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{{#Wiki_filter:TABLE OF CONTENTS JAFNPP i Amendment 287 1.0 USE AND APPLICATION 1.1 Definitions
{{#Wiki_filter:TABLE OF CONTENTS 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) 2.1           SLs ................................................................................................... 2.0-1 2.2           SL Violations ...................................................................................... 2.0-1 3.0       LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .......... 3.0-1 3.0       SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ......................... 3.0-3 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 3.1.4 3.1.5 3.1.6 T
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Control Rod OPERABILITY ............................................................... 3.1.3-1 Control Rod Scram Times .................................................................. 3.1.4-1 Control Rod Scram Accumulators ...................................................... 3.1.5-1 Rod Pattern Control ........................................................................... 3.1.6-1 3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 3.3 AF Standby Liquid Control (SLC) System ................................................ 3.1.7-1 Scram Discharge Volume (SDV) Vent and Drain Valves .................... 3.1.8-1 POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)3.2.1-1 MINIMUM CRITICAL POWER RATIO (MCPR) .................................. 3.2.2-1 LINEAR HEAT GENERATION RATE (LHGR) ................................... 3.2.3-1 INSTRUMENTATION 3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.2                              R Reactor Protection System (RPS) Instrumentation ............................ 3.3.1.1-1 Source Range Monitor (SRM) Instrumentation................................... 3.3.1.2-1 Control Rod Block Instrumentation ..................................................... 3.3.2.1-1 Feedwater and Main Turbine High Water Level Trip Instrumentation ................................................................... 3.3.2.2-1 3.3.3.1 3.3.3.2 3.3.4.1 3.3.5.1 3.3.5.2 3.3.5.23 D
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Post Accident Monitoring (PAM) Instrumentation ............................... 3.3.3.1-1 Remote Shutdown System ................................................................. 3.3.3.2-1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ................................... 3.3.4.1-1 Emergency Core Cooling System (ECCS) Instrumentation ................ 3.3.5.1-1 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation.3.3.5.2-1 Reactor Core Isolation Cooling (RCIC) System Instrumentation .......................................................................... 3.3.5.23-1 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 3.3.7.1       Control Room Emergency Ventilation Air Supply (CREVAS)
..........................
System Instrumentation ............................................................. 3.3.7.1-1 3.3.7.2       Condenser Air Removal Pump Isolation Instrumentation ................... 3.3.7.2-1 3.3.7.3       Emergency Service Water (ESW) System Instrumentation................ 3.3.7.3-1 JAFNPP                                                       i                                           Amendment 287
1.1-1 1.2 Logical Connectors
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1.2-1 1.3 Completion Times
................................
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1.3-1 1.4 Frequency ................................
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1.4-1 2.0 SAFETY LIMITS (SLs) 2.1 SLs ................................
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... 2.0-1 2.2 SL Violations
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2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ..........
3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
.........................
3.0-3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN (SDM)
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3.1.1-1 3.1.2 Reactivity Anomalies
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3.1.2-1 3.1.3 Control Rod OPERABILITY
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3.1.3-1 3.1.4  Control Rod Scram Times
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.. 3.1.4-1 3.1.5  Control Rod Scram Accumulators
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3.1.5-1 3.1.6  Rod Pattern Control
................................
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3.1.6-1 3.1.7 Standby Liquid Control (SLC) System
................................
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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)
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.. 3.2.2-1 3.2.3  LINEAR HEAT GENERATION RATE (LHGR)
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... 3.2.3-1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation
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3.3.1.1-1 3.3.1.2  Source Range Monitor (SRM)
Instrumentation
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... 3.3.1.2-1 3.3.2.1  Control Rod Block Instrumentation
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3.3.2.1-1 3.3.2.2  Feedwater and Main Turbine High Water Level Trip Instrumentation
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... 3.3.2.2-1 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation
...............................
3.3.3.1-1 3.3.3.Remote Shutdown System ................................
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. 3.3.3.2-1 3.3.4.1  Anticipated Transient Without Scram Recirculation Pump Trip (ATWS
-RPT) Instrumentation
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... 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 Pressure Vessel (RPV) Water Inventory Control    -1 3.3.5.2 3  Reactor Core Isolation Cooling (RCIC) System Instrumentation
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3.3.5.2 3-1 3.3.6.1 Primary Containment Isolation Instrumentation
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.. 3.3.6.1-1 3.3.6.2 Secondary Containment Isolation Instrumentation .............................
3.3.6.2-1 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS)
System Instrumentation
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3.3.7.1-1 3.3.7.2 Condenser Air Removal Pump Isolation Instrumentation
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3.3.7.2-1 3.3.7.3 Emergency Service Water (ESW) System Instrumentation
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3.3.7.3-1 TABLE OF CONTENTS JAFNPP i Amendment 287


TABLE OF CONTENTS (continued)
T AF R
D JAFNPP              i  Amendment 287
TABLE OF CONTENTS 3.3        INSTRUMENTATION (continued) 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 3.4        REACTOR COOLANT SYSTEM (RCS) 3.4.1          Recirculation Loops Operating ................................................... 3.4.1-1 3.4.2          Jet Pumps .................................................................................. 3.4.2-1 3.4.3          Safety/Relief Valves (S/RVs) ...................................................... 3.4.3-1 3.4.4          RCS Operational LEAKAGE....................................................... 3.4.4-1 3.4.5          RCS Leakage Detection Instrumentation ................................... 3.4.5-1 3.4.6          RCS Specific Activity .................................................................. 3.4.6-1 3.4.7          Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..................................................... 3.4.7-1 3.4.8          Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ................................................... 3.4.8-1 3.4.9          RCS Pressure and Temperature (P/T) Limits ............................. 3.4.9-1 3.5 3.5.1 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM T
ECCS - Operating ..................................................................... 3.5.1-1 Formatted: Indent: Left: 0", Hanging: 1.08" 3.5.2 3.5.3 3.6 3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 AF RPV Water Inventory ControlECCS - Shutdown........................ 3.5.2-1 RCIC System ............................................................................. 3.5.3-1 CONTAINMENT SYSTEMS Primary Containment ................................................................. 3.6.1.1-1 Primary Containment Air Locks .................................................. 3.6.1.2-1 Primary Containment Isolation Valves (PCIVs) .......................... 3.6.1.3-1 Drywell Pressure ........................................................................ 3.6.1.4-1 Drywell Air Temperature............................................................. 3.6.1.5-1 3.6.1.6 3.6.1.7 3.6.1.8 3.6.1.9 3.6.2.1 R
Reactor Building-to-Suppression Chamber Vacuum Breakers ... 3.6.1.6-1 Suppression Chamber-to-Drywell Vacuum Breakers.................. 3.6.1.7-1 Main Steam Leakage Collection (MSLC) System ....................... 3.6.1.8-1 Residual Heat Removal (RHR) Containment Spray System ....... 3.6.1.9-1 Suppression Pool Average Temperature .................................... 3.6.2.1-1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.3.1 3.6.3.2 3.6.4.1 3.6.4.2 3.6.4.3 D  Suppression Pool Water Level ................................................... 3.6.2.2-1 Residual Heat Removal (RHR) Suppression Pool Cooling ......... 3.6.2.3-1 Drywell-to-Suppression Chamber Differential Pressure .............. 3.6.2.4-1 Primary Containment System Concentration .............................. 3.6.3.1-1 Containment Atmosphere Dilution (CAD) System ...................... 3.6.3.2-1 Secondary Containment ............................................................. 3.6.4.1-1 Secondary Containment Isolation Valves (SCIVs) ...................... 3.6.4.2-1 Standby Gas Treatment (SGT) System ...................................... 3.6.4.3-1 3.7        PLANT SYSTEMS 3.7.1          Residual Heat Removal Service Water (RHRSW) System ......... 3.7.1-1 3.7.2          Emergency Service Water (ESW) System and Ultimate Heat Sink (UMS)................................................................. 3.7.2-1 (continued)
JAFNPP                                                ii                                        Amendment 274
TABLE OF CONTENTS T
AF R
D JAFNPP              ii  Amendment 274
1.1  Definitions (continued)
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 (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 human error), for all penetration flow paths below the TAF except:
: 1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic T
valves that are locked, sealed or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant AF          2.
through the penetration flow paths; Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or R                    3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained D                        c) 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.
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.
(continued)
(continued)
TABLE OF CONTENTS JAFNPP ii Amendment 274 3.3  INSTRUMENTATION  (continued) 3.3.8.1  Loss of Power (LOP) Instrumentation
JAFNPP                                       1.1-2a                            Amendment 315
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........ 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  3.4  REACTOR COOLANT SYSTEM (RCS) 3.4.1  Recirculation Loops Operating
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3.4.1-1 3.4.2  Jet Pumps ................................
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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
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.. 3.4.6-1 3.4.7  Residual Heat Removal (RHR) Shutdown Cooling System  Hot Shutdown
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3.4.7-1 3.4.8  Residual Heat Removal (RHR) Shutdown Cooling System  Cold Shutdown ................................
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3.4.8-1 3.4.9  RCS Pressure and Temperature (P/T) Limits
.............................
3.4.9-1  3.5  EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACT OR CORE    ISOLATION COOLING (RCIC) SYSTEM 3.5.1  ECCS  Operating ................................
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..... 3.5.1-1 3.5.2  RPV Water Inventory Control ECCS  Shutdown ........................
3.5.2-1 3.5.3  RCIC System
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3.5.3-1  3.6  CONTAINMENT SYSTEMS 3.6.1.1  Primary Containment
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. 3.6.1.1-1 3.6.1.2  Primary Containment Air Locks
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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 Pressure
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........ 3.6.1.4-1 3.6.1.5  Drywell Air Temperature
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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
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3.6.1.7-1 3.6.1.8  Main Steam Leakage Collection (MSLC) System
.......................
3.6.1.8-1 3.6.1.9  Residual Heat Removal (RHR) Containment Spray System
....... 3.6.1.9-1 3.6.2.1  Suppression Pool Average Temperature
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.... 3.6.2.1-1 3.6.2.2  Suppression Pool Water Level
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3.6.2.2-1 3.6.2.3  Residual Heat Removal (RHR) Suppression Pool Cooling ......... 3.6.2.3-1 3.6.2.4  Drywell-to-Suppression Chamber Differential Pressure
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3.6.2.4-1 3.6.3.1  Primary Containment System Concentration
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3.6.3.1-1 3.6.3.2  Containment Atmosphere Dilution (CAD) System
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3.6.3.2-1 3.6.4.1  Secondary Containment
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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
......... 3.7.1-1 3.7.2  Emergency Service Water (ESW) System and Ultimate Heat Sink (UMS)
................................
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. 3.7.2-1 (continued)
Formatted: Indent: Left:  0", Hanging:  1.08" TABLE OF CONTENTS JAFNPP ii Amendment 274


JAFNPP 1.1-2a Amendment 315 1.1 Definitions (continued)
ECCS Instrumentation 3.3.5.1 3.3      INSTRUMENTATION 3.3.5.1           Emergency Core Cooling System (ECCS) Instrumentation LCO      3.3.5.1            The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.
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 (TAF) seated in the RPV assuming:  a) The water inventory above the TAF is divided by the limiting drain rate:
APPLICABILITY:                According to Table 3.3.5.1-1.
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 human error), for all penetration flow paths below the TAF except:
ACTIONS
: 1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic valves that are locked, sealed or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - -
: 2. Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or
Separate Condition entry is allowed for each channel.
: 3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in the task, who in continuous communication with the control room, is stationed at the controls, and is capable of closing the penetration flow path isolation device without offsite power.
----------------------------------------------------------------------
c) The penetration flow paths required to be evaluated per paragraph b) are assumed to open instantaneously and are not subsequently isolated, and no water is assumed to be subsequently added to the RPV water inventory; d) No additional draining events occur; and e) Realistic cross-sectional areas and drain rates are used A Bounding DRAIN TIME may be used in lieu of a calculated value. (continued)
CONDITION                              REQUIRED ACTION                            COMPLETION TIME A. One or more channels inoperable.
A.1 T
Enter the Condition referenced in Table 3.3.5.1-1 for Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.
AF  B.1 the channel.
                                                        - - - - - -NOTES- - - - --
: 1. Only applicable in MODES 1, 2, and 3.
R                            2. Only applicable for functions 1.a, 1.b, 2.a, D                                              and 2.b.
                                                        ----------------
Declare supported feature(s) inoperable when its redundant 1 hour from discovery of loss of feature ECCS                      initiation initiation capability              capability for is inoperable.                    feature(s) in both divisions.
AND (continued)
JAFNPP                                                      3.3.5.1-1                                    Amendment 274315


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-1 Amendment 274 315 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
ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
-1 shall be OPERABLE.
CONDITION              REQUIRED ACTION                  COMPLETION TIME B.   (continued)          B.2    - - - - - -NOTE - - - - - -
APPLICABILITY:
Only applicable for functions 3.a and 3.b.
According to Table 3.3.5.1
                                  -----------------
-1. ACTIONS  - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - -  Separate Condition entry is allowed for each channel.
Declare High Pressure        1 hour from Coolant Injection            discovery of (HPCI) System                loss of HPCI inoperable.                   initiation capability AND B.3   Place channel in              24 hours trip.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -  CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable
T C. As required by Required Action A.1 and referenced in Table 3.3.5.1-1.     AF C.1   - - - - - -NOTES- - - - - -
. A.1 Enter the Condition referenced in Table 3.3.5.1
: 1. Only applicable in MODES 1, 2, and 3.
-1 for  the channel.
: 2. Only applicable for functions R                1.c, 1.d, 2.c, 2.d, and 2.f.
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,   and 2.b. - - - - - - - - - - - - - - - - Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
D                        Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
1 hour from discovery of loss of initiation capability for feature(s) in both divisions.
1 hour from discovery of loss of initiation capability for feature(s) in both divisions.
AND   (continued)
AND C.2    Restore channel to            24 hours OPERABLE status.
(continued)
JAFNPP                                3.3.5.1-2                            Amendment 274315


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-2 Amendment 274 315  ACTIONS   (continued)
ECCS Instrumentation 3.3.5.1 ACTIONS (continued CONDITION               REQUIRED ACTION                   COMPLETION TIME D. As required by        D.1      - - - - - -NOTE- - - - - -
CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
Required Action A.1           Only applicable if and referenced in             HPCI pump suction is Table 3.3.5.1-1.               not aligned to the suppression pool.
B.2 - - - - - -NOTE - - - - - - Only applicable for functions 3.a and 3.b. - - - - - - - - - - - - - - - - - Declare High Pressure Coolant Injection (HPCI) System inoperable.
                          .        -----------------
AND  B.3 Place cha nnel in  trip.      1 hour from discovery of loss of HPCI initiation capability 24 hours    C. As required by Required Action A.1 and referenced in Table 3.3.5.1
Declare HPCI System          1 hour from inoperable.                  discovery of loss of HPCI initiation capability AND trip.      T D.2.1 Place channel in               24 hours AF  OR D.2.2 Align the HPCI pump suction to the suppression pool.
-1. C.1 - - - - - -NOTE S- - - - - - 1. Only applicable in MODES 1, 2,    and 3. 2. Only applicable for functions 1.c, 1.d, 2.c ,    2.d, and 2.f. - - - - - - - - - - - - - - - -  Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is inoperable.
1 hour from discovery of loss of initiation capability for feature(s) in both divisions.
AND  C.2 Restore channel to OPERABLE status.
24 hours (continued)
24 hours (continued)
R D
JAFNPP                                3.3.5.1-3                            Amendment 274315


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-3 Amendment 274 315 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.
ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
. - - - - - - - - - - - - - - - - - Declare HPCI System inoperable.
CONDITION               REQUIRED ACTION                   COMPLETION TIME E. As required by       E.1    - - - - - -NOTES- - - - - -
AND D.2.1 Place channel in trip. OR  D.2.2 Align the HPCI pump  suction to the suppression pool.
Required Action A.1         1. Only Applicable and referenced in                 in MODES 1, 2, Table 3.3.5.1-1.                   and 3.
1 hour from discovery of loss of HPCI initiation capability 24 hours    24 hours (continued)
: 2. Only applicable for functions 1.e, 1.f, and 2.g.
                          ..    -----------------
Declare supported            1 hour from Feature(s) inoperable        discovery of when its redundant            loss of feature ECCS                  initiation T
Initiation capability Is inoperable capability for subsystems in both divisions.
AF AND E.2   Restore channel to OPERABLE status.
7 days (continued)
R D
JAFNPP                                3.3.5.1-4                          Amendment 274315


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-4 Amendment 274 315  ACTIONS   (continued)
ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required Action A.1 and referenced in Table 3.3.5.1
CONDITION               REQUIRED ACTION           COMPLETION TIME F. As required by       F.1    Declare Automatic    1 hour from Required Action A.1         Depressurization      discovery of and referenced in           System (ADS) valves  loss of ADS Table 3.3.5.1-1.             inoperable.           initiation capability in both trip systems.
-1. E.1 - - - - - -NOTE S- - - - - -  1. Only Applicable in MODES 1, 2,   and 3. 2. Only applicable for functions 1.e,    1.f, and 2.g. .. - - - - - - - - - - - - - - - - -  Declare supported Feature(s) inoperable when its redundant feature ECCS Initiation capability Is inoperable AND  E.2 Restore channel to OPERABLE status.
AND F.2   Place channel in     96 hours from trip.                 discovery of inoperable channel T              concurrent with HPCI or reactor core isolation AF                          cooling (RCIC) inoperable.
1 hour from discovery of loss of  initiation capability for subsystems in both divisions.
AND 8 days G.
7 days (continu ed)
R As required by Required Action A.1 and referenced in G.1   Declare ADS valves inoperable.
ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-5 Amendment 274 315  ACTIONS  (continued)
1 hour from discovery of loss of ADS D
CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action A.1 and referenced in Table 3.3.5.1
Table 3.3.5.1-1.
-1. F.1 Declare Automatic Depressurization System (ADS) valves inoperable.
AND initiation capability to both trip systems.
AND F.2 Place channel in trip. 1 hour from discovery of loss of ADS initiation capability in both trip systems. 96 hours from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable.
(continued)
AND 8 days     G. As required by Required Action A.1 and referenced in Table 3.3.5.1
JAFNPP                              3.3.5.1-5                    Amendment 274315
-1. G.1 Declare ADS valves inoperable.
AND  1 hour from discovery of loss of ADS initiation capability to both trip systems.   (continued)


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-6 Amendment 274 315 ACTIONS   (continued)
ECCS Instrumentation 3.3.5.1 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME G. (continued)
CONDITION                 REQUIRED ACTION           COMPLETION TIME G.   (continued)             G.2   Restore channel to     96 hours from OPERABLE status.       discovery of inoperable channel concurrent with HPCI or RCIC inoperable.
G.2 Restore channel to OPERABLE status.
AND 8 days H. Required Action and     H.1    Declare associated    Immediately associated Completion         supported feature(s)
96 hours from discovery of inoperable channel concurrent with HPCI or RCIC inoperable.
Time of Condition B, C, D, E, F, or G not met.
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.
T inoperable.
Immediately
AF R
D JAFNPP                                3.3.5.1-6                    Amendment 274315


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-7 Amendment 301 SURVEILLANCE REQUIREMENTS
ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS
  - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1. Refer to Table 3.3.5.1
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
-1 to determine which SRs apply for each ECCS Function.
: 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 hours for Functions 3.c, 3.f, and 3.g; and (b) for up to 6 hours for Functions other than 3.c, 3.f, and 3.g 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, 3.f, and 3.g; and (b) for up to 6 hours for Functions other than 3.c, 3.f, and 3.g provided the associated Function or the redundant Function maintains ECCS initiation capability.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - SURVELLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK.
---------------------------------------------------------------------
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.
SURVELLANCE                                                       FREQUENCY SR 3.3.5.1.1               Perform CHANNEL CHECK.                                                           In accordance with the Surveillance Frequency Control SR 3.3.5.1.2               Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.1.3 Perform CHANNEL CALIBRATION.
T                                          Program In accordance with SR 3.3.5.1.3 AF Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.1.4 Calibrate the trip units.
the Surveillance Frequency Control Program In accordance with the Surveillance SR 3.3.5.1.4 RCalibrate the trip units.
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.1.5 Perform CHANNEL CALIBRATION.
Frequency Control Program In accordance with SR 3.3.5.1.5 D              Perform CHANNEL CALIBRATION.
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.
the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.6               Perform LOGIC SYSTEM FUNCTIONAL TEST.                                           In accordance with the Surveillance Frequency Control Program JAFNPP                                                     3.3.5.1-7                                        Amendment 301
In accordanc e with the Surveillance Frequency Control Progra m ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-8 Amendment 274 315  Table 3.3.5.1
-1 (page 1 of 5)
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 Low (Level 1) 1, 2, 3, 4(a), 5(a) 4 (a b) B SR  3.3.5.1.1 SR  3.3.5.1.
2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 18  inches
: b. Drywell Pressure - High  1, 2, 3 4 (a b) B SR  3.3.5.1.1 SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6
: c. Reactor Pressure  Low (Injection Permissive) 1, 2, 3 4 C SR  3.3.5.1.1 SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 and 90 psig        4 (a), 5(a) 4 B SR  3.3.5.1.1 SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 and 90 psig      d. Core Spray Pump Start  Time Delay Relay 1, 2, 3 , 4(a), 5(a) 1 per pump C SR  3.3.5.1.5 SR  3.3.5.1.6 seconds      e. Core Spray Pump Discharge Flow  Low (Bypass) 1, 2, 3 , 4(a), 5(a) 1 per pump E SR  3.3.5.1.5 SR  3.3.5.1.6 and        f. Core Spray Pump Discharge Pressure  High (Bypass) 1, 2, 3 , 4 (a), 5(a) 1 per pump E SR  3.3.5.1.3 SR  3.3.5.1.6 110 psig      2. Low Pressure Coolant Injection (LPCI) System
: a. Reactor Vessel Water Level  Low Low Low (Level 1) 1, 2, 3 , 4(a), 5(a) 4 (a b) B SR  3.3.5.1.1 SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 (continued) a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS  Shutdown. b)a) Also required to initiate the associated emergency diesel generator subsystem.


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-9 Amendment 274 315  Table 3.3.5.1
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)
-1 (page 2 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                       CONDITIONS MODES           REQUIRED        REFERENCED OR OTHER         CHANNELS          FROM SPECIFIED         PER            REQUIRED     SURVEILLANCE      ALLOWABLE FUNCTION                   CONDITIONS       FUNCTION        ACTION A.1   REQUIREMENTS         VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE      2. LPCI System (continued)
: 1. Core Spray System
: b. Drywell Pressure - High 1, 2, 3 4 (a b) B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
: a. Reactor Vessel Water              1, 2, 3,          4(ab)              B       SR  3.3.5.1.1    18 inches Level - Low Low Low              4(a), 5(a)                                  SR  3.3.5.1.2 (Level 1)                                                                     SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6
: c. Reactor Pressure Low (Injection Permissive) 1, 2, 3 4 C SR  3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 and         4(a), 5(a) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 and        d. Reactor Pressure  Low (Recirculation Discharge Valve Permissive) 1 (b c), 2 (b c), 3 (b c) 4 C SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 295 psig       e. Reactor Vessel Shroud Level (Level 0) 1, 2, 3 2 B SR 3.3.5.1.1 SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 1.0 inches       f. Low Pressure Coolant Injection Pump Start  Time Delay Relay 1, 2, 3 , 4(a), 5(a) 1 per pump C SR 3.3.5.1.5 SR 3.3.5.1.6 Pumps A , D     1.51 seconds       Pumps B , C    6.73 seconds           (continued) a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
: b. Drywell                           1, 2, 3           4(ab)             B       SR   3.3.5.1.1   2.7 psig Pressure - High                                                                SR   3.3.5.1.2 SR   3.3.5.1.4 SR   3.3.5.1.5 SR   3.3.5.1.6
: c. Reactor Pressure - Low (Injection Permissive) 1, 2, 3 T
4               C       SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 410 psig and 490 psig
: d. Core Spray Pump Start - Time Delay AF 4(a), 5(a) 1, 2, 3, 4
1 per pump B
C SR SR SR SR SR SR 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 SR 3.3.5.1.5 410 psig and 490 psig 12.34 e.
Relay Core Spray Pump  R Discharge Flow - Low (Bypass) 4(a), 5(a) 1, 2, 3, 4(a), 5(a) 1 per pump            E SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 seconds 510 gpm and 980 gpm 2.
f.
D Core Spray Pump Discharge Pressure - High (Bypass)
Low Pressure Coolant Injection (LPCI) System 1, 2, 3, 4(a), 5(a) 1 per pump            E      SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 110 psig
: a. Reactor Vessel Water              1, 2, 3,          4(ab)              B       SR   3.3.5.1.1   18 inches Level - Low Low Low              4(a), 5(a)                                  SR   3.3.5.1.2 (Level 1)                                                                      SR   3.3.5.1.4 SR   3.3.5.1.5 SR   3.3.5.1.6 (continued) a)  When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.
b)a) Also required to initiate the associated emergency diesel generator subsystem.
JAFNPP                                                    3.3.5.1-8                              Amendment 274315
 
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                        CONDITIONS MODES            REQUIRED      REFERENCED OR OTHER          CHANNELS          FROM SPECIFIED          PER          REQUIRED    SURVEILLANCE      ALLOWABLE FUNCTION                    CONDITIONS        FUNCTION        ACTION A.1   REQUIREMENTS        VALUE
: 2. LPCI System (continued)
: b. Drywell                          1, 2, 3,            4(ab)            B      SR  3.3.5.1.1    2.7 psig Pressure - High                                                                SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6
: c. Reactor Pressure - Low            1, 2, 3             4               C       SR   3.3.5.1.1   410 psig (Injection Permissive)                                                        SR   3.3.5.1.2   and SR   3.3.5.1.4   490 psig SR   3.3.5.1.5 SR   3.3.5.1.6 4(a), 5(a)          4 T              B      SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 410 psig and 490 psig d.
e.
Reactor Pressure - Low (Recirculation Discharge Valve Permissive)
Reactor Vessel Shroud Level (Level 0)
AF 1(bc), 2(bc),
3(bc) 1, 2, 3 4
2 C
B SR SR SR SR SR SR SR SR 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 295 psig 1.0 inches f.
R Low Pressure Coolant             1, 2, 3,       1 per pump           C SR SR SR 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 SR 3.3.5.1.5 D
Injection Pump Start - Time Delay Relay Pumps A, D Pumps B, C 4(a), 5(a)                                  SR 3.3.5.1.6 1.51 seconds 6.73 seconds (continued) a)   When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
b)a) Also required to initiate the associated emergency diesel generator subsystem.
b)a) Also required to initiate the associated emergency diesel generator subsystem.
c)b) With associated recirculation pump discharge valve open.
c)b) With associated recirculation pump discharge valve open.
JAFNPP                                                    3.3.5.1-9                              Amendment 274315


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-10 Amendment 274 315  Table 3.3.5.1
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)
-1 (page 3 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                     CONDITIONS MODES OR         REQUIRED    REFERENCED OTHER           CHANNELS        FROM SPECIFIED         PER        REQUIRED         SURVEILLANCE      ALLOWABLE FUNCTION                 CONDITIONS       FUNCTION      ACTION A.1       REQUIREMENTS         VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE       2. LPCI System (continued)
: 2. LPCI System (continued)
: g. Low Pressure Coolant Injection Pump Discharge Flow  Low (Bypass) 1, 2, 3 , 4(a), 5(a) 1 per subsystem E SR 3.3.5.1.5 SR 3.3.5.1.6 040 gpm and        h. Containment Pressure - High  1, 2, 3 4 B SR 3.3.5.1.
: g. Low Pressure                     1, 2, 3,       1 per             E           SR 3.3.5.1.5     1040 gpm Coolant Injection Pump          4(a), 5(a)    subsystem                      SR 3.3.5.1.6     and Discharge Flow - Low                                                                            1665 gpm (Bypass)
3 SR 3.3.5.1.6
: h. Containment                     1, 2, 3           4               B           SR 3.3.5.1.3     1 psig and Pressure - High                                                                SR 3.3.5.1.6     2.7 psig
: 3. High Pressure Coolant Injection (HPCI) System
: 3. High Pressure Coolant Injection (HPCI) System
: a. Reactor Vessel Water Level Low Low (Level 2) 1, 2 (c d), 3 (c d) 4 B SR 3.3.5.1.1 SR 3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 126.5  inches       b. Drywell Pressure - High 1, 2 (c d), 3 (c d) 4 B SR 3.3.5.1.1 SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 2.7 psig        c. Reactor Vessel Water Level  High (Level 8) 1, 2 (c d), 3 (c d) 2 C SR  3.3.5.1.1 SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 222.5 inches       d. Condensate Storage Tank Level - Low 1, 2 (c d), 3 (c d) 4 D SR 3.3.5.1.3 SR  3.3.5.1.6 59.5 inches
: a. Reactor Vessel Water               1,            4              B          SR  3.3.5.1.1    126.5 Level - Low Low (Level 2) 2(cd), 3(cd)
: e. Suppression Pool Water Level  High 1, 2 (c d), 3 (c d) 2 D  SR 3.3.5.1.3 SR 3.3.5.1.6 14.5 ft      f. High Pressure Coolant Injection Pump Discharge Flow  
T                          SR SR SR SR 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 inches b.
- :Low (Bypass) 1, 2 (c d), 3 (c d) 1 E SR 3.3.5.1.5 SR 3.3.5.1.6 and 800 gpm       g. High Pressure Coolant Injection Pump Discharge Pressure  High (Bypass) 1, 2 (c d), 3 (c d) 1 E SR 3.3.5.1.3 SR 3.3.5.1.6 and 80 psig           (continued) a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
c.
c) With rector steam dose pressure > 150 psig.
Drywell Pressure - High Reactor Vessel Water Level - High (Level 8)
AF    1, 2(cd), 3(cd) 1, 2(cd), 3(cd) 4 2
B C
SR SR SR SR SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 2.7 psig 222.5 inches
: d. Condensate Storage Tank Level - Low R                1, 2(cd), 3(cd) 4               D SR SR 3.3.5.1.5 3.3.5.1.6 SR 3.3.5.1.3 SR 3.3.5.1.6 59.5 inches e.
: f. D Suppression Pool Water Level - High High Pressure Coolant Injection Pump Discharge Flow - :Low (Bypass) 1, 2(cd), 3(cd) 1, 2(cd), 3(cd) 2 1
D E
SR 3.3.5.1.3 SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 14.5 ft 475 gpm and 800 gpm
: g. High Pressure Coolant               1,             1               E           SR 3.3.5.1.3     25 psig Injection Pump                  2(cd), 3(cd)                                  SR 3.3.5.1.6     and Discharge                                                                                        80 psig Pressure - High (Bypass)
(continued) a)   When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.
c)   With rector steam dose pressure > 150 psig.
JAFNPP                                                  3.3.5.1-10                              Amendment 274315


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-11 Amendment 274 315 Table 3.3.5.1
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)
-1 (page 4 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                     CONDITIONS MODES OR         REQUIRED    REFERENCED OTHER           CHANNELS        FROM SPECIFIED         PER        REQUIRED         SURVEILLANCE      ALLOWABLE FUNCTION                 CONDITIONS       FUNCTION      ACTION A.1       REQUIREMENTS         VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE       4. Automatic Depressurization System (ADS) Trip System A
: 4. Automatic Depressurization System (ADS) Trip System A
: a. Reactor Vessel Water Level  Low Low Low (Level 1) 1, 2 (c d), 3 (c d) 2 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 18 inches        b. Automatic Depressurization System Initiation Timer  1, 2 (c d), 3 (c d) 1 G SR 3.3.5.1.5 SR 3.3.5.1.6 134 seconds
: a. Reactor Vessel Water               1,             2               F           SR   3.3.5.1.1   18 inches Level - Low Low Low            2(cd), 3(cd)                                  SR   3.3.5.1.2 (Level 1)                                                                      SR   3.3.5.1.4 SR   3.3.5.1.5 SR   3.3.5.1.6
: c. Reactor Vessel Water Level Low (Level
: b. Automatic                           1,             1               G           SR 3.3.5.1.5     134 seconds Depressurization                2(cd), 3(cd)                                  SR 3.3.5.1.6 System Initiation Timer
: 3) 1, 2 (c d), 3 (c d) 1 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 177 inches        d. Core Spray Pump Discharge Pressure - High 1, 2 (c d), 3 (c d) 2 G SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 110 psig        e. Low Pressure Coolant Injection Pump Discharge Pressure - High  1, 2 (c d), 3 (c d) 4 G SR 3.3.5.1.
: c. Reactor Vessel Water               1,            1              F          SR  3.3.5.1.1    177 inches Level - Low (Level 3)           2(cd), 3(cd)
3 SR 3.3.5.1.6 105 psig and 145 psig         5. ADS Trip System B
T                          SR SR SR SR 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 d.
: a. Reactor Vessel Water Level Low Low Low (Level 1) 1, 2 (c d), 3 (c d) 2 F SR 3.3.5.1.1 SR  3.3.5.1.2 SR  3.3.5.1.4 SR  3.3.5.1.5 SR  3.3.5.1.6 18 inches       b. Automatic Depressurization System Initiation Timer 1, 2 (c d), 3 (c d) 1 G SR 3.3.5.1.
e.
5 SR 3.3.5.1.6 134 seconds (continued)
Core Spray Pump Discharge Pressure - High Low Pressure Coolant Injection Pump Discharge Pressure - High AF    1, 2(cd), 3(cd) 1, 2(cd), 3(cd) 2 4
G G
SR 3.3.5.1.3 SR 3.3.5.1.6 SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 110 psig 105 psig and 145 psig
: 5. ADS Trip System B
: a.                   R Reactor Vessel Water Level - Low Low Low (Level 1) 1, 2(cd), 3(cd) 2               F           SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 18 inches
: b. D Automatic Depressurization System Initiation Timer 1,
2(cd), 3(cd) 1               G SR SR 3.3.5.1.5 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 134 seconds (continued)
: c. With rector steam dose pressure > 150 psig.
: c. With rector steam dose pressure > 150 psig.
JAFNPP                                                  3.3.5.1-11                              Amendment 274315


ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-12 Amendment 274 315  Table 3.3.5.1
ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)
-1 (page 5 of 5)
Emergency Core Cooling System Instrumentation APPLICABLE                     CONDITIONS MODES OR         REQUIRED    REFERENCED OTHER           CHANNELS        FROM SPECIFIED         PER        REQUIRED       SURVEILLANCE      ALLOWABLE FUNCTION                 CONDITIONS       FUNCTION      ACTION A.1     REQUIREMENTS         VALUE
Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE       5. ADS Trip System B (continued)
: 5. ADS Trip System B (continued)
: c. Reactor Vessel Water Level  Low (Level 3) 1, 2 (c d), 3 (c d) 1 F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
: c. Reactor Vessel Water               1,           1               F           SR   3.3.5.1.1   177 inches Level - Low (Level 3)          2(cd), 3(cd)                                  SR   3.3.5.1.2 SR   3.3.5.1.4 SR   3.3.5.1.5 SR   3.3.5.1.6
: d. Core Spray Pump Discharge Pressure - High 1, 2 (c d), 3 (c d) 2 G SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and        e. Low Pressure Coolant Injection Pump Discharge Pressure - High 1, 2 (c d), 3 (c d) 4 G SR  3.3.5.1.
: d. Core Spray Pump                     1,           2               G           SR 3.3.5.1.3     90 psig Discharge                      2(cd), 3(cd)                                  SR 3.3.5.1.6     and Pressure - High                                                                                110 psig
3 SR 3.3.5.1.
: e. Low Pressure Coolant               1,            4              G          SR 3.3.5.1.3      105 psig Injection Pump Discharge Pressure - High 2(cd), 3(cd)
6   105 psig  and 145 psig             (continued) d)c) With rector steam dose pressure > 150 psig.
T                          SR 3.3.5.1.6     and 145 psig (continued)
AF d)c) With rector steam dose pressure > 150 psig.
R D
JAFNPP                                                  3.3.5.1-12                              Amendment 274315


RPV Water Inventory C ontrol Instrumentation 3.3.5.2 JAFNPP 3.3.5.2-1 Amendment 315    3.3 INSTRUMENTAT I O N  3.3.5.2 Reactor Pressure Vess e l (RPV) Wa t er Inventory Control Inst rumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE. APPLICAB ILITY: According to Table 3.3.5.2-1. ACTIONS ---------------
RPV Water Inventory Control Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2       Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2                   The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.
----------------
APPLICABILITY:               According to Table 3.3.5.2-1.
----------------
ACTIONS
-------------
------------------------------------------------------------NOTE-----------------------------------------------------------
NO T E-----------
Separate Condition entry is allowed for each channel.
----------------
-------------------------------------------------------------------------------------------------------------------------------
----------------
CONDITION T
----------------
REQUIRED ACTION                           COMPLETION TIME A. One or more channels inoperable.
Separate Condition ent r y is allowed for each ch annel. ---------------
AF  A.1       Enter the Condition referenced in Table 3.3.5.2-1 for the channel.
----------------
Immediately Action A.1 and referenced in Table 3.3.5.2-1.
----------------
R B. As required by Required                B.1       Declare associated penetration flow path(s) incapable of automatic isolation.
----------------
Immediately D                              AND B.2       Calculate DRAIN TIME.                   Immediately C. As required by Required               C.1        Place channel in trip.                  1 hour Action A.1 and referenced in Table 3.3.5.2-1.
----------------
D. As required by Required               D.1        Restore channel to                      24 hours Action A.1 and                                   OPERABLE status.
----------------
referenced in Table 3.3.5.2-1.
----------------
JAFNPP                                                  3.3.5.2-1                                          Amendment 315
----------------
 
CONDITION REQUIR E D ACTION COMPLET I ON T I M E  A. O ne or more channels inoperable.
RPV Water Inventory Control Instrumentation 3.3.5.2 ACTIONS (continued)
A.1 Enter the Condition referenced in Table 3.3.5.2-1 for the channel. Immediately B. A s required by Required Action A.1 and referenced in Table 3.3.5.2-1. B.1 Declare associated penetration flow path(s) incapable of automatic isolation.
CONDITION                               REQUIRED ACTION                           COMPLETION TIME E. Required Action and                   E.1       Declare associated low                   Immediately associated Completion                            pressure ECCS Time of Condition C or D                          injection/spray subsystem not met.                                          inoperable.
AND B.2 Calculate DRAIN T I M E. Immediately Immediately C. A s required by Required Action A.1 and referenced in Table 3.3.5.2-1. C.1 Place chan n el in trip. 1 hour  D. A s required by Required Action A.1 and referenced in Table 3.3.5.2-1. D.1 Restore ch a nnel to OP ERAB LE status. 24 hours RPV Water Inventory C ontrol Instrumentation 3.3.5.2 JAFNPP 3.3.5.2-2 Amendment 315    ACTIONS (continued)
SURVEILLANCE REQUIREMENTS
CONDITION REQUIR E D ACTION COMPLET I ON T I M E  E. Required Action and associa t ed Completion Time of Condition C or D not met. E.1 Declare associated low pressure ECCS injection/sp r ay subsystem inoperable.
------------------------------------------------------------NOTE-----------------------------------------------------------
Immediately SUR VEILL ANCE REQU IREMENTS ---------------
Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.
----------------
-------------------------------------------------------------------------------------------------------------------------------
----------------
SR 3.3.5.2.1 SURVEILLANCE Perform CHANNEL CHECK.
-------------
T                                      FREQUENCY In accordance SR 3.3.5.2.2 AF Perform CHANNEL FUNCTIONAL TEST.
NO T E-----------
with the Surveillance Frequency Control Program In accordance R                                                                          with the Surveillance Frequency Control Program D
----------------
SR 3.3.5.2.3             Perform LOGIC SYSTEM FUNCTIONAL TEST.                                   In accordance with the Surveillance Frequency Control Program JAFNPP                                                  3.3.5.2-2                                          Amendment 315
----------------
 
----------------
RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)
Refer to Table 3.3.5.2-1 t o determine which SRs apply for each ECCS F unction. ---------------
RPV Water Inventory Control Instrumentation APPLICABLE                     CONDITIONS MODES OR REQUIRED              REFERENCED OTHER   CHANNELS                FROM SPECIFIED   PER                REQUIRED       SURVEILLANCE        ALLOWABLE FUNCTION       CONDITIONS FUNCTION              ACTION A.1     REQUIREMENTS           VALUE
----------------
: 1. Core Spray
----------------
: a. a. Reactor               4, 5           4               C             SR 3.3.5.2.1       < 490 psig Pressure -                                                          SR 3.3.5.2.2 Low (Injection Permissive)
----------------
: b. b. Core Spray             4, 5       1 per pump           D             SR 3.3.5.2.1       > 510 gpm Pump                                  (a)                            SR 3.3.5.2.2           and Discharge Flow                                                                          < 980 gpm
----------------
            - Low (Bypass)
----------------
: c. c. Manual             4, 5         1 per             D             SR 3.3.5.2.3           NA Initiation                    subsystem
----------------
: 2. Low Pressure Coolant Injection (LPCI) System (a)
----------------
T a.
SUR VEILL A NCE  FREQUENCY  SR 3.3.5.2.1 Perform CHANNEL CHECK. In accorda n ce with the Surveillance Frequency Control Program  SR 3.3.5.2.2 Perform CHANNEL FUNCTIONAL TEST. In accorda n ce with the Surveillance Frequency Control Program SR 3.3.5.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accorda n ce with the Surveillance Frequency Control Program RPV Water Inventory C ontrol Instrumentation 3.3.5.2 JAFNPP 3.3.5.2-3 Amendment 315  Table 3.3.5.2-1 (page 1 of 1) RPV Water Inventory C ontrol 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
b.
: a. a. Reactor Pressure  Low (Injection Permissive) 4, 5 4 C SR 3.3.5.2.1 SR 3.3.5.2.2
: a. Reactor Pressure -
< 490 psig        b. b. Core Spray Pump Discharge Flow  Low (Bypass) 4, 5 1 per pump (a) D SR 3.3.5.2.1 SR 3.3.5.2.2
Low (Injection Permissive)
> 510 gpm and < 980 gpm       c. c. Manual Initiation 4, 5 1 per subsystem (a) D SR 3.3.5.2.3 NA       2. Low Pressure Coolant Injection (LPCI) System
: b. Low Pressure Coolant Injection Pump AF 4, 5 4, 5 4
: a. a. Reactor Pressure Low (Injection Permissive) 4, 5 4 C SR 3.3.5.2.1 SR 3.3.5.2.2
1 per pump (a)
< 490 psig        b. b. Low Pressure Coolant Injection Pump Discharge Flow  Low (Bypass) 4, 5 1 per pump (a) D SR 3.3.5.2.1 SR 3.3.5.2.2
C D
> 1040 gpm and < 1665 gpm       c. c. Manual Initiation 4, 5 1 per subsystem (a) D SR 3.3.5.2.3 NA       3. Residual Heat Removal System Isolation
SR 3.3.5.2.1 SR 3.3.5.2.2 SR 3.3.5.2.1 SR 3.3.5.2.2
: a. a. Reactor Vessel Water Level Low, Level 3 (b) 2 in one trip system B SR 3.3.5.2.1 SR 3.3.5.2.2
                                                                                                    < 490 psig
> 177 inches
                                                                                                    > 1040 gpm and
                                                                                                    < 1665 gpm
: c. c.
Discharge Flow
            - Low (Bypass)
Manual R      4, 5         1 per             D             SR 3.3.5.2.3           NA D
Initiation
: 3. Residual Heat Removal System Isolation
: a. a. Reactor Vessel Water Level -
(b) subsystem (a) 2 in one trip system B             SR 3.3.5.2.1 SR 3.3.5.2.2
                                                                                                    > 177 inches Low, Level 3
: 4. Reactor Water Cleanup System Isolation
: 4. Reactor Water Cleanup System Isolation
: a. a. Reactor Vessel Water Level  Low Level 3 (b) 2 in one trip system B SR 3.3.5.2.1 SR 3.3.5.2.2
: a. a. Reactor Vessel         (b)       2 in one trip       B             SR 3.3.5.2.1       > 177 inches Water Level -                        system                          SR 3.3.5.2.2 Low Level 3 (a) Associated with an ECCS subsystem required to be OPERABLE by LCO 3.5.2, Reactor Pressure Vessel Water Inventory Control.
> 177 inches (b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
(b) When automatic isolation of the associated penetration flow path(s) is credited in calculating DRAIN TIME.
RCIC System Instrumentation 3.3.5.3 2 JAFNPP 3.3.5.3 2-1 Amendment 274 315 3.3 INSTRUMENTATION 3.3.5.3 2 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO  3.3.5.3 2 The RCIC System instrumentation for each Function in Table 3.3.5.
JAFNPP                                         3.3.5.2-3                                  Amendment 315
3 2-1 shall be OPERABLE. APPLICABILITY:
MODE 1,  MODES 2 and 3 with reactor steam dome pressure > 150 psig ACTIONS  - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - -  Separate Condition entry is allowed for each channel.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -  CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels inoperable
. A.1 Enter the Condition referenced in Table 3.3.5.
3 2-1 for  the channel.
Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.
3 2-1. B.1 Declare RCIC System inoperable.
AND 1 hour from discovery of loss of RCIC initiation capability B.2 Place channel in Trip. 24 hours    C. As required by Required Action A.1 and referenced in Table 3.3.5.
3 2-1. C.1 Restore channel in OPERABLE status.
24 hours      (continued)


RCIC System Instrumentation 3.3.5.3 2 JAFNPP 3.3.5.3 2-2 Amendment 274 315  ACTIONS  (continued)
RCIC System Instrumentation 3.3.5.32 3.3      INSTRUMENTATION 3.3.5.32          Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO      3.3.5.32            The RCIC System instrumentation for each Function in Table 3.3.5.32-1 shall be OPERABLE.
CONDITION REQUIRED ACTION COMPLETION TIME D. As required by Required Action A.1 and referenced in Table 3.3.5.
APPLICABILITY:                MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig ACTIONS
3 2-1. D.1 - - - - - -NOTE- - - - - - - Only applicable if  RCIC pump suction is not aligned to the suppression pool.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - -
  - - - - - - - - - - - - - - - - - Declare (R CI C) System inoperable.
Separate Condition entry is allowed for each channel.
AND        1 hour from discovery of loss of automatic R CI C initiation capability D.2.1 Place channel in trip. OR  24 hours D.2.2 Align RCIC pump suction to the suppression pool.
----------------------------------------------------------------------
24 hours   E. Required Action and associated Completion Time of Condition B,  C, or D not met.
CONDITION                              REQUIRED ACTION                            COMPLETION TIME A. One or more channels inoperable.
E.1 Declare RCIC System inoperable.
A.1                  T Enter the Condition referenced in Immediately B. As required by Required Action A.1 and referenced in AF  B.1 Table 3.3.5.32-1 for the channel.
Immediately
Declare RCIC System inoperable.
1 hour from discovery of loss of RCIC Table 3.3.5.32-1.
R                 AND initiation capability C.
D As required by B.2 C.1 Place channel in Trip.
Restore channel in 24 hours 24 hours Required Action A.1                              OPERABLE status.
and referenced in Table 3.3.5.32-1.
(continued)
JAFNPP                                                    3.3.5.32-1                                    Amendment 274315


RCIC System Instrumentation 3.3.5.3 2 JAFNPP 3.3.5.3 2-3 Amendment 301 315  SURVEILLANCE REQUIREMENTS
RCIC System Instrumentation 3.3.5.32 ACTIONS (continued)
  - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -  1. Refer to Table 3.3.5.
CONDITION                REQUIRED ACTION                  COMPLETION TIME D. As required by          D.1    - - - - - -NOTE- - - - - - -
3 2-1 to determine which SRs apply for each RCIC Function. 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows:  (a) for up to 6 hours for Functions 2 and 4; and (b) for up to 6 hours fo r Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.
Required Action A.1           Only applicable if and referenced in              RCIC pump suction is Table 3.3.5.32-1.             not aligned to the suppression pool.
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -  SURVELLANCE FREQUENCY  SR 3.3.5.3 2.1  Perform CHANNEL CHECK.
                                    -----------------
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.3 2.2  Perform CHANNEL FUNCTIONAL TEST.
Declare (RCIC) System         1 hour from inoperable.                   discovery of loss of automatic RCIC initiation capability AND trip.
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.3 2.3  Perform CHANNEL CALIBRATION.
T D.2.1 Place channel in                24 hours AF    OR D.2.2 Align RCIC pump suction to the suppression pool.
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.3 2.4  Calibrate the trip units.
24 hours E.
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.3 2.5  Perform CHANNEL CALIBRATION.
R Required Action and associated Completion Time of Condition B, E.1   Declare RCIC System inoperable.
In accordance with the Surveillance Frequency Control Progra m  SR 3.3.5.3 2.6  Perform LOGIC SYSTEM FUNCTIONAL TEST.
Immediately D
In accordance with the Surveillance Frequency Control Progra m RCIC System Instrumentation 3.3.5.3 2 JAFNPP 3.3.5.3 2-4 Amendment 274 315  Table 3.3.5.
C, or D not met.
3 2-1 Reactor Core Isolation Cooling System Instrumentation (Page 1 of 1)      FUNCTION  REQUIRED CHANNELS PER FUNCTION  CONDITIONS REFERENCED FROM REQUIRED ACTION A.1 SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE      1. Reactor Vessel Water Level  Low Low (Level 2)  4 B SR  3.3.5.
JAFNPP                                  3.3.5.32-2                           Amendment 274315
3 2.1 SR  3.3.5.
3 2.2 SR  3.3.5.
3 2.4 SR  3.3.5.
3 2.5 SR  3.3.5.
3 2.6        2. Reactor Vessel Water Level  High (Level 8) 2 C SR  3.3.5.
3 2.1 SR  3.3.5.
3 2.2 SR  3.3.5.
3 2.4 SR  3.3.5.
3 2.5 SR  3.3.5.
3 2.6      3. Condensate Storage Tank Level - Low 4 D SR  3.3.5.
3 2.3 SR  3.3.5.
3 2.6      4. Manual Initiat ion 1 C SR  3.3.5.
3 2.6 NA Primary Containment Isolation Instrumentation 3.3.6.1 JAFNPP 3.3.6.1-3 Amendment 274 315 ACTIONS  (continued)
CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and associated Completion Time of Condition F or G not met.
OR  As required by Required Action C
.1  and referenced in Table 3.3.6.1
-1. H.1 Be in MODE 3.
AND  H.2 Be in MODE 4.
12 hours  36 hours  I. As required by Required Action C.1 and referenced in Table 3.3.6.1
-1. I.1 Declare associated standby liquid control subsystem (SLC) inoperable.
OR  I.2  Isolate the Reactor Water Cleanup System.
1 hour      1 hour  J. As required by Required Action C.1 and referenced in Table 3.3.6.1
-1. J.1    Initiate action to restore channel to OPERABLE status.
OR  J.2 Initiate action to isolate the Residual Heat Removal (RHR) Shutdown Cooling System. Immediately Immediately


Primary Containment Isolation Instrumentation 3.3.6.1    JAFNPP 3.3.6.1-10 Amendment 298 315  Table 3.3.6.1-1 (page 5 of 6)  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. Reactor Water Cleanup (RWCU) System Isolation
RCIC System Instrumentation 3.3.5.32 SURVEILLANCE REQUIREMENTS
: a. RWCU Suction Line Penetration Area TemperatureHigh    1,2,3    1     F    SR  3.3.6.1.3 SR  3.3.6.1.7 144 F  b. RWCU Pump Area TemperatureHigh    1,2,3    1 per  room    F    SR  3.3.6.1.3 SR  3.3.6.1.7 165F for Pump Room A and 175F for Pump Room B  c. RWCU Heat  Exchanger Room Area TemperatureHigh  1,2,3 1 F SR  3.3.6.1.3 SR  3.3.6.1.7 155 F  d. SLC System Initiation 1,2 2(d) I SR  3.3.6.1.7 NA  e. Reactor Vessel Water LevelLow (Level
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
: 3) 1,2,3 2 F SR 3.3.6.1.1 SR  3.3.6.1.2 SR 3.3.6.1.4 SR  3.3.6.1.5 SR  3.3.6.1.7 177 inches
: 1. Refer to Table 3.3.5.32-1 to determine which SRs apply for each RCIC Function.
: f. Drywell PressureHigh 1,2,3 2 F SR  3.3.6.1.1 SR 3.3.6.1.2 SR  3.3.6.1.4 SR 3.3.6.1.5 SR  3.3.6.1.7 2.7 psig 6. Shutdown Cooling System Isolation  a. Reactor PressureHigh    1,2,3    1    F    SR  3.3.6.1.1 SR  3.3.6.1.
: 2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours for Functions 2 and 4; and (b) for up to 6 hours for Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.
2 SR  3.3.6.1.
---------------------------------------------------------------------
4 SR 3.3.6.1.5 SR  3.3.6.1.7 74 psig    b. Reactor Vessel Water LevelLow (Level 3) 3,4,5   2(e)  J      SR  3.3.6.1.1 SR 3.3.6.1.2 SR  3.3.6.1.4 SR  3.3.6.1.5 SR  3.3.6.1.7 177 inches    (continued)
SURVELLANCE                                                      FREQUENCY SR 3.3.5.32.1             Perform CHANNEL CHECK.                                                           In accordance with the Surveillance Frequency Control Program SR 3.3.5.32.2             Perform CHANNEL FUNCTIONAL TEST.     T                                          In accordance with the Surveillance SR 3.3.5.32.3 AF Perform CHANNEL CALIBRATION.
(d) SLC System Initiation only inputs into one of the two trip systems and only isolates one valve in the RWCU suction and return line.  (e) Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
Frequency Control Program In accordance with the Surveillance Frequency Control SR 3.3.5.32.4 RCalibrate the trip units.
Program In accordance with the Surveillance D
SR 3.3.5.32.5             Perform CHANNEL CALIBRATION.
Frequency Control Program In accordance with the Surveillance Frequency Control Program SR 3.3.5.32.6             Perform LOGIC SYSTEM FUNCTIONAL TEST.                                           In accordance with the Surveillance Frequency Control Program JAFNPP                                                    3.3.5.32-3                                   Amendment 301315


Secondary Containment Isolation Instrumentation 3.3.6.2 JAFNPP 3.3.6.2-4 Amendment 27 6 315 `  Table 3.3.6.2
RCIC System Instrumentation 3.3.5.32 Table 3.3.5.32-1 Reactor Core Isolation Cooling System Instrumentation (Page 1 of 1)
-1 (page 1 of 1)
CONDITIONS REQUIRED             REFERENCED CHANNELS           FROM REQUIRED        SURVEILLANCE              ALLOWABLE FUNCTION              PER FUNCTION            ACTION A.1        REQUIREMENTS                 VALUE
Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE     1. Reactor Vessel Water     Level  Low (Level 3) 1, 2, 3, (a)  2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6
: 1. Reactor Vessel Water                   4                    B              SR     3.3.5.32.1   126.5 inches Level - Low Low (Level 2)                                                    SR     3.3.5.32.2 SR     3.3.5.32.4 SR     3.3.5.32.5 SR     3.3.5.32.6
: 2. Drywell Pressure - High  1, 2, 3 2 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6       3. Reactor Building Exhaust Radiation
: 2. Reactor Vessel Water                  2                     C              SR     3.3.5.32.1   222.5 inches Level - High (Level 8)                                                      SR     3.3.5.32.2 SR     3.3.5.32.4 SR     3.3.5.32.5 SR     3.3.5.32.6
- High 1, 2, 3 , (a), (b) 1 SR 3.3.6.2.1 SR 3.3.6.2.3 SR 3.3.6.2.6 24,800 cpa      4. Refueling Floor Exhaust Radiation
: 3. Condensate Storage Tank                4                    D              SR 3.3.5.32.3       59.5 inches Level - Low                                                                  SR 3.3.5.32.6
- High  1, 2, 3, (a), (b) 1 SR 3.3.6.2.1 SR 3.3.6.2.3 SR 3.3.6.2.6 (a) During operation with a potential for draining the reactor vessel.
: 4. Manual Initiation                      1 T      C              SR 3.3.5.32.6       NA AF R
(b)(a) During movement of recently irradiated fuel assemblies in secondary containment.
D JAFNPP                                              3.3.5.32-4                                    Amendment 274315


CREVAS System Instrumentation 3.3.7.1     JAFNPP 3.3.7.1-1 Amendment 276315 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS)
Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)
System Instrumentation LCO 3.3.7.1 The Control Room Air Inlet RadiationHigh channel shall be OPERABLE. APPLICABILITY:
CONDITION              REQUIRED ACTION              COMPLETION TIME H. Required Action and      H.1   Be in MODE 3.             12 hours associated Completion Time of Condition F or  AND G not met.                                              36 hours H.2  Be in MODE 4.
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. ACTIONS  CONDITION REQUIRED ACTION COMPLETION TIME A. Channel inoperable.
OR As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
A.1      Place the CREVAS System in the isolate mode of operation.
I. As required by        I.1  Declare associated        1 hour Required Action C.1         standby liquid and referenced in Table 3.3.6.1-1.                     T control subsystem (SLC) inoperable.
OR A.2       Declare both CREVAS subsystems inoperable.
AF OR I.2   Isolate the Reactor Water Cleanup System.
1 hour     1 hour CREVAS System Instrumentation 3.3.7.1 JAFNPP 3.3.7.1-2 Amendment 301 SURVEILLANCE REQUIREMENTS
1 hour J.
   ----------------------------------------------------------NOTE-----------------------------------------------
R As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
When the channel is placed in an inoperable status solely for performance of required Surveillances, entry into the Condition and Required Actions may be delayed for up to 6 hours. ------------------------------------------------------------------------------------------------------------------
J.1   Initiate action to restore channel to OPERABLE status.
SURVEILLANCE FREQUENCY  SR  3.3.7.1.1        Perform CHANNEL CHECK.
Immediately D                OR J.2  Initiate action to isolate the Residual Heat Removal (RHR)
In accordance with the  Surveillance Frequency Control Program SR  3.3.7.1.2        Perform CHANNEL CALIBRATION. The Allowable Value shall be  4000 cpm. In accordance with the  Surveillance Frequency Control Program
Shutdown Cooling System.
Immediately JAFNPP                                3.3.6.1-3                        Amendment 274315


ECCS - Operating 3.5.1  JAFNPP 3.5.1-1 Amendment 284 315 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1   ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 6)
APPLICABILITY:
Primary Containment Isolation Instrumentation APPLICABLE        REQUIRED      CONDITIONS          SURVEILLANCE              ALLOWABLE MODES OR        CHANNELS      REFERENCED          REQUIREMENTS                VALUE OTHER            PER TRIP        FROM SPECIFIED        SYSTEM        REQUIRED FUNCTION                    CONDITIONS                        ACTION C.1
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 psig. ACTIONS ---------------------------------------------------------NOTE-------------------------------------------------------------
: 5. Reactor Water Cleanup (RWCU)
System Isolation
: a. RWCU Suction Line                    1,2,3            1                F              SR 3.3.6.1.3        144F Penetration Area                                                                      SR 3.3.6.1.7 Temperature  High
: b. RWCU Pump Area                      1,2,3              1 per          F              SR 3.3.6.1.3        165F for Pump Temperature  High                                      room                          SR 3.3.6.1.7        Room A and 175F for Pump Room B c.
d.
RWCU Heat Exchanger Room Area Temperature  High SLC System Initiation 1,2,3 1,2 1
2(d)
T            F I
SR 3.3.6.1.3 SR 3.3.6.1.7 SR 3.3.6.1.7 155F NA e.
f.
Reactor Vessel Water Level Low (Level 3)
Drywell Pressure  High AF    1,2,3 1,2,3 2
2 F
F SR SR SR SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 177 inches 2.7 psig 6.
R Shutdown Cooling System Isolation SR SR 3.3.6.1.5 3.3.6.1.7 a.
b.
D Reactor Pressure High Reactor Vessel Water Level Low (Level 3) 1,2,3 3,4,5 1
2(e)
F J
SR SR SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 74 psig 177 inches SR  3.3.6.1.4 SR  3.3.6.1.5 SR  3.3.6.1.7 (continued)
(d)    SLC System Initiation only inputs into one of the two trip systems and only isolates one valve in the RWCU suction and return line.
(e)    Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
JAFNPP                                                       3.3.6.1-10                                    Amendment 298315
 
Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)
Secondary Containment Isolation Instrumentation APPLICABLE MODES OR          REQUIRED OTHER            CHANNELS SPECIFIED            PER            SURVEILLANCE        ALLOWABLE FUNCTION                  CONDITIONS        TRIP SYSTEM        REQUIREMENTS          VALUE
: 1. Reactor Vessel Water                  1, 2, 3,            2          SR 3.3.6.2.1    177 inches Level - Low (Level 3)                  (a)                            SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6
: 2. Drywell Pressure - High              1, 2, 3              2          SR 3.3.6.2.1     2.7 psig SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6
: 3. Reactor Building Exhaust              1, 2, 3,            1          SR 3.3.6.2.1    24,800 cpa Radiation - High                      (a), (b)                        SR 3.3.6.2.3 SR 3.3.6.2.6
: 4. Refueling Floor Exhaust Radiation - High 1, 2, 3, (a), (b)
T1          SR 3.3.6.2.1 SR 3.3.6.2.3 24,800 cpa AF (a) During operation with a potential for draining the reactor vessel.
(b)(a)
SR 3.3.6.2.6 During movement of recently irradiated fuel assemblies in secondary containment.
R D
JAFNPP                                                  3.3.6.2-4                          Amendment 276315
`
 
CREVAS System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1  Control Room Emergency Ventilation Air Supply (CREVAS)
System Instrumentation LCO 3.3.7.1      The Control Room Air Inlet Radiation  High channel 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.
ACTIONS CONDITION T
REQUIRED ACTION                  COMPLETION TIME A. Channel inoperable.
AF    A.1 OR A.2 Place the CREVAS System in the isolate mode of operation.
Declare both CREVAS 1 hour 1 hour R                          subsystems inoperable.
D JAFNPP                                        3.3.7.1-1                          Amendment 276315
 
CREVAS System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS
----------------------------------------------------------NOTE-----------------------------------------------
When the channel is placed in an inoperable status solely for performance of required Surveillances, entry into the Condition and Required Actions may be delayed for up to 6 hours.
------------------------------------------------------------------------------------------------------------------
SURVEILLANCE                                                              FREQUENCY SR 3.3.7.1.1                  Perform CHANNEL CHECK.                                                        In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2                  Perform CHANNEL CALIBRATION. The Allowable                                    In accordance Value shall be  4000 cpm.
T                                        with the Surveillance Frequency Control Program AF R
D JAFNPP                                                          3.3.7.1-2                                            Amendment 301
 
ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1   ECCS-Operating LCO 3.5.1               Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
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.
LCO 3.0.4.b is not applicable to HPCI.
-----------------------------------------------------------------------------------------------------------------------------
------------------------------------------------------------------------------------------------------------------------------
-    CONDITION REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS injection/spray subsystem inoperable.
CONDITION T
OR One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.
REQUIRED ACTION                         COMPLETION TIME A. One low pressure ECCS injection/spray subsystem inoperable.
A.1   Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.
OR One low pressure coolant AF      A.1       Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.
7 days 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.
7 days R
12 hours   36 hours   (continued)
injection (LPCI) pump in both LPCI subsystems inoperable.
B.         D Required Action and associated Completion Time of Condition A not met.
B.1 AND B.2 Be in MODE 3.
Be in Mode 4.
12 hours 36 hours (continued)
JAFNPP                                                    3.5.1-1                                  Amendment 284315


RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-1 Amendment 274 315  3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control E CCS - Shutdown LCO   3.5.2 DRAIN TIME of RPV water inventory to the top of act ive fuel (TAF) shall be > 36 hours. AND   OneTwo low pressure ECCS injection/spray subsystem s shall be   OPERABLE.     -------------------------------------NOTE------------------------------------------------
RPV Water Inventory ControlECCS - Shutdown 3.5.2 3.5     EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2           Reactor Pressure Vessel (RPV) Water Inventory ControlECCS - Shutdown LCO                   3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be > 36 hours.
AND OneTwo low pressure ECCS injection/spray subsystems shall be OPERABLE.
                      -------------------------------------NOTE------------------------------------------------
A 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 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.
----------------------------------------------------------------------------------------------
T
                      ----------------------------------------------------------------------------------------------
APPLICABILITY:
APPLICABILITY:
MODE S 4 and 5   MODES 5, except with the spent fuel storage pool gates the reactor pressure vessel flange.
ACTIONS AF MODES 4 and 5 MODES 5, except with the spent fuel storage pool gates removed and water level  22 ft 2 inches over the top of the reactor pressure vessel flange.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One r Required low pressure ECCS injection/spray subsystem inoperable.
A.
A.1 Restore required low pressure ECCS injection/spray subsystem to OPER ABLE  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).
CONDITION R
Immediately
One rRequired low            A.1 REQUIRED ACTION Restore required low COMPLETION TIME 4 hours D
pressure ECCS injection/spray subsystem inoperable.
pressure ECCS injection/spray subsystem to OPERABLE status.
B.     Required Action and         B.1     Initiate action to establish a           Immediately associated Completion                method of water injection Time of Condition A                  capable of operating not met.                            without offsite electrical power.
Initiate action to suspend operations with.a potential for draining the reactor vessel (OPDRVs).
JAFNPP                                              3.5.2-1                                  Amendment 274315


RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-2 Amendment 274 315  C. DRAIN TIME < 36 hours and  8 hours. C.1 Verify secondary containment boundary is capable of being establish e d in less than t he DRAIN T IME. AND C.2 Verify each secondary containment penetration flow path is capable of being isol at ed in less t h an the DRAIN TIME. AND C.3   Verify one standby gas treatment subsystem is capable of being placed in operation in less than t h e DRAIN T IME. 4 hours          4 hours          4 hours    C. Two required low pressure ECCS injection/spray subsystems inoperable.
RPV Water Inventory ControlECCS - Shutdown 3.5.2 C. DRAIN TIME < 36 hours    C.1    Verify secondary          4 hours and  8 hours.                   containment boundary is capable of being established in less than the DRAIN TIME.
C.1 Initiate action to suspend OPDRVs.
AND C.2     Verify each secondary     4 hours containment penetration flow path is capable of being isolated in less than the DRAIN TIME.
AND Immediately C.2 Restore one required low pressure ECCS injection/spray subsystem to OPERBLE status. 4 hours (continued)
AND C.3 Verify one standby gas       4 hours treatment subsystem is T
capable of being placed in operation in less than the DRAIN TIME.
C. Two required low pressure ECCS injection/spray subsystems inoperable.
AF C.1 AND C.2 Initiate action to suspend OPDRVs.
Restore one required Immediately 4 hours R                  low pressure ECCS injection/spray subsystem to OPERBLE status.
D                                                                    (continued)
JAFNPP                                  3.5.2-2                      Amendment 274315


RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-2 Amendment 274 315  ACTIONS   (continued)
RPV Water Inventory ControlECCS - Shutdown 3.5.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D. DRAIN TIME < 8 hours.Required Action C.2 and E. associated Completion F.D. Time not met. D.1 ------------- NOTE --------------Initiate Required ECCS injection/spray subsystem or additional method of water injection shall be capable of operating without offsite electrical power.
CONDITION                 REQUIRED ACTION                         COMPLETION TIME D. DRAIN TIME < 8         D.1   ------------- NOTE --------------       Immediately hours.Required Action          Initiate Required ECCS C.2 and                        injection/spray subsystem E. associated Completion          or additional method of F.D. Time not met.                  water injection shall be capable of operating without offsite electrical power.
-------------------------------------
                                    -------------------------------------
action to restore secondary containment to OPERABLE status.
action to restore secondary containment to OPERABLE status.
Initiate action to establish an additional method of water injection with water sources capable of maintaining RPV water > TAF for > 36 hours. AND  Immediately D.2 Initiate action to establish secondary containment boundary. restore one standby gas treatment subsystem to OPERABLE status. AND Immediately D.3 Initiate action to isolate each secondary containment penetration flow path or verify it can be manually isolated from the control room.
Initiate action to establish T
restore Isolation capability in each required secondary containment penetration flow path not isolated.
an additional method of water injection with water sources capable of AF AND D.2 maintaining RPV water >
Immediately AND RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-3 Amendment 274 315 D.4 Initiate action to verify o n e standby gas treatment subsystem is capable of being placed in operation.
TAF for > 36 hours.
E. Required Action and associa t ed Completion Time of Condition C or D not met. O R  DRAIN T I ME < 1 hour. E.1 Initiate ac t i o n to restore DRAIN T I ME to  36 hours. Immediately SURVEILLANCE REQUIREMENTS SURVELLANCE FREQUENCY SR 3.5.2.1 Verify DRA I N TIME  3 6 hours. In accorda n ce with the Surveillance Frequency Control Program   SR 3.5.2.1 2  Verify, for each required low pressure coolant injection (LPCI) subsystem, the suppression pool water level is 33 ft. In accordance with the Surveillance Frequency Control Program (continued)
Initiate action to establish secondary containment Immediately R                  boundary. restore standby gas treatment subsystem to OPERABLE status.
one D                  AND D.3   Initiate action to isolate each secondary Immediately containment penetration flow path or verify it can be manually isolated from the control room.
restore Isolation capability in each required secondary containment penetration flow path not isolated.
AND JAFNPP                                    3.5.2-2                              Amendment 274315
 
RPV Water Inventory ControlECCS - Shutdown 3.5.2 D.4     Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.
E. Required Action and       E.1  Initiate action to restore            Immediately associated Completion     DRAIN TIME to  36 hours.
Time of Condition C or D not met.
OR DRAIN TIME < 1 hour.
SURVEILLANCE REQUIREMENTS SURVELLANCE       T                                  FREQUENCY SR 3.5.2.1 SR 3.5.2.12 AF Verify DRAIN TIME  36 hours.
Verify, for each required low pressure coolant injection In accordance with the Surveillance Frequency Control Program In accordance with R
(LPCI) subsystem, the suppression pool water level is 10.33 ft.
the Surveillance Frequency Control Program (continued)
D JAFNPP                                      3.5.2-3                            Amendment 274315
 
RPV Water Inventory ControlECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVELLANCE                                                  FREQUENCY SR 3.5.2.23    Verify for each a required Ccore sSpray (CS) subsystem,                   In accordance with the:                                                                      the Surveillance Frequency Control
: a. Suppression pool water level is 10.33 ft; or                          Program
: b. The water level in each condensate storage Tank is > 324 inches - - - - - - - - - - - - - - -NOTE - - - - - - -
                --------
Only one required CS subsystem may take credit for this option during OPDRVs.
                -----------------------------------
The water level in each condensate storage Tank is  324 inches.
SR 3.5.2.34 T
Verify, for eachthe required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.
In accordance with the Surveillance Frequency Control SR 3.5.2.45                AF
              - - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - - -
One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
Program R------------------------------------
Verify each for the required ECCS injection/spray subsystem, each In accordance with the Surveillance D    manual, power operated, and automatic valve in the flow path, that is not locked, seated, or otherwise secured in position, is in the correct position.
Frequency Control Program (continued)
JAFNPP                                          3.5.2-4                                Amendment 274315


RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-4 Amendment 274 315  SURVEILLANCE REQUIREMENTS (continued)
RPV Water Inventory ControlECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)
SURVELLANCE FREQUENCY SR 3.5.2.2 3  Verify for each a required C c ore s Spray (CS) subsystem,  the:  a. b. The water level in each condensate storage Tank is > 324 inches
SURVELLANCE                                           FREQUENCY SR 3.5.2.56    Operate the required ECCS injection/spray subsystem                   In accordance with through the recirculation line for > 10 minutes.Verify               the Inservice each required ECCS pump develops the                                 Testing Program specified flow rate against a system head corresponding to the specified reactor pressure above primary containment pressure.
- - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - -  Only one required CS subsystem may take credit for this option during OPDRVs.
SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE NO.         ABOVE PRIMARY OF          CONTAINMENT SYSTEM      FLOW RATE              PUMPS      PRESSURE OF 4265 gpm                          113 psi CS LPCI          7700 gpm 1
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -  The water level in each condensate storage Tank is    In accordance with the Surveillance Frequency Control Progra m  SR 3.5.2.3 4  Verify, for each the required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.
1 T        20 psi SR 3.5.2.7 SR 3.5.2.68 AF Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.
In accordance with the Surveillance Frequency Control Progra m  SR 3.5.2.4 5 - - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - - - One LPCI subsystem may be considered OPERABLE during alignment and operation for decay heat removal if capable of being manually realigned and not otherwise inoperable.
              - - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - - -
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Verify each for the required ECCS injection/spray subsystem
Vessel injection/spray may be excluded.
, each  manual, power operated, and automatic valve in the flow path, that is not locked, seated, or otherwise secured in position, is in the correct position.
In accordance with the Surveillance Frequency Control Program R------------------------------------
In accordance with the Surveillance Frequency Control Progra m  (continued)
Verify theeach required ECCS injection/spray subsystem actuates on an a manual actual or simulated automatic In accordance with the Surveillance D    initiation signal.                                                    Frequency Control Program JAFNPP                                            3.5.2-5                        Amendment 274315


RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-5 Amendment 274 315  SURVEILLANCE REQUIREMENTS (continued)
RCIC SYSTEM 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO 3.5.3          The RCIC System shall be OPERABLE.
SURVELLANCE FREQUENCY  SR 3.5.2.5 6  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 pressure above primary containment pressure. SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE    NO. ABOVE PRIMARY OF CONTAINMENT SYSTEM FLOW  RATE  PUMPS PRESSURE OF C S    1  LPCI  7700  gpm  1    In accordance with the Inservice Testing Program  SR 3.5.2.7 Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.
APPLICABILITY:      MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
In accordance with the Surveillance Frequency Control Program  SR 3.5.2.6 8  - - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - - - Vessel injection/spray may be excluded.
ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -  Verify theeach required ECCS injection/spray subsystem actuates on an a manual actual or simulated automatic initiation signal.
-----------------------------NOTE--------------------------------
In accordance with the Surveillance Frequency Control Program RCIC SYSTEM 3.5.3 JAFNPP 3.5.3-1 Amendment 2 84 315  3.5  EMERGENCY CORE COOLING SYSTEMS (E CCS), RPV WATER INVENTORY CONTROL,  AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 RCIC System LCO  3.5.3 The RCIC System shall be OPERABLE.
LCO 3.0.4.b is not applicable to RCIC.
APPLICABILITY:
-----------------------------------------------------------------
MODE 1, MODES 2 and 3 with reactor steam dome pressure >
CONDITION T
150 psig. ACTIONS NOTE LCO 3.0.4.b is not applicable to RCIC.
REQUIRED ACTION                COMPLETION TIME A. RCIC System inoperable.
AF A.1    Verify by administrative means High Pressure Coolant Injection System is OPERABLE.
Immediately R              AND A.2    Restore RCIC System to OPERABLE status.
14 days B.
D Required Action and associated Completion Time not met.
B.1 AND Be in MODE 3.                 12 hours B.2    Reduce reactor steam          36 hours dome pressure to 150 psig.
JAFNPP                                   3.5.3-1                       Amendment 284315
 
PCIVs 3.6.1.3 ACTIONS (continued)
CONDITION            REQUIRED ACTION                COMPLETION TIME F. Required Action and      F.1    Be in MODE 3.         12 hours associated Completion Time of Condition A,    AND B, C, D, or E not met In MODE 1, 2, or 3.      F.2    Be in MODE 4.          36 hours G. Required Action and     G.1    Initiate action to    Immediately associated Completion          suspend operations Time of Condition A or          with a potential for B not met for PCIV(s)          draining the reactor required to be                  vessel.
OPERABLE during Mode 4 or 5.                    OR T
G.2 Initiate action to        Immediately AF  restore valve(s) to OPERABLE status.
R D
JAFNPP                              3.6.1.3-6                    Amendment 274315


CONDITION REQUIRED ACTION COMPLETION TIME  A. RCIC System inoperable.
Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1         The secondary containment shall be OPERABLE.
A.1  Verify by administrative means High Pressure Coolant Injection System is OPERABLE. AND  A.2  Restore RCIC System to OPERABLE status.
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).
Immediately 14 days  B. Required Action and associated Completion Time not met.
ACTIONS A.
B.1 Be in MODE
CONDITION Secondary containment      A.1 T
: 3. AND  B.2  Reduce reactor steam dome pressure to 50 psig. 12 hours    36 hours PCIVs 3.6.1.3 JAFNPP 3.6.1.3-6 Amendment 274 315  ACTIONS  (continued)
REQUIRED ACTION Restore secondary COMPLETION TIME 4 hours B.
CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and associated Completion Time of Condition A, B, C, D, or E not met In MODE 1, 2, or 3.
inoperable in MODE 1, 2, or 3.
F.1 Be in MODE 3.
Required Action and AF B.1 containment to OPERABLE status.
AND  F.2 Be in MODE 4.
Be in MODE 3.                       12 hours not met. R associated Completion Time of Condition A       AND B.2    Be in MODE 4.                       36 hours C.
12 hours   36 hours    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. OR  Immediately G.2 Initiate action to restore valve(s) to OPERABLE status.
D Secondary containment inoperable during movement of recently irradiated fuel C.1     ------------NOTE------------
Immediately
LCO 3.0.3 is not applicable.
                                      ---------------------------------
assemblies in the secondary containment            Suspend movement of recently        Immediately or during OPDRVs.                 irradiated fuel assemblies in the secondary containment.
AND (continued)
JAFNPP                                      3.6.4.1-1                        Amendment 276315


Secondary Containment 3.6.4.1   JAFNPP 3.6.4.1-1 Amendment 276 315 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO  3.6.4.1 The secondary containment shall be OPERABLE.
Secondary Containment 3.6.4.1 ACTIONS (continued)
APPLICABILITY:
CONDITION                    REQUIRED ACTION                  COMPLETION TIME C. (continued)                C.2    Initiate action to suspend      Immediately OPDVRVs.
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).
SURVEILLANCE REQUIREMENTS SURVEILLANCE                                    FREQUENCY SR 3.6.4.1.1 of vacuum water gauge.     T Verify secondary containment vacuum is 0.25 inch      In accordance with the Surveillance Frequency Control SR 3.6.4.1.2              AF Verify all secondary containment equipment hatches are closed and sealed.
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
Program In accordance with the Surveillance Frequency Control Program SR 3.6.4.1.3    R Verify one secondary containment access door in each access opening is closed.
: 3. AND  B.2 Be in MODE
In accordance with the Surveillance D
: 4. 12 hours   36 hours  C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs
SR 3.6.4.1.4    Verify the secondary containment can be maintained 0.25 inch of vacuum water gauge for 1 hour using Frequency Control Program In accordance with the Surveillance one SGT subsystem at a flow rate 6000 cfm.            Frequency Control Program JAFNPP                                  3.6.4.1-2                      Amendment 301315
. C.1  ------------NOTE------------  LCO 3.0.3 is not applicable.
  ---------------------------------
Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND        Immediately (continued)


Secondary Containment 3.6.4.1  JAFNPP 3.6.4.1-2 Amendment 301 315  ACTIONS  (continued)
SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)
CONDITION REQUIRED ACTION COMPLETION TIME C.  (continued)
LCO 3.6.4.2               Each SCIV shall be OPERABLE.
C.2 Initiate action to suspend OPDVRVs. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY  SR  3.6.4.1.1 Verify secondary containment vacuum is 0.25 inch  of vacuum water gauge.
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).
In accordance with the Surveillance Frequency Control Program  SR  3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.
ACTIONS
In accordance with the Surveillance Frequency Control Program  SR  3.6.4.1.3 Verify one secondary containment access door in each access opening is closed.
----------------------------------------------------NOTES----------------------------------------------------
In accordance with the Surveillance Frequency Control Program  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  6000 cfm. In accordance with the Surveillance Frequency Control Program SCIVs 3.6.4.2   JAFNPP 3.6.4.2-1 Amendment 27 6 315 3.6  CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)
: 1. Penetration flow paths may be unisolated intermittently under 2.
LCO 3.6.4.2 Each SCIV shall be OPERABLE.
administrative controls.
APPLICABILITY:
T Separate Condition entry is allowed for each penetration flow path.
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).
2.
ACTIONS ----------------------------------------------------NOTES----------------------------------------------------
AF Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.
: 1. Penetration flow paths may be unisolated intermittently under administrative controls.
-------------------------------------------------------------------------------------------------------------------
: 2. Separate Condition entry is allowed for each penetration flow path.
CONDITION                             REQUIRED ACTION                         COMPLETION TIME A.                       R One or more penetration flow paths with one A.1       Isolate the affected penetration flow path 8 hours D
: 2. Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.
SCIV inoperable.                              by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.
-------------------------------------------------------------------------------------------------------------------
AND (continued)
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration flow paths with one SCIV inoperable.
JAFNPP                                                  3.6.4.2-1                                  Amendment 276315
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 hours            (continued)


SCIVs 3.6.4.2  JAFNPP 3.6.4.2-2 Amendment 27 4  ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
SCIVs 3.6.4.2 ACTIONS CONDITION                     REQUIRED ACTION                   COMPLETION TIME A.   (continued)                 A.2   --------NOTES--------
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.
: 1. Isolation devices in high radiation areas may be verified by use of administrative means.
B. ---------NOTE---------  Only applicable to penetration flow paths with two isolation valves. ----------------------
: 2. Isolation devices that are locked, sealed, or otherwise secured may be verified by use of T
administrative means.
                                        -----------------------------
B. ---------NOTE---------
AF B.1 Verify the affected penetration flow path is isolated.
Isolate the affected Once per 31 days.
4 hours R
Only applicable to penetration flow paths with two isolation valves.
penetration flow path by use of at least one closed and de-activated D
    ----------------------
One or more penetration flow paths with two SCIVs inoperable.
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.
automatic valve, closed manual valve, or blind flange.
4 hours    C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1  Be in MODE
C. Required Action and         C.1        Be in MODE 3.              12 hours associated Completion Time of Condition A         AND or B not met in MODE 1, 2, or 3.           C.2       Be in MODE 4.               36 hours (continued)
: 3. AND  C.2 Be in MODE
JAFNPP                                      3.6.4.2-2                            Amendment 274
: 4. 12 hours    36 hours   (continued)


SCIVs 3.6.4.2 JAFNPP 3.6.4.2-3 Amendment 276 315  ACTIONS (continued)
SCIVs 3.6.4.2 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.
CONDITION                 REQUIRED ACTION               COMPLETION TIME D. Required Action and     D.1 --------NOTE---------
---------------------
associated Completion      LCO 3.0.3 is not Time of Condition A        applicable.
Suspend movement of recently irradiated fuel assemblies in the secondary containment.
or B not met during        ---------------------
AND D.2Initiate action to suspend OPDRVs.       Immediately Immediately
movement of recently irradiated fuel        Suspend movement of             Immediately assemblies in the              recently irradiated secondary                      fuel assemblies in containment or during          the secondary OPDRVs.                        containment.
AND T
D.2Initiate action to suspend OPDRVs.
Immediately AF R
D JAFNPP                                  3.6.4.2-3                    Amendment 276315


SCIVs 3.6.4.2  JAFNPP 3.6.4.2-4 Amendment 301 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.
SCIVs 3.6.4.2 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.
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.
: 2. Not required to be met for SCIVs that are open under administrative controls.
In accordance With the Surveillance Frequency Control Program SR 3.6.4.2.2 Verify the isolation time of each power operated, automatic SCIV is within limits.
              -----------------------------------------------------------
In accordance with the Surveillance Frequency Control Program SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation position on an actual or simulated actuation signal.
Verify each secondary containment isolation                   In accordance manual valve and blind flange that is not locked,             With the sealed, or otherwise secured and is required to be           Surveillance closed during accident conditions is closed.                 Frequency T                              Control Program SR 3.6.4.2.2 AF Verify the isolation time of each power operated, automatic SCIV is within limits.
In accordance with the Surve illance Frequ e ncy Control Program SGT System 3.6.4.3  JAFNPP 3.6.4.3-1 Amendment 276 315 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.
In accordance with the Surveillance Frequency Control Program SR 3.6.4.2.3 R
APPLICABILITY:
Verify each automatic SCIV actuates to the isolation position on an actual or simulated actuation signal.
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).
In accordance with the Surveillance D                                                                  Frequency Control Program JAFNPP                                  3.6.4.2-4                                Amendment 301
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem inoperable.
 
A.1 Restore SGT subsystem to OPERABLE status.
SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3       Two SGT subsystems shall be OPERABLE.
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
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).
: 3. AND  B.2  Be in MODE
ACTIONS CONDITION                       REQUIRED ACTION                       COMPLETION TIME A. One SGT subsystem inoperable.
: 4. 12 hours   36 hours       C. Required Action and associated Completion Time of Condition A   not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs
A.1               T 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.
----NOTE---------------- LCO 3.0.3 is not applicable.
AF  B.1 AND B.2 Be in MODE 3.
---------------------------------------- C.1   Place OPERABLE SGT subsystem in operation.
Be in MODE 4.
OR   Immediately (continued)
12 hours 36 hours R
C.
D Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment
                                  ----------------NOTE----------------
LCO 3.0.3 is not applicable.
                                  ----------------------------------------
C.1     Place OPERABLE SGT subsystem in operation.
Immediately or during OPDRVs.            OR (continued)
JAFNPP                                          3.6.4.3-1                            Amendment 276315
 
SGT System 3.6.4.3 ACTIONS CONDITION                  REQUIRED ACTION                COMPLETION TIME C.  (continued)            C.2.1  Suspend movement of          Immediately recently irradiated fuel assemblies in secondary containment.
AND C.2.2    Initiate action to          Immediately suspend OPDRVs.
D. Two SGT subsystems    D.1      Enter LCO 3.0.3.            Immediately inoperable in MODE 1, 2, or 3.
E. Two SGT subsystems      E.1 T
                                      --------NOTE---------
inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.
AF        LCO 3.0.3 is not applicable.
                                      -------------------------
Suspend movement of recently irradiated fuel assemblies in secondary Immediately R        AND containment.
D                  E.2      Initiate action to suspend OPDRVs.
Immediately JAFNPP                                  3.6.4.3-2                        Amendment 276315
 
SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                      FREQUENCY SR 3.6.4.3.1  Operate each SGT subsystem for  10 continuous        In accordance hours with heaters operating.                        with the Surveillance Frequency Control Program SR 3.6.4.3.2  Perform required SGT filter testing in accordance    In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.4.3.3 T
Verify each SGT subsystem actuates on an actual or simulated initiation signal.
In accordance With the Surveillance SR 3.6.4.3.4 AF Manually cycle each SGT subsystem filter cooling cross-tie valve.
Frequency Control Program In accordance With the Surveillance R                                                    Frequency Control Program D
JAFNPP                              3.6.4.3-3                          Amendment 301


SGT System 3.6.4.3 JAFNPP 3.6.4.3-2 Amendment 276 315 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)
CREVAS System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS) System LCO 3.7.3           Two CREVAS subsystems shall be OPERABLE.
C.2.1  Suspend movement of recently irradiated fuel assemblies in secondary containment.
                    ----------------------------------- NOTE --------------------------------------
AND  C.2.2  Initiate action to suspend OPDRVs.
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
Immediately 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.
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).
E.1  --------NOTE---------   LCO 3.0.3 is not applicable.
ACTIONS CONDITION T
  -------------------------   Suspend movement of recently irradiated fuel assemblies in secondary containment.
REQUIRED ACTION                        COMPLETION TIME A.
AND E.2   Initiate action to suspend OPDRVs.
B.
Immediately Immediately
One CREVAS subsystem inoperable for reasons other than Condition B.
One or more CREVAS AF      A.1 B.1 Restore CREVAS subsystem to OPERABLE status.
Initiate action to 7 days Immediately R
subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3.                          AND implement mitigating actions.
D                          B.2       Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed 24 hours limits.
AND B.3      Restore CRE boundary to               90 days OPERABLE status.
(continued)
JAFNPP                                          3.7.3-1                                Amendment 289315


SGT System 3.6.4.3     JAFNPP 3.6.4.3-3 Amendment 301 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY  SR  3.6.4.3.1 Operate each SGT subsystem for  10 continuous hours with heaters operating.
CREVAS System 3.7.3 ACTIONS (continued)
In accordance with the Surv eillance Freq uency  Control Program  SR  3.6.4.3.2 Perform required SGT filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
CONDITION                        REQUIRED ACTION                COMPLETION TIME C. Required Action and          C.1      Be in MODE 3.                   12 hours associated Completion Time of Condition A or B not met   AND in MODE 1, 2, or 3.
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 Surv eillance Freq uency  Contr ol Program   SR  3.6.4.3.4 Manually cycle each SGT subsystem filter cooling cross-tie valve.
C.2     Be in MODE 4.                   36 hours D. Required Action and          -------------- NOTE --------------
In accordance With the Surv eillance Freq uency  Control Program CREVAS System 3.7.3  JAFNPP 3.7.3-1 Amendment 2 89 315 3.7  PLANT SYSTEMS 3.7.3  Control Room Emergency Ventilation Air Supply (CREVAS) System LCO  3.7.3 Two CREVAS subsystems shall be OPERABLE.
associated Completion Time   LCO 3.0.3 is not applicable.
  -----------------------------
of Condition A not met        --------------------------------------
------ NOTE ------------------------------
during movement of recently irradiated fuel     D.1      Place OPERABLE CREVAS          Immediately assemblies in the secondary           subsystem in isolate mode.
--------   The control room envelope (CRE) boundary may be opened intermittently under administrative control.
containment or during OPDRVs.                       OR T
  -----------------------------------------------------------------------------------
D.2.1 Suspend movement of                Immediately AF    AND recently irradiated fuel assemblies in the secondary containment.
APPLICABILITY:
D.2.2 Initiate action to suspend        Immediately E.
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).
R Two CREVAS subsystems         E.1 OPDRVs.
ACTIONS  CONDITION REQUIRED ACTION COMPLETION TIME A. One CREVAS subsystem inoperable for reasons other than Condition B
Enter LCO 3.0.3.                Immediately D
. A.1  Restore CREVAS subsystem to OPERABLE status. 7 days  B. One or more CREVAS 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.
inoperable in MODE 1, 2, or 3 for reasons other than Condition B.
Immediately 24 hours        90 days    (continued)
(continued)
JAFNPP                                      3.7.3-2                        Amendment 289315


CREVAS System 3.7.3   JAFNPP 3.7.3-2 Amendment 289 315 ACTIONS (continued)
CREVAS System 3.7.3 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 F. Two CREVAS subsystems            --------------- NOTE ---------------
: 3. AND  C.2  Be in MODE
inoperable during movement      LCO 3.0.3 is not applicable.
: 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.  --------------
of recently irradiated fuel      ----------------------------------------
NOTE --------------
assemblies in the secondary containment or during            F.1     Suspend movement of               Immediately OPDRVs.                                  recently irradiated fuel assemblies in the OR                                        secondary containment.
LCO 3.0.3 is not applicable.
One or more CREVAS              AND subsystems inoperable due to an inoperable CRE            F.2     Initiate action to suspend       Immediately boundary during movement                OPDRVs.
--------------------------------------
of recently irradiated fuel in the secondary containment or during OPDRVs.
D.1  Place OPERABLE CREVAS subsystem in isolate mode.
T SURVEILLANCE REQUIREMENTS AF SURVEILLANCE                                          FREQUENCY SR 3.7.3.1         R Operate each CREVAS subsystem for 15 minutes.                  In accordance with the Surveillance D
OR  D.2.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
SR 3.7.3.2    Perform required CREVAS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
AND D.2.2 Initiate action to suspend OPDRVs.     Immediately Immediately Immediately E. Two CREVAS subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.
Frequency Control Program In accordance with the VFTP (continued)
E.1  Enter LCO 3.0.3. Immediately (continued)
JAFNPP                                        3.7.3-3                            Amendment 301315


CREVAS System 3.7.3   JAFNPP 3.7.3-3 Amendment 301 315 ACTIONS  (continued)
CREVAS System 3.7.3 SURVEILLANCE REQUIREMENTS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREVAS subsystems inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. OR  One or more CREVAS subsystems inoperable due to an inoperable CRE boundary during movement of recently irradiated fuel in the secondary containment or during OPDRVs.
SURVEILLANCE                                       FREQUENCY SR 3.7.3.3  Perform required CRE unfiltered air in-leakage testing in  In accordance with accordance with the control room Envelope Habitability      the Control Room Program.                                                    Envelope Habitability Program T
  -------------
AF R
-- NOTE ---------------
D JAFNPP                                    3.7.3-4                            Amendment 289
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 3.7.3.1 Operate each CREVAS subsystem for  15 minutes. In accordance with the Surveillance Frequency Control Program   SR  3.7.3.2 Perform required CREVAS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).
In accordance with the VFTP (continued)


CREVAS System 3.7.3  JAFNPP 3.7.3-4 Amendment 289  SURVEILLANCE REQUIREMENTS (continued)
Control Room AC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4           Two control room AC subsystems shall be OPERABLE.
SURVEILLANCE FREQUENCY  SR  3.7.3.3 Perform required CRE unfiltered air in
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).
-leakage testing in accordance with the control room Envelope Habitability Program. In accordance with the Control Room Envelope Habitability Program Control Room AC System 3.7.4   JAFNPP 3.7.4-1 Amendment 290  315  3.7  PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC subsystems shall be OPERABLE.
ACTIONS CONDITION                   REQUIRED ACTION               COMPLETION TIME A. One control room AC subsystem inoperable.
APPLICABILITY:
A.1           T Restore control room AC subsystem to OPERABLE 30 days B. Two control room AC subsystems 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 control room AC subsystem inoperable.
AF B.1 status.
A.1   Restore control room AC subsystem to OPERABLE status. 30 days B. Two control room AC subsystems inoperable.
Verify control room area temperature < 90 &deg;F.
B.1   Verify control room area temperature  
Once per 4 hours R              AND B.2   Restore one control           72 hours C.
< 90 &deg;F. AND B.2 Restore one control room AC subsystem to OPERABLE status.
D Required Action and associated Completion C.1 room AC subsystem to OPERABLE status.
Once per 4 hours 72 hours C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1  Be in MODE 3.
Be in MODE 3.                12 hours Time of Condition A or B   AND not met in MODE 1, 2, or
AND  C.2 Be in MODE 4.
: 3.                         C.2   Be in MODE 4.                 36 hours (continued)
12 hours    36 hours     (continued)
JAFNPP                                    3.7.4-1                  Amendment 290 315


Control Room AC System 3.7.4   JAFNPP 3.7.4-2 Amendment 290          315 ACTIONS (continued)
Control Room AC System 3.7.4 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME 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.
CONDITION                       REQUIRED ACTION                     COMPLETION TIME D. Required Action and       - - - - - - - - - NOTE - - - - - - - - - -
  - - - - - - - - - NOTE - - - - - - - - - - LCO 3.0.3 is not applicable.
associated Completion      LCO 3.0.3 is not applicable.
- - - - - - - - - - - - - - - - - - - - - - - -  D.1 Place OPERABLE control room AC subsystem in operation.
Time of Condition A not    ------------------------
OR D.2.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
met during movement of recently irradiated fuel   D.1     Place OPERABLE                       Immediately assemblies in the                  control room AC secondary containment or            subsystem in during OPDRVs.                      operation.
AND  D.2.2 Initiate action to suspend OPDRVs.       Immediately 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.
OR T
  - - - - - - - - -  NOTE - - - - - - - - - -  LCO 3.0.3 is not applicable.
D.2.1 Suspend movement of recently irradiated fuel assemblies in the Immediately AF    AND secondary containment.
- - - - - - - - - - - - - - - - - - - - - - - -   E.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
D.2.2 Initiate action to suspend OPDRVs.
AND E.2 Initiate action to suspend OPDRVs.       Immediately Immediately SURVEILLANCE REQUIREMENTS
Immediately E.
R Required Action and       - - - - - - - - - NOTE - - - - - - - - - -
D associated Completion Time of Condition B not met during movement of recently irradiated fuel assemblies in the secondary containment or LCO 3.0.3 is not applicable.
                                ------------------------
E.1     Suspend movement of recently irradiated fuel assemblies in the Immediately during OPDRVs.                    secondary containment.
AND E.2     Initiate action to suspend           Immediately OPDRVs.
SURVEILLANCE REQUIREMENTS JAFNPP                                    3.7.4-2                  Amendment 290            315


Control Room AC System 3.7.4   JAFNPP 3.7.4-3 Amendment 301  SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the capability to remove the assumed heat load.
Control Room AC System 3.7.4 SURVEILLANCE                               FREQUENCY SR 3.7.4.1   Verify each control room AC subsystem has the     In accordance capability to remove the assumed heat load.       with the Surveillance Frequency Control Program T
In accordance with the Surveillance Frequency Control Program
AF R
D JAFNPP                              3.7.4-3                  Amendment 301


AC Sources
AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2         The following AC electrical power sources shall be OPERABLE:
- Shutdown 3.8.2  JAFNPP 3.8.2-1 Amendment 276 315 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources
: a. One qualified circuit between the offsite transmission network and one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown";
- Shutdown   LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:
: b. One qualified circuit, which maybe the same circuit required by LCO 3.8.2.a, between the offsite transmission network and the other division of the plant Class 1E AC electrical power distribution subsystem(s),
: a. One qualified circuit between the offsite transmission network and one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems
when a second division is required by LCO 3.8.8; and
-Shutdown";
: c. One emergency diesel generator (EDG) subsystem capable T
: b. One qualified circuit, which maybe the same circuit required by LCO 3.8.2.a, between the offsite transmission network and the other division of the plant Class 1E AC electrical power distribution subsystem(s), when a second division is required by LCO 3.8.8; and
of supplying one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.
: c. One emergency diesel generator (EDG) subsystem capable of supplying one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8. APPLICABILITY:
APPLICABILITY:           AF 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.
R D
JAFNPP                                  3.8.2-1                        Amendment 276315


AC Sources
AC Sources - Shutdown 3.8.2 ACTIONS
- Shutdown 3.8.2  JAFNPP 3.8.2-2 Amendment 276 315 ACTIONS -------------------------------------------------
----------------------------------------------------------NOTE-----------------------------------------------------------
---------NOTE-----------------------------------------------------------
LCO 3.0.3 is not applicable.
LCO 3.0.3 is not applicable.
-----------------------------------------------------------------------------------------------------------------------------
-----------------------------------------------------------------------------------------------------------------------------
CONDITION REQUIRED ACTION COMPLETION TIME A. One or both required offsite circuits inoperable.
CONDITION                                 REQUIRED ACTION                       COMPLETION TIME A. One or both required               -------------------NOTE------------------
  -------------------NOTE------------------
offsite circuits                    Enter applicable Condition inoperable.                        and Required Actions of LCO 3.8.8, when any required division is de-energized as a result of Condition A.
Enter applicable Condition and Required Actions of LCO 3.8.8, when any required division is de
                                            ---------------------------------------------
-energized as a result of Condition A. --------------------------------------------
A.1     Declare affected                       Immediately required feature(s),
A.1 Declare affected required feature(s),   with no offsite power available,    inoperable.
available,T with no offsite power inoperable.
OR A.2.1 Suspend CORE ALTERATIONS.
AF  OR A.2.1 Suspend CORE ALTERATIONS.
AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
AND Immediately R                  A.2.2 Suspend movement of recently irradiated fuel assemblies in Immediately D                                    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                         Immediately suspend operations with a potential for draining the reactor vessel (OPDRVs).
AND            Immediately Immediately Immediately Immediately (continued)
AND (continued)
JAFNPP                                                    3.8.2-2                                  Amendment 276315
 
AC Sources - Shutdown 3.8.2 ACTIONS CONDITION                REQUIRED ACTION                COMPLETION TIME A. (continued)           A.2.34 Initiate action to restore    Immediately required offsite power circuit(s) to OPERABLE status.
B. One required EDG        B.1    Suspend CORE                Immediately subsystem inoperable.          ALTERATIONS.
AND B.2    Suspend movement of          Immediately recently irradiated secondary T
fuel assemblies in containment.
AF AND B.3 AND Initiate action to suspend OPDRVs.
Immediately R        B.34            Initiate action to restore required EDG subsystem to OPERABLE status.
Immediately D
JAFNPP                                  3.8.2-3                    Amendment 276315


AC Sources
AC Sources  Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE                                          FREQUENCY SR 3.8.2.1  ---------------------------NOTES---------------------
  - Shutdown 3.8.2   JAFNPP 3.8.2-3 Amendment 276 315 ACTIONSCONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
: 1. The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11, SR 3.8.1.12, and SR 3.8.1.13.
A.2.3 4  Initiate action to restore required offsite power circuit(s) to OPERABLE status.
: 2. SR 3.8.1.10 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 - ShutdownRPV Water Inventory Control."
Immediately B. One required EDG subsystem inoperable.
            ------------------------------------------------------------
B.1 Suspend CORE ALTERATIONS.
SRs of Specification 3.8.1, except SR 3.8.1.7, are applicable.
AND  B.2  Suspend movement of recently irradiated fuel assemblies in secondary containment.
T For AC sources required to be OPERABLE the                    In accordance with applicable SRs AF R
AND  B.3  Initiate action to suspend OPDRVs.
D JAFNPP                                      3.8.2-4                        Amendment 274315
AND  B.3 4  Initiate action to restore required EDG subsystem to OPERABLE status. Immediately Immediately Immediately Immediately


AC SourcesShutdown  3.8.2  JAFNPP 3.8.2-4 Amendment 27 4 315  SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY  SR  3.8.2.1  ---------------------------NOTES---------------------
DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources Shutdown LCO 3.8.5                 One 125 VDC electrical power subsystem shall be OPERABLE to support one division of the plant Class IE DC Electrical Power Distribution System required by LCO 3.8.8, "Distribution Systems - Shutdown."
: 1. The following SRs are not required to be performed:  SR 3.8.1.3, SR 3.8.1.8,  SR 3.8.1.9, SR 3.8.1.11, SR 3.8.1.12,  and SR 3.8.1.13.
APPLICABILITY:             MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
: 2. SR 3.8.1.10 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-ShutdownRPV Water Inventory Control
ACTIONS T
." ------------------------------------------------------------
-----------------------------------------------------------NOTE----------------------------------------------------------
For AC sources required to be OPERABLE the SRs of Specification 3.8.1, except SR 3.8.1.7, are applicable.
In accordance with applicable SRs DC Sources
- Shutdown 3.8.5   JAFNPP 3.8.5-1 Amendment 276 3.8  ELECTRICAL POWER SYSTEMS 3.8.5  DC SourcesShutdown  LCO 3.8.5 One 125 VDC electrical power subsystem shall be OPERABLE to support one division of the plant Class IE 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.
LCO 3.0.3 is not applicable.
-----------------------------------------------------------------------------------------------------------------------------
A.
CONDITION  REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable.
CONDITION Required DC electrical AF
A.1  Declare affected required feature(s) inoperable.
-----------------------------------------------------------------------------------------------------------------------------
OR  A.2.1 Suspend CORE ALTERATIONS.
A.1 REQUIRED ACTION Declare affected COMPLETION TIME Immediately power subsystem inoperable.
AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
R                    OR required feature(s) inoperable.
AND   Immediately Immediately Immediately (continued)
D                                  A.2.1 Suspend CORE ALTERATIONS.
AND Immediately A.2.2 Suspend movement of                       Immediately recently irradiated fuel assemblies in the secondary containment.
AND (continued)
JAFNPP                                                    3.8.5-1                                      Amendment 276
 
DC Sources - Shutdown 3.8.5 ACTIONS CONDITIONS                              REQUIRED ACTION          COMPLETION TIME A. (continued)                          A.2.3      Initiate action to    Immediately suspend operations with a potential for draining the reactor vessel.
AND A.2.34 Initiate action to        Immediately restore required DC electrical power subsystem to OPERABLE status.
T SURVEILLANCE REQUIREMENTS AF SR 3.8.5.1 R        SURVEILLANCE
                -----------------------NOTE----------------------
FREQUENCY D      The following SRs are not required to be performed: SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.
                ------------------------------------------------------
For DC electrical power subsystem required                  In accordance to be OPERABLE the following SRs are                        with applicable applicable:                                                SRs SR 3.8.4.1, SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.
JAFNPP                                            3.8.5-2                  Amendment 274315


DC Sources
Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems Shutdown LCO 3.8.8                 The necessary portions of the AC and 125 VDC electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.
-Shutdown  3.8.5  JAFNPP 3.8.5-2 Amendment 27 4 315  ACTIONS CONDITIONS REQUIRED ACTION COMPLETION TIME A. (continued)
APPLICABILITY:             MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.
A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel. AND  A.2.3 4 Initiate action to restore required DC electrical power subsystem to OPERABLE status. Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY  SR  3.8.5.1 -----------------------NOTE--------------------
ACTIONS
--  The following SRs are not required to be performed:  SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.  ------------------------------------------------------
-------------------------------------------------------NOTE----------------------------------------------------------
For DC electrical power subsystem required to be OPERABLE the following SRs are applicable:
SR 3.8.4.1, SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.        In accordance with applicable SRs Distribution Systems
- Shutdown 3.8.8   JAFNPP 3.8.8-1 Amendment 276 315 3.8  ELECTRICAL POWER SYSTEMS 3.8.8  Distribution SystemsShutdown  LCO 3.8.8 The necessary portions of the AC and 125 VDC 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.
LCO 3.0.3 is not applicable.
-------------------------------------------------------------------------------------------------------------------------
T
CONDITION  REQUIRED ACTION COMPLETION TIME A. One or more required AC or 125 VDC electrical power distribution subsystems inoperable.
-------------------------------------------------------------------------------------------------------------------------
A.1   Declare associated supported required feature(s) inoperable.
A.
OR A.2.1 Suspend CORE ALTERATIONS.
CONDITION One or more required AC or 125 VDC electrical power distribution AF      A.1 REQUIRED ACTION Declare associated supported required feature(s) inoperable.
AND A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.
COMPLETION TIME Immediately R
AND   Immediately Immediately Immediately (continued)
subsystems inoperable.
OR A.2.1 Suspend CORE                             Immediately D                                        ALTERATIONS.
AND A.2.2 Suspend movement of recently irradiated Immediately fuel assemblies in the secondary containment.
AND (continued)
JAFNPP                                                    3.8.8-1                                  Amendment 276315


Distribution Systems
Distribution Systems - Shutdown 3.8.8 ACTIONS (continued)
- Shutdown 3.8.8   JAFNPP 3.8.8-2 Amendment 301 315  ACTIONS (continued)
A. (continued)
A. (continued)
A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel. AND A.2.3 4  Initiate actions to restore required AC and 125 VDC electrical power distribution subsystems to OPERABLE status.
A.2.3   Initiate action to suspend   Immediately operations with a potential for draining the reactor vessel.
AND A.2.4 5  Declare associated required shutdown cooling subsystem(s) inoperable.
AND A.2.34 Initiate actions to restore   Immediately required AC and 125 VDC electrical power distribution subsystems to OPERABLE status.
Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and voltage to required AC and 125 VDC electrical power distribution subsystems.
AND T
In accordance with the Surveillance Frequency Control Program}}
A.2.45 Declare associated required shutdown cooling Immediately AF            subsystem(s) inoperable.
R SURVEILLANCE REQUIREMENTS SURVEILLANCE                                   FREQUENCY D
SR 3.8.8.1       Verify correct breaker alignments and voltage to required AC and 125 VDC electrical power distribution subsystems.
In accordance with the Surveillance Frequency Control Program JAFNPP                                      3.8.8-2                      Amendment 301315}}

Revision as of 18:54, 29 October 2019

Pre-Submittal Draft FitzPatrick TSTF-542 Combined Markups (Technical Specifications Only)
ML17261A743
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 09/18/2017
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Venkataraman, B, NRR/DORL/LPL1
References
Download: ML17261A743 (62)


Text

TABLE OF CONTENTS 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) 2.1 SLs ................................................................................................... 2.0-1 2.2 SL Violations ...................................................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY .......... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ......................... 3.0-3 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 3.1.4 3.1.5 3.1.6 T

Control Rod OPERABILITY ............................................................... 3.1.3-1 Control Rod Scram Times .................................................................. 3.1.4-1 Control Rod Scram Accumulators ...................................................... 3.1.5-1 Rod Pattern Control ........................................................................... 3.1.6-1 3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 3.3 AF Standby Liquid Control (SLC) System ................................................ 3.1.7-1 Scram Discharge Volume (SDV) Vent and Drain Valves .................... 3.1.8-1 POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)3.2.1-1 MINIMUM CRITICAL POWER RATIO (MCPR) .................................. 3.2.2-1 LINEAR HEAT GENERATION RATE (LHGR) ................................... 3.2.3-1 INSTRUMENTATION 3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.2 R Reactor Protection System (RPS) Instrumentation ............................ 3.3.1.1-1 Source Range Monitor (SRM) Instrumentation................................... 3.3.1.2-1 Control Rod Block Instrumentation ..................................................... 3.3.2.1-1 Feedwater and Main Turbine High Water Level Trip Instrumentation ................................................................... 3.3.2.2-1 3.3.3.1 3.3.3.2 3.3.4.1 3.3.5.1 3.3.5.2 3.3.5.23 D

Post Accident Monitoring (PAM) Instrumentation ............................... 3.3.3.1-1 Remote Shutdown System ................................................................. 3.3.3.2-1 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation ................................... 3.3.4.1-1 Emergency Core Cooling System (ECCS) Instrumentation ................ 3.3.5.1-1 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation.3.3.5.2-1 Reactor Core Isolation Cooling (RCIC) System Instrumentation .......................................................................... 3.3.5.23-1 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 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS)

System Instrumentation ............................................................. 3.3.7.1-1 3.3.7.2 Condenser Air Removal Pump Isolation Instrumentation ................... 3.3.7.2-1 3.3.7.3 Emergency Service Water (ESW) System Instrumentation................ 3.3.7.3-1 JAFNPP i Amendment 287

TABLE OF CONTENTS (continued)

T AF R

D JAFNPP i Amendment 287

TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 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 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating ................................................... 3.4.1-1 3.4.2 Jet Pumps .................................................................................. 3.4.2-1 3.4.3 Safety/Relief Valves (S/RVs) ...................................................... 3.4.3-1 3.4.4 RCS Operational LEAKAGE....................................................... 3.4.4-1 3.4.5 RCS Leakage Detection Instrumentation ................................... 3.4.5-1 3.4.6 RCS Specific Activity .................................................................. 3.4.6-1 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..................................................... 3.4.7-1 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ................................................... 3.4.8-1 3.4.9 RCS Pressure and Temperature (P/T) Limits ............................. 3.4.9-1 3.5 3.5.1 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM T

ECCS - Operating ..................................................................... 3.5.1-1 Formatted: Indent: Left: 0", Hanging: 1.08" 3.5.2 3.5.3 3.6 3.6.1.1 3.6.1.2 3.6.1.3 3.6.1.4 3.6.1.5 AF RPV Water Inventory ControlECCS - Shutdown........................ 3.5.2-1 RCIC System ............................................................................. 3.5.3-1 CONTAINMENT SYSTEMS Primary Containment ................................................................. 3.6.1.1-1 Primary Containment Air Locks .................................................. 3.6.1.2-1 Primary Containment Isolation Valves (PCIVs) .......................... 3.6.1.3-1 Drywell Pressure ........................................................................ 3.6.1.4-1 Drywell Air Temperature............................................................. 3.6.1.5-1 3.6.1.6 3.6.1.7 3.6.1.8 3.6.1.9 3.6.2.1 R

Reactor Building-to-Suppression Chamber Vacuum Breakers ... 3.6.1.6-1 Suppression Chamber-to-Drywell Vacuum Breakers.................. 3.6.1.7-1 Main Steam Leakage Collection (MSLC) System ....................... 3.6.1.8-1 Residual Heat Removal (RHR) Containment Spray System ....... 3.6.1.9-1 Suppression Pool Average Temperature .................................... 3.6.2.1-1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.3.1 3.6.3.2 3.6.4.1 3.6.4.2 3.6.4.3 D Suppression Pool Water Level ................................................... 3.6.2.2-1 Residual Heat Removal (RHR) Suppression Pool Cooling ......... 3.6.2.3-1 Drywell-to-Suppression Chamber Differential Pressure .............. 3.6.2.4-1 Primary Containment System Concentration .............................. 3.6.3.1-1 Containment Atmosphere Dilution (CAD) System ...................... 3.6.3.2-1 Secondary Containment ............................................................. 3.6.4.1-1 Secondary Containment Isolation Valves (SCIVs) ...................... 3.6.4.2-1 Standby Gas Treatment (SGT) System ...................................... 3.6.4.3-1 3.7 PLANT SYSTEMS 3.7.1 Residual Heat Removal Service Water (RHRSW) System ......... 3.7.1-1 3.7.2 Emergency Service Water (ESW) System and Ultimate Heat Sink (UMS)................................................................. 3.7.2-1 (continued)

JAFNPP ii Amendment 274

TABLE OF CONTENTS T

AF R

D JAFNPP ii Amendment 274

1.1 Definitions (continued)

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 (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 human error), for all penetration flow paths below the TAF except:

1. Penetration flow paths connected to an intact closed system, or isolated by manual or automatic T

valves that are locked, sealed or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant AF 2.

through the penetration flow paths; Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or R 3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained D c) 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.

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.

(continued)

JAFNPP 1.1-2a Amendment 315

ECCS Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation LCO 3.3.5.1 The ECCS instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.


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

A.1 T

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

AF B.1 the channel.

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

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

R 2. Only applicable for functions 1.a, 1.b, 2.a, D and 2.b.


Declare supported feature(s) inoperable when its redundant 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 feature ECCS initiation initiation capability capability for is inoperable. feature(s) in both divisions.

AND (continued)

JAFNPP 3.3.5.1-1 Amendment 274315

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 - - - - - -NOTE - - - - - -

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


Declare High Pressure 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Coolant Injection discovery of (HPCI) System loss of HPCI inoperable. initiation capability AND B.3 Place channel in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> trip.

T C. As required by Required Action A.1 and referenced in Table 3.3.5.1-1. AF C.1 - - - - - -NOTES- - - - - -

1. Only applicable in MODES 1, 2, and 3.
2. Only applicable for functions R 1.c, 1.d, 2.c, 2.d, and 2.f.

D Declare supported feature(s) inoperable when its redundant feature ECCS initiation capability is 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 initiation capability for feature(s) in both divisions.

AND C.2 Restore channel to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> OPERABLE status.

(continued)

JAFNPP 3.3.5.1-2 Amendment 274315

ECCS Instrumentation 3.3.5.1 ACTIONS (continued CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 - - - - - -NOTE- - - - - -

Required Action A.1 Only applicable if and referenced in HPCI pump suction is Table 3.3.5.1-1. not aligned to the suppression pool.

. -----------------

Declare HPCI System 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from inoperable. discovery of loss of HPCI initiation capability AND trip. T D.2.1 Place channel in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AF OR D.2.2 Align the HPCI pump suction to the suppression pool.

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

R D

JAFNPP 3.3.5.1-3 Amendment 274315

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by E.1 - - - - - -NOTES- - - - - -

Required Action A.1 1. Only Applicable and referenced in in MODES 1, 2, Table 3.3.5.1-1. and 3.

2. Only applicable for functions 1.e, 1.f, and 2.g.

.. -----------------

Declare supported 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Feature(s) inoperable discovery of when its redundant loss of feature ECCS initiation T

Initiation capability Is inoperable capability for subsystems in both divisions.

AF AND E.2 Restore channel to OPERABLE status.

7 days (continued)

R D

JAFNPP 3.3.5.1-4 Amendment 274315

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by F.1 Declare Automatic 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from Required Action A.1 Depressurization discovery of and referenced in System (ADS) valves loss of ADS Table 3.3.5.1-1. inoperable. initiation capability in both trip systems.

AND F.2 Place channel in 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from trip. discovery of inoperable channel T concurrent with HPCI or reactor core isolation AF cooling (RCIC) inoperable.

AND 8 days G.

R As required by Required Action A.1 and referenced in G.1 Declare ADS valves 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 ADS D

Table 3.3.5.1-1.

AND initiation capability to both trip systems.

(continued)

JAFNPP 3.3.5.1-5 Amendment 274315

ECCS Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. (continued) G.2 Restore channel to 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> from OPERABLE status. discovery of inoperable channel concurrent with HPCI or RCIC inoperable.

AND 8 days H. Required Action and H.1 Declare associated Immediately associated Completion supported feature(s)

Time of Condition B, C, D, E, F, or G not met.

T inoperable.

AF R

D JAFNPP 3.3.5.1-6 Amendment 274315

ECCS Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.1-1 to determine which SRs apply for each ECCS Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c, 3.f, and 3.g; 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, 3.f, and 3.g provided the associated Function or the redundant Function maintains ECCS initiation capability.

SURVELLANCE FREQUENCY SR 3.3.5.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control SR 3.3.5.1.2 Perform CHANNEL FUNCTIONAL TEST.

T Program In accordance with SR 3.3.5.1.3 AF Perform CHANNEL CALIBRATION.

the Surveillance Frequency Control Program In accordance with the Surveillance SR 3.3.5.1.4 RCalibrate the trip units.

Frequency Control Program In accordance with SR 3.3.5.1.5 D Perform CHANNEL CALIBRATION.

the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program JAFNPP 3.3.5.1-7 Amendment 301

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 5)

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

1. Core Spray System
a. Reactor Vessel Water 1, 2, 3, 4(ab) B SR 3.3.5.1.1 18 inches Level - Low Low Low 4(a), 5(a) SR 3.3.5.1.2 (Level 1) SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
b. Drywell 1, 2, 3 4(ab) B SR 3.3.5.1.1 2.7 psig Pressure - High SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Pressure - Low (Injection Permissive) 1, 2, 3 T

4 C SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 410 psig and 490 psig

d. Core Spray Pump Start - Time Delay AF 4(a), 5(a) 1, 2, 3, 4

1 per pump B

C SR SR SR SR SR SR 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 SR 3.3.5.1.5 410 psig and 490 psig 12.34 e.

Relay Core Spray Pump R Discharge Flow - Low (Bypass) 4(a), 5(a) 1, 2, 3, 4(a), 5(a) 1 per pump E SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 seconds 510 gpm and 980 gpm 2.

f.

D Core Spray Pump Discharge Pressure - High (Bypass)

Low Pressure Coolant Injection (LPCI) System 1, 2, 3, 4(a), 5(a) 1 per pump E SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 110 psig

a. Reactor Vessel Water 1, 2, 3, 4(ab) B SR 3.3.5.1.1 18 inches Level - Low Low Low 4(a), 5(a) SR 3.3.5.1.2 (Level 1) SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6 (continued) a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2, ECCS - Shutdown.

b)a) Also required to initiate the associated emergency diesel generator subsystem.

JAFNPP 3.3.5.1-8 Amendment 274315

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 of 5)

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

2. LPCI System (continued)
b. Drywell 1, 2, 3, 4(ab) B SR 3.3.5.1.1 2.7 psig Pressure - High SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Pressure - Low 1, 2, 3 4 C SR 3.3.5.1.1 410 psig (Injection Permissive) SR 3.3.5.1.2 and SR 3.3.5.1.4 490 psig SR 3.3.5.1.5 SR 3.3.5.1.6 4(a), 5(a) 4 T B SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 410 psig and 490 psig d.

e.

Reactor Pressure - Low (Recirculation Discharge Valve Permissive)

Reactor Vessel Shroud Level (Level 0)

AF 1(bc), 2(bc),

3(bc) 1, 2, 3 4

2 C

B SR SR SR SR SR SR SR SR 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 295 psig 1.0 inches f.

R Low Pressure Coolant 1, 2, 3, 1 per pump C SR SR SR 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 SR 3.3.5.1.5 D

Injection Pump Start - Time Delay Relay Pumps A, D Pumps B, C 4(a), 5(a) SR 3.3.5.1.6 1.51 seconds 6.73 seconds (continued) a) When associated ECCS subsystem(s) are required to be OPERABLE per LCO 3.5.2.

b)a) Also required to initiate the associated emergency diesel generator subsystem.

c)b) With associated recirculation pump discharge valve open.

JAFNPP 3.3.5.1-9 Amendment 274315

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 of 5)

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

2. LPCI System (continued)
g. Low Pressure 1, 2, 3, 1 per E SR 3.3.5.1.5 1040 gpm Coolant Injection Pump 4(a), 5(a) subsystem SR 3.3.5.1.6 and Discharge Flow - Low 1665 gpm (Bypass)
h. Containment 1, 2, 3 4 B SR 3.3.5.1.3 1 psig and Pressure - High SR 3.3.5.1.6 2.7 psig
3. High Pressure Coolant Injection (HPCI) System
a. Reactor Vessel Water 1, 4 B SR 3.3.5.1.1 126.5 Level - Low Low (Level 2) 2(cd), 3(cd)

T SR SR SR SR 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 inches b.

c.

Drywell Pressure - High Reactor Vessel Water Level - High (Level 8)

AF 1, 2(cd), 3(cd) 1, 2(cd), 3(cd) 4 2

B C

SR SR SR SR SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 2.7 psig 222.5 inches

d. Condensate Storage Tank Level - Low R 1, 2(cd), 3(cd) 4 D SR SR 3.3.5.1.5 3.3.5.1.6 SR 3.3.5.1.3 SR 3.3.5.1.6 59.5 inches e.
f. D Suppression Pool Water Level - High High Pressure Coolant Injection Pump Discharge Flow - :Low (Bypass) 1, 2(cd), 3(cd) 1, 2(cd), 3(cd) 2 1

D E

SR 3.3.5.1.3 SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 14.5 ft 475 gpm and 800 gpm

g. High Pressure Coolant 1, 1 E SR 3.3.5.1.3 25 psig Injection Pump 2(cd), 3(cd) SR 3.3.5.1.6 and Discharge 80 psig Pressure - High (Bypass)

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

c) With rector steam dose pressure > 150 psig.

JAFNPP 3.3.5.1-10 Amendment 274315

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 of 5)

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

4. Automatic Depressurization System (ADS) Trip System A
a. Reactor Vessel Water 1, 2 F SR 3.3.5.1.1 18 inches Level - Low Low Low 2(cd), 3(cd) SR 3.3.5.1.2 (Level 1) SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
b. Automatic 1, 1 G SR 3.3.5.1.5 134 seconds Depressurization 2(cd), 3(cd) SR 3.3.5.1.6 System Initiation Timer
c. Reactor Vessel Water 1, 1 F SR 3.3.5.1.1 177 inches Level - Low (Level 3) 2(cd), 3(cd)

T SR SR SR SR 3.3.5.1.2 3.3.5.1.4 3.3.5.1.5 3.3.5.1.6 d.

e.

Core Spray Pump Discharge Pressure - High Low Pressure Coolant Injection Pump Discharge Pressure - High AF 1, 2(cd), 3(cd) 1, 2(cd), 3(cd) 2 4

G G

SR 3.3.5.1.3 SR 3.3.5.1.6 SR 3.3.5.1.3 SR 3.3.5.1.6 90 psig and 110 psig 105 psig and 145 psig

5. ADS Trip System B
a. R Reactor Vessel Water Level - Low Low Low (Level 1) 1, 2(cd), 3(cd) 2 F SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.4 18 inches
b. D Automatic Depressurization System Initiation Timer 1,

2(cd), 3(cd) 1 G SR SR 3.3.5.1.5 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 134 seconds (continued)

c. With rector steam dose pressure > 150 psig.

JAFNPP 3.3.5.1-11 Amendment 274315

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 5)

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

5. ADS Trip System B (continued)
c. Reactor Vessel Water 1, 1 F SR 3.3.5.1.1 177 inches Level - Low (Level 3) 2(cd), 3(cd) SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.5 SR 3.3.5.1.6
d. Core Spray Pump 1, 2 G SR 3.3.5.1.3 90 psig Discharge 2(cd), 3(cd) SR 3.3.5.1.6 and Pressure - High 110 psig
e. Low Pressure Coolant 1, 4 G SR 3.3.5.1.3 105 psig Injection Pump Discharge Pressure - High 2(cd), 3(cd)

T SR 3.3.5.1.6 and 145 psig (continued)

AF d)c) With rector steam dose pressure > 150 psig.

R D

JAFNPP 3.3.5.1-12 Amendment 274315

RPV Water Inventory Control Instrumentation 3.3.5.2 3.3 INSTRUMENTATION 3.3.5.2 Reactor Pressure Vessel (RPV) Water Inventory Control Instrumentation LCO 3.3.5.2 The RPV Water Inventory Control instrumentation for each Function in Table 3.3.5.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.2-1.

ACTIONS


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

Separate Condition entry is allowed for each channel.


CONDITION T

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

AF A.1 Enter the Condition referenced in Table 3.3.5.2-1 for the channel.

Immediately Action A.1 and referenced in Table 3.3.5.2-1.

R B. As required by Required B.1 Declare associated penetration flow path(s) incapable of automatic isolation.

Immediately D AND B.2 Calculate DRAIN TIME. Immediately C. As required by Required 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 /> Action A.1 and referenced in Table 3.3.5.2-1.

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

referenced in Table 3.3.5.2-1.

JAFNPP 3.3.5.2-1 Amendment 315

RPV Water Inventory Control Instrumentation 3.3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Declare associated low Immediately associated Completion pressure ECCS Time of Condition C or D injection/spray subsystem not met. inoperable.

SURVEILLANCE REQUIREMENTS


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

Refer to Table 3.3.5.2-1 to determine which SRs apply for each ECCS Function.


SR 3.3.5.2.1 SURVEILLANCE Perform CHANNEL CHECK.

T FREQUENCY In accordance SR 3.3.5.2.2 AF Perform CHANNEL FUNCTIONAL TEST.

with the Surveillance Frequency Control Program In accordance R with the Surveillance Frequency Control Program D

SR 3.3.5.2.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program JAFNPP 3.3.5.2-2 Amendment 315

RPV Water Inventory Control Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)

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

1. Core Spray
a. a. Reactor 4, 5 4 C SR 3.3.5.2.1 < 490 psig Pressure - SR 3.3.5.2.2 Low (Injection Permissive)
b. b. Core Spray 4, 5 1 per pump D SR 3.3.5.2.1 > 510 gpm Pump (a) SR 3.3.5.2.2 and Discharge Flow < 980 gpm

- Low (Bypass)

c. c. Manual 4, 5 1 per D SR 3.3.5.2.3 NA Initiation subsystem
2. Low Pressure Coolant Injection (LPCI) System (a)

T a.

b.

a. Reactor Pressure -

Low (Injection Permissive)

b. Low Pressure Coolant Injection Pump AF 4, 5 4, 5 4

1 per pump (a)

C D

SR 3.3.5.2.1 SR 3.3.5.2.2 SR 3.3.5.2.1 SR 3.3.5.2.2

< 490 psig

> 1040 gpm and

< 1665 gpm

c. c.

Discharge Flow

- Low (Bypass)

Manual R 4, 5 1 per D SR 3.3.5.2.3 NA D

Initiation

3. Residual Heat Removal System Isolation
a. a. Reactor Vessel Water Level -

(b) subsystem (a) 2 in one trip system B SR 3.3.5.2.1 SR 3.3.5.2.2

> 177 inches Low, Level 3

4. Reactor Water Cleanup System Isolation
a. a. Reactor Vessel (b) 2 in one trip B SR 3.3.5.2.1 > 177 inches Water Level - system SR 3.3.5.2.2 Low Level 3 (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.

JAFNPP 3.3.5.2-3 Amendment 315

RCIC System Instrumentation 3.3.5.32 3.3 INSTRUMENTATION 3.3.5.32 Reactor Core Isolation Cooling (RCIC) System Instrumentation LCO 3.3.5.32 The RCIC System instrumentation for each Function in Table 3.3.5.32-1 shall be OPERABLE.

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

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

Separate Condition entry is allowed for each channel.


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

A.1 T Enter the Condition referenced in Immediately B. As required by Required Action A.1 and referenced in AF B.1 Table 3.3.5.32-1 for the channel.

Declare RCIC System 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 RCIC Table 3.3.5.32-1.

R AND initiation capability C.

D As required by B.2 C.1 Place channel in Trip.

Restore channel in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours Required Action A.1 OPERABLE status.

and referenced in Table 3.3.5.32-1.

(continued)

JAFNPP 3.3.5.32-1 Amendment 274315

RCIC System Instrumentation 3.3.5.32 ACTIONS (continued)

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

Required Action A.1 Only applicable if and referenced in RCIC pump suction is Table 3.3.5.32-1. not aligned to the suppression pool.


Declare (RCIC) System 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from inoperable. discovery of loss of automatic RCIC initiation capability AND trip.

T D.2.1 Place channel in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> AF OR D.2.2 Align RCIC pump suction to the suppression pool.

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

R Required Action and associated Completion Time of Condition B, E.1 Declare RCIC System inoperable.

Immediately D

C, or D not met.

JAFNPP 3.3.5.32-2 Amendment 274315

RCIC System Instrumentation 3.3.5.32 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.5.32-1 to determine which SRs apply for each RCIC Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 2 and 4; 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 1 and 3 provided the associated Function maintains RCIC initiation capability.

SURVELLANCE FREQUENCY SR 3.3.5.32.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.5.32.2 Perform CHANNEL FUNCTIONAL TEST. T In accordance with the Surveillance SR 3.3.5.32.3 AF Perform CHANNEL CALIBRATION.

Frequency Control Program In accordance with the Surveillance Frequency Control SR 3.3.5.32.4 RCalibrate the trip units.

Program In accordance with the Surveillance D

SR 3.3.5.32.5 Perform CHANNEL CALIBRATION.

Frequency Control Program In accordance with the Surveillance Frequency Control Program SR 3.3.5.32.6 Perform LOGIC SYSTEM FUNCTIONAL TEST. In accordance with the Surveillance Frequency Control Program JAFNPP 3.3.5.32-3 Amendment 301315

RCIC System Instrumentation 3.3.5.32 Table 3.3.5.32-1 Reactor Core Isolation Cooling System Instrumentation (Page 1 of 1)

CONDITIONS REQUIRED REFERENCED CHANNELS FROM REQUIRED SURVEILLANCE ALLOWABLE FUNCTION PER FUNCTION ACTION A.1 REQUIREMENTS VALUE

1. Reactor Vessel Water 4 B SR 3.3.5.32.1 126.5 inches Level - Low Low (Level 2) SR 3.3.5.32.2 SR 3.3.5.32.4 SR 3.3.5.32.5 SR 3.3.5.32.6
2. Reactor Vessel Water 2 C SR 3.3.5.32.1 222.5 inches Level - High (Level 8) SR 3.3.5.32.2 SR 3.3.5.32.4 SR 3.3.5.32.5 SR 3.3.5.32.6
3. Condensate Storage Tank 4 D SR 3.3.5.32.3 59.5 inches Level - Low SR 3.3.5.32.6
4. Manual Initiation 1 T C SR 3.3.5.32.6 NA AF R

D JAFNPP 3.3.5.32-4 Amendment 274315

Primary Containment Isolation Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME H. Required Action and H.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition F or AND G not met. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> H.2 Be in MODE 4.

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

I. As required by I.1 Declare associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Required Action C.1 standby liquid and referenced in Table 3.3.6.1-1. T control subsystem (SLC) inoperable.

AF OR I.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 /> J.

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

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

Immediately D OR J.2 Initiate action to isolate the Residual Heat Removal (RHR)

Shutdown Cooling System.

Immediately JAFNPP 3.3.6.1-3 Amendment 274315

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 6)

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

5. Reactor Water Cleanup (RWCU)

System Isolation

a. RWCU Suction Line 1,2,3 1 F SR 3.3.6.1.3 144F Penetration Area SR 3.3.6.1.7 Temperature High
b. RWCU Pump Area 1,2,3 1 per F SR 3.3.6.1.3 165F for Pump Temperature High room SR 3.3.6.1.7 Room A and 175F for Pump Room B c.

d.

RWCU Heat Exchanger Room Area Temperature High SLC System Initiation 1,2,3 1,2 1

2(d)

T F I

SR 3.3.6.1.3 SR 3.3.6.1.7 SR 3.3.6.1.7 155F NA e.

f.

Reactor Vessel Water Level Low (Level 3)

Drywell Pressure High AF 1,2,3 1,2,3 2

2 F

F SR SR SR SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 177 inches 2.7 psig 6.

R Shutdown Cooling System Isolation SR SR 3.3.6.1.5 3.3.6.1.7 a.

b.

D Reactor Pressure High Reactor Vessel Water Level Low (Level 3) 1,2,3 3,4,5 1

2(e)

F J

SR SR SR SR SR SR SR 3.3.6.1.1 3.3.6.1.2 3.3.6.1.4 3.3.6.1.5 3.3.6.1.7 3.3.6.1.1 3.3.6.1.2 74 psig 177 inches SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)

(d) SLC System Initiation only inputs into one of the two trip systems and only isolates one valve in the RWCU suction and return line.

(e) Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

JAFNPP 3.3.6.1-10 Amendment 298315

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

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

1. Reactor Vessel Water 1, 2, 3, 2 SR 3.3.6.2.1 177 inches Level - Low (Level 3) (a) SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6
2. Drywell Pressure - High 1, 2, 3 2 SR 3.3.6.2.1 2.7 psig SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.5 SR 3.3.6.2.6
3. Reactor Building Exhaust 1, 2, 3, 1 SR 3.3.6.2.1 24,800 cpa Radiation - High (a), (b) SR 3.3.6.2.3 SR 3.3.6.2.6
4. Refueling Floor Exhaust Radiation - High 1, 2, 3, (a), (b)

T1 SR 3.3.6.2.1 SR 3.3.6.2.3 24,800 cpa AF (a) During operation with a potential for draining the reactor vessel.

(b)(a)

SR 3.3.6.2.6 During movement of recently irradiated fuel assemblies in secondary containment.

R D

JAFNPP 3.3.6.2-4 Amendment 276315

`

CREVAS System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1 Control Room Emergency Ventilation Air Supply (CREVAS)

System Instrumentation LCO 3.3.7.1 The Control Room Air Inlet Radiation High channel 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.

ACTIONS CONDITION T

REQUIRED ACTION COMPLETION TIME A. Channel inoperable.

AF A.1 OR A.2 Place the CREVAS System in the isolate mode of operation.

Declare both CREVAS 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour R subsystems inoperable.

D JAFNPP 3.3.7.1-1 Amendment 276315

CREVAS System Instrumentation 3.3.7.1 SURVEILLANCE REQUIREMENTS


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

When the channel is placed in an inoperable status solely for performance of required Surveillances, entry into the Condition 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 />.


SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.1.2 Perform CHANNEL CALIBRATION. The Allowable In accordance Value shall be 4000 cpm.

T with the Surveillance Frequency Control Program AF R

D JAFNPP 3.3.7.1-2 Amendment 301

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

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 T

REQUIRED ACTION COMPLETION TIME A. One low pressure ECCS injection/spray subsystem inoperable.

OR One low pressure coolant AF A.1 Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.

7 days R

injection (LPCI) pump in both LPCI subsystems inoperable.

B. D Required Action and associated Completion Time of Condition A not met.

B.1 AND B.2 Be in MODE 3.

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 (continued)

JAFNPP 3.5.1-1 Amendment 284315

RPV Water Inventory ControlECCS - Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEM (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.2 Reactor Pressure Vessel (RPV) Water Inventory ControlECCS - Shutdown LCO 3.5.2 DRAIN TIME of RPV water inventory to the top of active fuel (TAF) shall be > 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

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


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

A 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.

T


APPLICABILITY:

ACTIONS AF MODES 4 and 5 MODES 5, except with the spent fuel storage pool gates removed and water level 22 ft 2 inches over the top of the reactor pressure vessel flange.

A.

CONDITION R

One rRequired low A.1 REQUIRED ACTION Restore required low COMPLETION TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> D

pressure ECCS injection/spray subsystem inoperable.

pressure ECCS injection/spray subsystem to OPERABLE status.

B. Required Action and B.1 Initiate action to establish a Immediately associated Completion method of water injection Time of Condition A capable of operating not met. without offsite electrical power.

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

JAFNPP 3.5.2-1 Amendment 274315

RPV Water Inventory ControlECCS - Shutdown 3.5.2 C. DRAIN TIME < 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.1 Verify secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. containment boundary is capable of being established in less than the DRAIN TIME.

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

AND C.3 Verify one standby gas 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> treatment subsystem is T

capable of being placed in operation in less than the DRAIN TIME.

C. Two required low pressure ECCS injection/spray subsystems inoperable.

AF C.1 AND C.2 Initiate action to suspend OPDRVs.

Restore one required Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> R low pressure ECCS injection/spray subsystem to OPERBLE status.

D (continued)

JAFNPP 3.5.2-2 Amendment 274315

RPV Water Inventory ControlECCS - Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. DRAIN TIME < 8 D.1 ------------- NOTE -------------- Immediately hours.Required Action Initiate Required ECCS C.2 and injection/spray subsystem E. associated Completion or additional method of F.D. Time not met. water injection shall be capable of operating without offsite electrical power.


action to restore secondary containment to OPERABLE status.

Initiate action to establish T

an additional method of water injection with water sources capable of AF AND D.2 maintaining RPV water >

TAF for > 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Initiate action to establish secondary containment Immediately R boundary. restore standby gas treatment subsystem to OPERABLE status.

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

restore Isolation capability in each required secondary containment penetration flow path not isolated.

AND JAFNPP 3.5.2-2 Amendment 274315

RPV Water Inventory ControlECCS - Shutdown 3.5.2 D.4 Initiate action to verify one standby gas treatment subsystem is capable of being placed in operation.

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

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 />.

SURVEILLANCE REQUIREMENTS SURVELLANCE T FREQUENCY SR 3.5.2.1 SR 3.5.2.12 AF Verify DRAIN TIME 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.

Verify, for each required low pressure coolant injection In accordance with the Surveillance Frequency Control Program In accordance with R

(LPCI) subsystem, the suppression pool water level is 10.33 ft.

the Surveillance Frequency Control Program (continued)

D JAFNPP 3.5.2-3 Amendment 274315

RPV Water Inventory ControlECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVELLANCE FREQUENCY SR 3.5.2.23 Verify for each a required Ccore sSpray (CS) subsystem, In accordance with the: the Surveillance Frequency Control

a. Suppression pool water level is 10.33 ft; or Program
b. The water level in each condensate storage Tank is > 324 inches - - - - - - - - - - - - - - -NOTE - - - - - - -

Only one required CS subsystem may take credit for this option during OPDRVs.


The water level in each condensate storage Tank is 324 inches.

SR 3.5.2.34 T

Verify, for eachthe required ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.

In accordance with the Surveillance Frequency Control SR 3.5.2.45 AF

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

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

Program R------------------------------------

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

Frequency Control Program (continued)

JAFNPP 3.5.2-4 Amendment 274315

RPV Water Inventory ControlECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVELLANCE FREQUENCY SR 3.5.2.56 Operate the required ECCS injection/spray subsystem In accordance with through the recirculation line for > 10 minutes.Verify the Inservice each required ECCS pump develops the Testing Program specified flow rate against a system head corresponding to the specified reactor pressure above primary containment pressure.

SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE NO. ABOVE PRIMARY OF CONTAINMENT SYSTEM FLOW RATE PUMPS PRESSURE OF 4265 gpm 113 psi CS LPCI 7700 gpm 1

1 T 20 psi SR 3.5.2.7 SR 3.5.2.68 AF Verify each valve credited for automatically isolating a penetration flow path actuates to the isolation position on an actual or simulated isolation signal.

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

Vessel injection/spray may be excluded.

In accordance with the Surveillance Frequency Control Program R------------------------------------

Verify theeach required ECCS injection/spray subsystem actuates on an a manual actual or simulated automatic In accordance with the Surveillance D initiation signal. Frequency Control Program JAFNPP 3.5.2-5 Amendment 274315

RCIC SYSTEM 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), RPV WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 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 RCIC.


CONDITION T

REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.

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

Immediately R AND A.2 Restore RCIC System to OPERABLE status.

14 days B.

D Required Action and associated Completion Time not met.

B.1 AND Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> B.2 Reduce reactor steam 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> dome pressure to 150 psig.

JAFNPP 3.5.3-1 Amendment 284315

PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and F.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A, AND B, C, D, or E not met In MODE 1, 2, or 3. F.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> G. Required Action and G.1 Initiate action to Immediately associated Completion suspend operations Time of Condition A or with a potential for B not met for PCIV(s) draining the reactor required to be vessel.

OPERABLE during Mode 4 or 5. OR T

G.2 Initiate action to Immediately AF restore valve(s) to OPERABLE status.

R D

JAFNPP 3.6.1.3-6 Amendment 274315

Secondary Containment 3.6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

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

ACTIONS A.

CONDITION Secondary containment A.1 T

REQUIRED ACTION Restore secondary COMPLETION TIME 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B.

inoperable in MODE 1, 2, or 3.

Required Action and AF B.1 containment to OPERABLE status.

Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> not met. R associated Completion Time of Condition A AND B.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.

D Secondary containment inoperable during movement of recently irradiated fuel C.1 ------------NOTE------------

LCO 3.0.3 is not applicable.


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

AND (continued)

JAFNPP 3.6.4.1-1 Amendment 276315

Secondary Containment 3.6.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Initiate action to suspend Immediately OPDVRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 of vacuum water gauge. T Verify secondary containment vacuum is 0.25 inch In accordance with the Surveillance Frequency Control SR 3.6.4.1.2 AF Verify all secondary containment equipment hatches are closed and sealed.

Program In accordance with the Surveillance Frequency Control Program SR 3.6.4.1.3 R Verify one secondary containment access door in each access opening is closed.

In accordance with the Surveillance D

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 Frequency Control Program In accordance with the Surveillance one SGT subsystem at a flow rate 6000 cfm. Frequency Control Program JAFNPP 3.6.4.1-2 Amendment 301315

SCIVs 3.6.4.2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

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

ACTIONS


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

1. Penetration flow paths may be unisolated intermittently under 2.

administrative controls.

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

2.

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


CONDITION REQUIRED ACTION COMPLETION TIME A. R One or more penetration flow paths with one A.1 Isolate the affected penetration flow path 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> D

SCIV inoperable. by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND (continued)

JAFNPP 3.6.4.2-1 Amendment 276315

SCIVs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) 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 T

administrative means.


B. ---------NOTE---------

AF B.1 Verify the affected penetration flow path is isolated.

Isolate the affected Once per 31 days.

4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> R

Only applicable to penetration flow paths with two isolation valves.

penetration flow path by use of at least one closed and de-activated D


One or more penetration flow paths with two SCIVs inoperable.

automatic valve, closed manual valve, or blind flange.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND or B not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

JAFNPP 3.6.4.2-2 Amendment 274

SCIVs 3.6.4.2 ACTIONS (continued)

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

associated Completion LCO 3.0.3 is not Time of Condition A applicable.

or B not met during ---------------------

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

AND T

D.2Initiate action to suspend OPDRVs.

Immediately AF R

D JAFNPP 3.6.4.2-3 Amendment 276315

SCIVs 3.6.4.2 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 In accordance manual valve and blind flange that is not locked, With the sealed, or otherwise secured and is required to be Surveillance closed during accident conditions is closed. Frequency T Control Program SR 3.6.4.2.2 AF Verify the isolation time of each power operated, automatic SCIV is within limits.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.2.3 R

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

In accordance with the Surveillance D Frequency Control Program JAFNPP 3.6.4.2-4 Amendment 301

SGT System 3.6.4.3 3.6 CONTAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT) System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

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

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

A.1 T 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.

AF B.1 AND B.2 Be in MODE 3.

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 R

C.

D Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment


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

LCO 3.0.3 is not applicable.


C.1 Place OPERABLE SGT subsystem in operation.

Immediately or during OPDRVs. OR (continued)

JAFNPP 3.6.4.3-1 Amendment 276315

SGT System 3.6.4.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in secondary containment.

AND C.2.2 Initiate action to Immediately suspend OPDRVs.

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

E. Two SGT subsystems E.1 T


NOTE---------

inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

AF LCO 3.0.3 is not applicable.


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

D E.2 Initiate action to suspend OPDRVs.

Immediately JAFNPP 3.6.4.3-2 Amendment 276315

SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 10 continuous In accordance hours with heaters operating. with the Surveillance Frequency Control Program SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.4.3.3 T

Verify each SGT subsystem actuates on an actual or simulated initiation signal.

In accordance With the Surveillance SR 3.6.4.3.4 AF Manually cycle each SGT subsystem filter cooling cross-tie valve.

Frequency Control Program In accordance With the Surveillance R Frequency Control Program D

JAFNPP 3.6.4.3-3 Amendment 301

CREVAS System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Emergency Ventilation Air Supply (CREVAS) System LCO 3.7.3 Two CREVAS 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 T

REQUIRED ACTION COMPLETION TIME A.

B.

One CREVAS subsystem inoperable for reasons other than Condition B.

One or more CREVAS AF A.1 B.1 Restore CREVAS subsystem to OPERABLE status.

Initiate action to 7 days Immediately R

subsystems inoperable due to inoperable CRE boundary in MODE 1, 2, or 3. AND implement mitigating actions.

D B.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> limits.

AND B.3 Restore CRE boundary to 90 days OPERABLE status.

(continued)

JAFNPP 3.7.3-1 Amendment 289315

CREVAS System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A or B not met AND in MODE 1, 2, or 3.

C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D. Required Action and -------------- NOTE --------------

associated Completion Time LCO 3.0.3 is not applicable.

of Condition A not met --------------------------------------

during movement of recently irradiated fuel D.1 Place OPERABLE CREVAS Immediately assemblies in the secondary subsystem in isolate mode.

containment or during OPDRVs. OR T

D.2.1 Suspend movement of Immediately AF AND recently irradiated fuel assemblies in the secondary containment.

D.2.2 Initiate action to suspend Immediately E.

R Two CREVAS subsystems E.1 OPDRVs.

Enter LCO 3.0.3. Immediately D

inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

JAFNPP 3.7.3-2 Amendment 289315

CREVAS System 3.7.3 ACTIONS (continued)

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

inoperable during movement LCO 3.0.3 is not applicable.

of recently irradiated fuel ----------------------------------------

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

One or more CREVAS AND subsystems inoperable due to an inoperable CRE F.2 Initiate action to suspend Immediately boundary during movement OPDRVs.

of recently irradiated fuel in the secondary containment or during OPDRVs.

T SURVEILLANCE REQUIREMENTS AF SURVEILLANCE FREQUENCY SR 3.7.3.1 R Operate each CREVAS subsystem for 15 minutes. In accordance with the Surveillance D

SR 3.7.3.2 Perform required CREVAS filter testing in accordance with the Ventilation Filter Testing Program (VFTP).

Frequency Control Program In accordance with the VFTP (continued)

JAFNPP 3.7.3-3 Amendment 301315

CREVAS System 3.7.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.3.3 Perform required CRE unfiltered air in-leakage testing in In accordance with accordance with the control room Envelope Habitability the Control Room Program. Envelope Habitability Program T

AF R

D JAFNPP 3.7.3-4 Amendment 289

Control Room AC System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Air Conditioning (AC) System LCO 3.7.4 Two control room AC 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 control room AC subsystem inoperable.

A.1 T Restore control room AC subsystem to OPERABLE 30 days B. Two control room AC subsystems inoperable.

AF B.1 status.

Verify control room area temperature < 90 °F.

Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> R AND B.2 Restore one control 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> C.

D Required Action and associated Completion C.1 room AC subsystem to OPERABLE status.

Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Time of Condition A or B AND not met in MODE 1, 2, or

3. C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

JAFNPP 3.7.4-1 Amendment 290 315

Control Room AC System 3.7.4 ACTIONS (continued)

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

associated Completion LCO 3.0.3 is not applicable.

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

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

OR T

D.2.1 Suspend movement of recently irradiated fuel assemblies in the Immediately AF AND secondary containment.

D.2.2 Initiate action to suspend OPDRVs.

Immediately E.

R Required Action and - - - - - - - - - NOTE - - - - - - - - - -

D associated Completion Time of Condition B not met during movement of recently irradiated fuel assemblies in the secondary containment or LCO 3.0.3 is not applicable.


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

AND E.2 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS JAFNPP 3.7.4-2 Amendment 290 315

Control Room AC System 3.7.4 SURVEILLANCE FREQUENCY SR 3.7.4.1 Verify each control room AC subsystem has the In accordance capability to remove the assumed heat load. with the Surveillance Frequency Control Program T

AF R

D JAFNPP 3.7.4-3 Amendment 301

AC Sources - Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems - Shutdown";
b. One qualified circuit, which maybe the same circuit required by LCO 3.8.2.a, between the offsite transmission network and the other division of the plant Class 1E AC electrical power distribution subsystem(s),

when a second division is required by LCO 3.8.8; and

c. One emergency diesel generator (EDG) subsystem capable T

of supplying one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

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

R D

JAFNPP 3.8.2-1 Amendment 276315

AC Sources - Shutdown 3.8.2 ACTIONS


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

LCO 3.0.3 is not applicable.


CONDITION REQUIRED ACTION COMPLETION TIME A. One or both required -------------------NOTE------------------

offsite circuits Enter applicable Condition inoperable. and Required Actions of LCO 3.8.8, when any required division is de-energized as a result of Condition A.


A.1 Declare affected Immediately required feature(s),

available,T with no offsite power inoperable.

AF OR A.2.1 Suspend CORE ALTERATIONS.

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

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

AND (continued)

JAFNPP 3.8.2-2 Amendment 276315

AC Sources - Shutdown 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.34 Initiate action to restore Immediately required offsite power circuit(s) to OPERABLE status.

B. One required EDG B.1 Suspend CORE Immediately subsystem inoperable. ALTERATIONS.

AND B.2 Suspend movement of Immediately recently irradiated secondary T

fuel assemblies in containment.

AF AND B.3 AND Initiate action to suspend OPDRVs.

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

Immediately D

JAFNPP 3.8.2-3 Amendment 276315

AC Sources Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 ---------------------------NOTES---------------------

1. The following SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.8, SR 3.8.1.9, SR 3.8.1.11, SR 3.8.1.12, and SR 3.8.1.13.
2. SR 3.8.1.10 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 - ShutdownRPV Water Inventory Control."

SRs of Specification 3.8.1, except SR 3.8.1.7, are applicable.

T For AC sources required to be OPERABLE the In accordance with applicable SRs AF R

D JAFNPP 3.8.2-4 Amendment 274315

DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources Shutdown LCO 3.8.5 One 125 VDC electrical power subsystem shall be OPERABLE to support one division of the plant Class IE 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 T


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

LCO 3.0.3 is not applicable.

A.

CONDITION Required DC electrical AF


A.1 REQUIRED ACTION Declare affected COMPLETION TIME Immediately power subsystem inoperable.

R OR required feature(s) inoperable.

D A.2.1 Suspend CORE ALTERATIONS.

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

AND (continued)

JAFNPP 3.8.5-1 Amendment 276

DC Sources - Shutdown 3.8.5 ACTIONS CONDITIONS REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel.

AND A.2.34 Initiate action to Immediately restore required DC electrical power subsystem to OPERABLE status.

T SURVEILLANCE REQUIREMENTS AF SR 3.8.5.1 R SURVEILLANCE


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

FREQUENCY D The following SRs are not required to be performed: SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.


For DC electrical power subsystem required In accordance to be OPERABLE the following SRs are with applicable applicable: SRs SR 3.8.4.1, SR 3.8.4.2, SR 3.8.4.3, and SR 3.8.4.4.

JAFNPP 3.8.5-2 Amendment 274315

Distribution Systems - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems Shutdown LCO 3.8.8 The necessary portions of the AC and 125 VDC 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.

T


A.

CONDITION One or more required AC or 125 VDC electrical power distribution AF A.1 REQUIRED ACTION Declare associated supported required feature(s) inoperable.

COMPLETION TIME Immediately R

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately D ALTERATIONS.

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

AND (continued)

JAFNPP 3.8.8-1 Amendment 276315

Distribution Systems - Shutdown 3.8.8 ACTIONS (continued)

A. (continued)

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

AND A.2.34 Initiate actions to restore Immediately required AC and 125 VDC electrical power distribution subsystems to OPERABLE status.

AND T

A.2.45 Declare associated required shutdown cooling Immediately AF subsystem(s) inoperable.

R SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY D

SR 3.8.8.1 Verify correct breaker alignments and voltage to required AC and 125 VDC electrical power distribution subsystems.

In accordance with the Surveillance Frequency Control Program JAFNPP 3.8.8-2 Amendment 301315