Text

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

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from Coolant Injection discovery of (HPCI) System loss of HPCI inoperable. initiation capability AND B.3 Place channel in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of initiation capability for feature(s) in both divisions.

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

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

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from OPERABLE status. discovery of inoperable channel concurrent with HPCI or RCIC inoperable.

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

Time of Condition B, C, 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 3.c, 3.f, and 3.g; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions other than 3.c, 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Action A.1 and OPERABLE status.

referenced in Table 3.3.5.2-1.

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from inoperable. discovery of loss of automatic RCIC initiation capability AND trip.

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

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 2 and 4; and (b) for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months for Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition F or AND G not met. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.1 Verify secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . containment boundary is capable of being established in less than the DRAIN TIME.

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

AND C.3 Verify one standby gas 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Time of Condition C or D not met.

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

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

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

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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months not met. R associated Completion Time of Condition A AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months R AND B.2 Restore one control 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months C.

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

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

3. C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (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

v t e Letter Sequence Draft Other
CAC:MG0158, (Open)
Initiation Acceptance... Administration Meeting Questions Answers Results Approval... Other:
MONTHYEAR2017-09-18 [Table View]

ML17261A743

Text

Navigation menu

Search