 3.8.4.3. ---------------------------------------------------------------------
For DC sources required to be OPERABLE, the following SRs are applicable:
SR 3.8.4.1, SR 3.8.4.2, and SR 3.8.4.3.
In accordance with applicable SRs Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-1 Amendment No.
146 , 148, XXX 3.8 ELECTRICAL POWER SYSTEMS
3.8.8 Distribution Systems - Shutdown LCO 3.8.8 The necessary portions of the AC and DC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.
APPLICABILITY:
MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
ACTIONS ------------------------------------------------------------NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC or DC electrical power distribution subsystems inoperable.
A.1 Declare associated supported required feature(s) inoperable.
OR A.2.1 Suspend CORE ALTERATIONS.
AND A.2.2 Suspend handling of recently irradiated fuel assemblies in the secondary containment.
AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel. AND Immediately
Immediately Immediately Immediately
Distribution Systems - Shutdown 3.8.8 Monticello 3.8.8-2 Amendment No.
146, XXX ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A.2.34 Initiate actions to restore required AC and DC electrical power distribution subsystems to OPERABLE status. AND A.2.45 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.
Immediately
Immediately
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage to required AC and DC electrical power distribution subsystems.
7 days