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 JAFNPP i Amendment 287 1.0 USE AND APPLICATION

1.1 Definitions

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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

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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

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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

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3.3.3.1-1 3.3.3.2 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

(continued)

TABLE OF CONTENTS JAFNPP ii Amendment 274 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation

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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

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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

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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)

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 valves that are locked, sealed or otherwise secured in the closed position, blank flanges, or other devices that prevent flow of reactor coolant through the penetration flow paths;

2. Penetration flow paths capable of being isolated by valves that will close automatically without offsite power prior to the RPV water level being equal to the TAF when actuated by RPV water level isolation instrumentation; or

3. Penetration flow paths with isolation devices that can be closed prior to the RPV water level being equal to the TAF by a dedicated operator trained in 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)

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

-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.5.1

-1. ACTIONS - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - - - - Separate Condition entry is allowed for each channel.

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

. A.1 Enter the Condition referenced in Table 3.3.5.1

-1 for the channel.

Immediately B. As required by Required Action A.1 and referenced in Table 3.3.5.1

-1. B.1 - - - - - -NOTE S- - - - -- 1. Only applicable in MODES 1, 2, and 3. 2. Only applicable for functions 1.a, 1.b, 2.a, and 2.b. - - - - - - - - - - - - - - - - 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 (continued)

ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-2 Amendment 274 315 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)

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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of HPCI initiation capability 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. As required by Required Action A.1 and referenced in Table 3.3.5.1

-1. C.1 - - - - - -NOTE S- - - - - - 1. Only applicable in MODES 1, 2, and 3. 2. Only applicable for functions 1.c, 1.d, 2.c , 2.d, and 2.f. - - - - - - - - - - - - - - - - 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 OPERABLE status.

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

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.

. - - - - - - - - - - - - - - - - - Declare HPCI System inoperable.

AND D.2.1 Place channel in trip. OR D.2.2 Align the HPCI pump suction to the suppression pool.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of HPCI initiation capability 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-4 Amendment 274 315 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. As required by Required Action A.1 and referenced in Table 3.3.5.1

-1. E.1 - - - - - -NOTE S- - - - - - 1. Only Applicable in MODES 1, 2, and 3. 2. Only applicable for 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.

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 subsystems in both divisions.

7 days (continu ed)

ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-5 Amendment 274 315 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. As required by Required Action A.1 and referenced in Table 3.3.5.1

-1. F.1 Declare Automatic Depressurization System (ADS) valves inoperable.

AND F.2 Place channel in trip. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability in both trip systems. 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from discovery of inoperable channel concurrent with HPCI or reactor core isolation cooling (RCIC) inoperable.

AND 8 days G. As required by Required Action A.1 and referenced in Table 3.3.5.1

-1. G.1 Declare ADS valves inoperable.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of ADS initiation capability to both trip systems. (continued)

ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-6 Amendment 274 315 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. (continued)

G.2 Restore channel to OPERABLE status.

96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months from discovery of inoperable channel concurrent with HPCI or RCIC inoperable.

AND 8 days H. Required Action and associated Completion Time of Condition B, C, D, E, F, or G not met. H.1 Declare associated supported feature(s) inoperable.

Immediately

ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-7 Amendment 301 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 Progra m 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.

In accordance with the Surveillance Frequency Control Progra m SR 3.3.5.1.4 Calibrate the trip units.

In accordance with the Surveillance Frequency Control Progra m SR 3.3.5.1.5 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Progra m SR 3.3.5.1.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

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

-1 (page 2 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 2. LPCI System (continued)

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

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

ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-10 Amendment 274 315 Table 3.3.5.1

-1 (page 3 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 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.

3 SR 3.3.5.1.6

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

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

- :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) With rector steam dose pressure > 150 psig.

ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-11 Amendment 274 315 Table 3.3.5.1

-1 (page 4 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 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

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 3.3.5.1.6 177 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.

3 SR 3.3.5.1.6 105 psig and 145 psig 5. ADS Trip System B

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 (continued)

c. With rector steam dose pressure > 150 psig.

ECCS Instrumentation 3.3.5.1 JAFNPP 3.3.5.1-12 Amendment 274 315 Table 3.3.5.1

-1 (page 5 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 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

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.

3 SR 3.3.5.1.

6 105 psig and 145 psig (continued) d)c) With rector steam dose pressure > 150 psig.

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

NO T E-----------

Separate Condition ent r y is allowed for each ch annel. ---------------

CONDITION REQUIR E D ACTION COMPLET I ON T I M E A. O ne or more channels inoperable.

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.

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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RPV Water Inventory C ontrol Instrumentation 3.3.5.2 JAFNPP 3.3.5.2-2 Amendment 315 ACTIONS (continued)

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.

Immediately SUR VEILL ANCE REQU IREMENTS ---------------

NO T E-----------

Refer to Table 3.3.5.2-1 t o determine which SRs apply for each ECCS F unction. ---------------

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

a. a. Reactor Pressure Low (Injection Permissive) 4, 5 4 C SR 3.3.5.2.1 SR 3.3.5.2.2

< 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

> 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

a. a. Reactor Pressure Low (Injection Permissive) 4, 5 4 C SR 3.3.5.2.1 SR 3.3.5.2.2

< 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

> 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

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

> 177 inches

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

> 177 inches (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.

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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of RCIC initiation capability B.2 Place channel in Trip. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months C. As required by Required Action A.1 and referenced in Table 3.3.5.

3 2-1. C.1 Restore channel in OPERABLE status.

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

RCIC System Instrumentation 3.3.5.3 2 JAFNPP 3.3.5.3 2-2 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.

3 2-1. D.1 - - - - - -NOTE- - - - - - - Only applicable if RCIC pump suction is not aligned to the suppression pool.

- - - - - - - - - - - - - - - - - Declare (R CI C) System inoperable.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery of loss of automatic R CI C initiation capability D.2.1 Place channel in trip. OR 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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. Required Action and associated Completion Time of Condition B, C, or D not met.

E.1 Declare RCIC System inoperable.

Immediately

RCIC System Instrumentation 3.3.5.3 2 JAFNPP 3.3.5.3 2-3 Amendment 301 315 SURVEILLANCE REQUIREMENTS

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - 1. Refer to Table 3.3.5.

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 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 fo r Functions 1 and 3 provided the associated Function maintains RCIC initiation capability.

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

In accordance with the Surveillance Frequency Control Progra m SR 3.3.5.3 2.3 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Progra m SR 3.3.5.3 2.4 Calibrate the trip units.

In accordance with the Surveillance Frequency Control Progra m SR 3.3.5.3 2.5 Perform CHANNEL CALIBRATION.

In accordance with the Surveillance Frequency Control Progra m SR 3.3.5.3 2.6 Perform LOGIC SYSTEM FUNCTIONAL TEST.

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.

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.

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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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

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

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

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 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)

(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.

Secondary Containment Isolation Instrumentation 3.3.6.2 JAFNPP 3.3.6.2-4 Amendment 27 6 315 ` Table 3.3.6.2

-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1. Reactor Vessel Water Level Low (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

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

- 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

- 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.

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

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)

System Instrumentation LCO 3.3.7.1 The Control Room Air Inlet RadiationHigh 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 REQUIRED ACTION COMPLETION TIME A. Channel inoperable.

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

OR A.2 Declare both CREVAS subsystems inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CREVAS System Instrumentation 3.3.7.1 JAFNPP 3.3.7.1-2 Amendment 301 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 Value shall be 4000 cpm. In accordance with the Surveillance Frequency Control Program

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.

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 psig. ACTIONS ---------------------------------------------------------NOTE-------------------------------------------------------------

LCO 3.0.4.b is not applicable to HPCI.

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

OR One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.

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.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

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 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . AND OneTwo low pressure ECCS injection/spray subsystem s 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.

APPLICABILITY:

MODE S 4 and 5 MODES 5, except with the spent fuel storage pool gates the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One r Required low pressure ECCS injection/spray subsystem inoperable.

A.1 Restore required low pressure ECCS injection/spray subsystem to OPER ABLE status. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion Time of Condition A not met. B.1 Initiate action to establish a method of water injection capable of operating without offsite electrical power. Initiate action to suspend operations with.a potential for draining the reactor vessel (OPDRVs).

Immediately

RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-2 Amendment 274 315 C. DRAIN TIME < 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months and 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . 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 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. Two required low pressure ECCS injection/spray subsystems inoperable.

C.1 Initiate action to suspend OPDRVs.

AND Immediately C.2 Restore one required low pressure ECCS injection/spray subsystem to OPERBLE status. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (continued)

RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-2 Amendment 274 315 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. DRAIN TIME < 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .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.

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

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

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.

E. Required Action and associa t ed Completion Time of Condition C or D not met. O R DRAIN T I ME < 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . E.1 Initiate ac t i o n to restore DRAIN T I ME to 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . Immediately SURVEILLANCE REQUIREMENTS SURVELLANCE FREQUENCY SR 3.5.2.1 Verify DRA I N TIME 3 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . 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)

RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-4 Amendment 274 315 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

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

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

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.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Verify each for the required ECCS injection/spray subsystem

, 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 Progra m (continued)

RPV Water Inventory Control ECCS - Shutdown 3.5.2 JAFNPP 3.5.2-5 Amendment 274 315 SURVEILLANCE REQUIREMENTS (continued)

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.

In accordance with the Surveillance Frequency Control Program SR 3.5.2.6 8 - - - - - - - - - - - - - - -NOTE - - - - - - - - - - - - - - - - Vessel injection/spray may be excluded.

- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - Verify theeach required ECCS injection/spray subsystem actuates on an a manual actual or simulated automatic initiation signal.

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.

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 REQUIRED ACTION COMPLETION TIME A. RCIC System inoperable.

A.1 Verify by administrative means High Pressure Coolant Injection System is OPERABLE. AND A.2 Restore RCIC System to OPERABLE status.

Immediately 14 days B. Required Action and associated Completion Time not met.

B.1 Be in MODE

3. AND B.2 Reduce reactor steam dome pressure to 50 psig. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months PCIVs 3.6.1.3 JAFNPP 3.6.1.3-6 Amendment 274 315 ACTIONS (continued)

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.

F.1 Be in MODE 3.

AND F.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months 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.

Immediately

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.

APPLICABILITY:

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment inoperable in MODE 1, 2, or 3. A.1 Restore secondary containment to OPERABLE status. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Action and associated Completion Time of Condition A not met. B.1 Be in MODE

3. AND B.2 Be in MODE

4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Secondary containment inoperable during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs

. C.1 ------------NOTE------------ LCO 3.0.3 is not applicable.

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

AND Immediately (continued)

Secondary Containment 3.6.4.1 JAFNPP 3.6.4.1-2 Amendment 301 315 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)

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.

In accordance with the Surveillance Frequency Control Program SR 3.6.4.1.2 Verify all secondary containment equipment hatches are closed and sealed.

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.

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

LCO 3.6.4.2 Each SCIV shall be OPERABLE.

APPLICABILITY:

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

ACTIONS ----------------------------------------------------NOTES----------------------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration flow paths with one SCIV inoperable.

A.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (continued)

SCIVs 3.6.4.2 JAFNPP 3.6.4.2-2 Amendment 27 4 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 administrative means. ----------------------------- Verify the affected penetration flow path is isolated. Once per 31 days.

B. ---------NOTE--------- Only applicable to penetration flow paths with two isolation valves. ----------------------

One or more penetration flow paths with two SCIVs inoperable.

B.1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1 Be in MODE

3. AND C.2 Be in MODE

4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

SCIVs 3.6.4.2 JAFNPP 3.6.4.2-3 Amendment 276 315 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. D.1 --------NOTE--------- LCO 3.0.3 is not applicable.

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

AND D.2Initiate action to suspend OPDRVs. Immediately Immediately

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.

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.

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.

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.

APPLICABILITY:

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

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

A.1 Restore SGT subsystem to OPERABLE status.

7 days B. Required Action and associated Completion Time of Condition A not met in MODE 1, 2, or 3. B.1 Be in MODE

3. AND B.2 Be in MODE

4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs

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

NOTE---------------- LCO 3.0.3 is not applicable.

C.1 Place OPERABLE SGT subsystem in operation.

OR Immediately (continued)

SGT System 3.6.4.3 JAFNPP 3.6.4.3-2 Amendment 276 315 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued)

C.2.1 Suspend movement of recently irradiated fuel assemblies in secondary containment.

AND C.2.2 Initiate action to suspend OPDRVs.

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.

E.1 --------NOTE--------- LCO 3.0.3 is not applicable.

Suspend movement of recently irradiated fuel assemblies in secondary containment.

AND E.2 Initiate action to suspend OPDRVs.

Immediately Immediately

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.

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).

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.

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.

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

The control room envelope (CRE) boundary may be opened intermittently under administrative control.

APPLICABILITY:

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREVAS subsystem inoperable for reasons other than Condition B

. 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.

Immediately 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 90 days (continued)

CREVAS System 3.7.3 JAFNPP 3.7.3-2 Amendment 289 315 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition A or B not met in MODE 1, 2, or 3. C.1 Be in MODE

3. AND C.2 Be in MODE

4. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Required Action and associated Completion Time of Condition A not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs. --------------

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

LCO 3.0.3 is not applicable.

D.1 Place OPERABLE CREVAS subsystem in isolate mode.

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

AND D.2.2 Initiate action to suspend OPDRVs. Immediately Immediately Immediately E. Two CREVAS subsystems inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

E.1 Enter LCO 3.0.3. Immediately (continued)

CREVAS System 3.7.3 JAFNPP 3.7.3-3 Amendment 301 315 ACTIONS (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.

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

LCO 3.0.3 is not applicable.

F.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND F.2 Initiate action to suspend OPDRVs. Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 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)

SURVEILLANCE FREQUENCY SR 3.7.3.3 Perform required CRE unfiltered air in

-leakage testing in accordance with the control room Envelope Habitability Program. In accordance with the Control Room Envelope Habitability Program Control Room 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.

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 Restore control room AC subsystem to OPERABLE status. 30 days B. Two control room AC subsystems inoperable.

B.1 Verify control room area temperature

< 90 °F. AND B.2 Restore one control room AC subsystem to OPERABLE status.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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.

AND C.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

Control Room AC System 3.7.4 JAFNPP 3.7.4-2 Amendment 290 315 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.

- - - - - - - - - NOTE - - - - - - - - - - LCO 3.0.3 is not applicable.

- - - - - - - - - - - - - - - - - - - - - - - - D.1 Place OPERABLE control room AC subsystem in operation.

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

AND D.2.2 Initiate action to suspend OPDRVs. Immediately Immediately Immediately E. Required Action and associated Completion Time of Condition B not met during movement of recently irradiated fuel assemblies in the secondary containment or during OPDRVs.

- - - - - - - - - NOTE - - - - - - - - - - LCO 3.0.3 is not applicable.

- - - - - - - - - - - - - - - - - - - - - - - - E.1 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND E.2 Initiate action to suspend OPDRVs. Immediately Immediately SURVEILLANCE REQUIREMENTS

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.

In accordance with the Surveillance Frequency Control Program

AC Sources

- Shutdown 3.8.2 JAFNPP 3.8.2-1 Amendment 276 315 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 of supplying one division of the plant Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8. APPLICABILITY:

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

AC Sources

- Shutdown 3.8.2 JAFNPP 3.8.2-2 Amendment 276 315 ACTIONS -------------------------------------------------

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

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or both required offsite circuits inoperable.

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

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

OR A.2.1 Suspend CORE ALTERATIONS.

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

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

AND Immediately Immediately Immediately Immediately (continued)

AC Sources

- Shutdown 3.8.2 JAFNPP 3.8.2-3 Amendment 276 315 ACTIONSCONDITION REQUIRED ACTION COMPLETION TIME A. (continued)

A.2.3 4 Initiate action to restore required offsite power circuit(s) to OPERABLE status.

Immediately B. One required EDG subsystem inoperable.

B.1 Suspend CORE ALTERATIONS.

AND B.2 Suspend movement of recently irradiated fuel assemblies in secondary containment.

AND B.3 Initiate action to suspend OPDRVs.

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

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

." ------------------------------------------------------------

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.

CONDITION REQUIRED ACTION COMPLETION TIME A. Required DC electrical power subsystem inoperable.

A.1 Declare affected required feature(s) inoperable.

OR A.2.1 Suspend CORE ALTERATIONS.

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

AND Immediately Immediately Immediately (continued)

DC Sources

-Shutdown 3.8.5 JAFNPP 3.8.5-2 Amendment 27 4 315 ACTIONS CONDITIONS REQUIRED ACTION COMPLETION TIME A. (continued)

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

-- 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 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.

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.

OR A.2.1 Suspend CORE ALTERATIONS.

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

AND Immediately Immediately Immediately (continued)

Distribution Systems

- Shutdown 3.8.8 JAFNPP 3.8.8-2 Amendment 301 315 ACTIONS (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.

AND A.2.4 5 Declare associated required shutdown cooling subsystem(s) inoperable.

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.

In accordance with the Surveillance Frequency Control Program

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

1.1 Definitions

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