Text

GE-Hitachi ABWR Design Control Document Tier 1 & 2, Rev. 7 - Chapter 16 - Technical Specifications
	ML20007E349
Person / Time
Site:	05200001, 05200045
Issue date:	12/20/2019
From:	Michelle Catts; GE-Hitachi Nuclear Energy Americas
To:	; Office of Nuclear Reactor Regulation
	Shea J
References
	GEHITACHIABWR, GEHITACHIABWR.SUBMISSION.8, 25A5675.P, 25A5675.P.7
	Download: ML20007E349 (341)
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25A5675AU Revision 7 TABLE OF CONTENTS 16.0 TECHNICAL SPECIFICATIONS ............................................................... 16.0-1 1.0 USE AND APPLICATION .......................................................................... 1.1-1 1.1 Definitions .......................................................................................... 1.1-1 1.2 Logical Connectors ............................................................................ 1.2-1 1.3 Completion Times.............................................................................. 1.3-1 1.4 Frequency.......................................................................................... 1.4-1 2.0 SAFETY LIMITS (SLs) ............................................................................... 2.0-1 2.1 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 3.1.1 Shutdown Margin (SDM) ............................................................. 3.1-1 3.1.2 Reactivity Anomalies ................................................................... 3.1-4 3.1.3 Control Rod OPERABILITY ......................................................... 3.1-6 3.1.4 Control Rod Scram Times ........................................................... 3.1-10 3.1.5 Control Rod Scram Accumulators ............................................... 3.1-13 3.1.6 Rod Pattern Control ..................................................................... 3.1-15 3.1.7 Standby Liquid Control (SLC) System ......................................... 3.1-17 3.2 POWER DISTRIBUTION LIMITS ...................................................... 3.2-1 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR) ........... 3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR)........................................ 3.2-2 3.2.3 Linear Heat Generation Rate (LHGR) (Non-GE Fuel) ................. 3.2-3 3.3 INSTRUMENTATION ........................................................................ 3.3-1 3.3.1.1 Safety System Logic and Control (SSLC) Sensor Instrumentation ...................................................................... 3.3-1 3.3.1.2 Reactor Protection System (RPS) and Main Steam Isolation Valve (MSIV) Actuation .......................................................... 3.3-20 3.3.1.3 Standby Liquid Control (SLC) and Feedwater Runback (FWRB) Actuation .................................................................. 3.3-27 3.3.1.4 ESF Actuation Instrumentation .................................................... 3.3-31 3.3.2.1 Startup Range Monitor (SRNM) Instrumentation ......................... 3.3-44 3.3.3.1 Essential Multiplexing System (EMS) .......................................... 3.3-49 3.3.4.1 Anticipated Transient Without Scram (ATWS) and End-of-Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation ...................................................................... 3.3-51 3.3.4.2 Feedwater and Main Turbine Trip Instrumentation ...................... 3.3-58 3.3.5.1 Control Rod Block Instrumentation .............................................. 3.3-60 (continued)

ABWR TS i Design Control Document/Tier 2

25A5675AU Revision 7 TABLE OF CONTENTS 3.3 INSTRUMENTATION (continued) 3.3.6.1 Post Accident Monitoring (PAM) Instrumentation ........................ 3.3-64 3.3.6.2 Remote Shutdown System .......................................................... 3.3-68 3.3.7.1 Control Room Habitability Area (CRHA) Emergency Filtration (EF) System Instrumentation .................................. 3.3-72 3.3.8.1 Electric Power Monitoring ............................................................ 3.3-75 3.3.8.2 Reactor Coolant Temperature Monitoring - Shutdown ............... 3.3-77 3.4 REACTOR COOLANT SYSTEM (RCS) ............................................ 3.4-1 3.4.1 Reactor Internal Pumps (RIPs) - Operating ................................ 3.4-1 3.4.2 Safety/Relief Valves (S/RVs) ....................................................... 3.4-2 3.4.3 RCS Operational LEAKAGE ........................................................ 3.4-4 3.4.4 RCS Pressure Isolation Valve (PIV) Leakage ............................. 3.4-6 3.4.5 RCS Leakage Detection Instrumentation .................................... 3.4-8 3.4.6 RCS Specific Activity ................................................................... 3.4-11 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ........................................................ 3.4-13 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ...................................................... 3.4-16 3.4.9 RCS Pressure and Temperature (P/T) Limits .............................. 3.4-18 3.4.10 Reactor Steam Dome Pressure ................................................... 3.4-21 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ....................... 3.5-1 3.5.1 ECCS - Operating ....................................................................... 3.5-1 3.5.2 ECCS - Shutdown ....................................................................... 3.5-6 3.6 CONTAINMENT SYSTEMS .............................................................. 3.6-1 3.6.1.1 Primary Containment ................................................................... 3.6-1 3.6.1.2 Primary Containment Air Locks ................................................... 3.6-3 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ........................... 3.6-8 3.6.1.4 Drywell Pressure.......................................................................... 3.6-17 3.6.1.5 Drywell Air Temperature .............................................................. 3.6-18 3.6.1.6 Wetwell-to-Drywell Vacuum Breakers ......................................... 3.6-19 3.6.2.1 Suppression Pool Average Temperature..................................... 3.6-21 3.6.2.2 Suppression Pool Water Level .................................................... 3.6-24 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ......... 3.6-25 3.6.2.4 Residual Heat Removal (RHR) Containment Spray .................... 3.6-27 3.6.3.1 Primary Containment Hydrogen Recombiners ............................ 3.6-29 3.6.3.2 Primary Containment Oxygen Concentration .............................. 3.6-31 3.6.4.1 Secondary Containment .............................................................. 3.6-32 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ...................... 3.6-34 3.6.4.3 Standby Gas Treatment (SGT) System ....................................... 3.6-38 3.7 PLANT SYSTEMS ............................................................................. 3.7-1 3.7.1 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Operating ......................................................... 3.7-1 (continued)

ABWR TS ii Design Control Document/Tier 2

25A5675AU Revision 7 TABLE OF CONTENTS 3.7 PLANT SYSTEMS (continued) 3.7.2 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Shutdown ......................................................... 3.7-4 3.7.3 Reactor Building Cooling Water (RCW) System and Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Refueling .................................................................. 3.7-7 3.7.4 Control Room Habitability Area (CRHA) - Emergency Filtration (EF) System ............................................................ 3.7-9 3.7.5 Control Room Habitability Area (CRHA) - Air Conditioning (AC) System .......................................................................... 3.7-12 3.7.6 Main Condenser Offgas ............................................................... 3.7-15 3.7.7 Main Turbine Bypass System ...................................................... 3.7-17 3.7.8 Fuel Pool Water Level ................................................................. 3.7-19 3.8 ELECTRICAL POWER SYSTEMS .................................................... 3.8-1 3.8.1 AC Sources - Operating .............................................................. 3.8-1 3.8.2 AC Sources - Refueling .............................................................. 3.8-18 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air ................................... 3.8-21 3.8.4 DC Sources - Operating.............................................................. 3.8-24 3.8.5 DC Sources - Shutdown ............................................................. 3.8-28 3.8.6 Battery Cell Parameters............................................................... 3.8-30 3.8.7 Inverters - Operating ................................................................... 3.8-34 3.8.8 Inverters - Shutdown ................................................................... 3.8-36 3.8.9 Distribution Systems - Operating ................................................ 3.8-38 3.8.10 Distribution Systems - Shutdown ................................................ 3.8-42 3.8.11 AC Sources - Shutdown (Low Water Level) ............................... 3.8-44 3.9 REFUELING OPERATIONS ............................................................. 3.9-1 3.9.1 Refueling Equipment Interlocks ................................................... 3.9-1 3.9.2 Refuel Position Rod-Out Interlock ............................................... 3.9-2 3.9.3 Control Rod Position .................................................................... 3.9-3 3.9.4 Control Rod Position Indication ................................................... 3.9-4 3.9.5 Control Rod OPERABILITY - Refueling ...................................... 3.9-6 3.9.6 Reactor Pressure Vessel (RPV) Water Level .............................. 3.9-7 3.9.7 Residual Heat Removal (RHR) - High Water Level .................... 3.9-8 3.9.8 Residual Heat Removal (RHR) - Low Water Level ..................... 3.9-10 3.10 SPECIAL OPERATIONS ................................................................... 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation ...................... 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing ....................................... 3.10-3 3.10.3 Control Rod Withdrawal - Hot Shutdown .................................... 3.10-5 3.10.4 Control Rod Withdrawal - Cold Shutdown .................................. 3.10-8 3.10.5 Control Rod Drive (CRD) Removal - Refueling........................... 3.10-11 3.10.6 Multiple Control Rod Withdrawal - Refueling .............................. 3.10-13 3.10.7 Control Rod Testing - Operating ................................................. 3.10-15 (continued)

ABWR TS iii Design Control Document/Tier 2

25A5675AU Revision 7 TABLE OF CONTENTS 3.10 SPECIAL OPERATIONS (continued) 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling.......................... 3.10-16 3.10.9 Reactor Internal Pumps (RIPs) - Testing .................................... 3.10-19 3.10.10 Training Startups ......................................................................... 3.10-20 3.10.11 Low Power PHYSICS TEST ........................................................ 3.10-21 3.10.12 Multiple Control Rod Drive Subassembly Removal - Refueling ............................................................. 3.10-24 4.0 DESIGN FEATURES ................................................................................. 4.0-1 4.1 Site .................................................................................................... 4.0-1 4.2 Reactor Core ..................................................................................... 4.0-1 4.3 Fuel Storage ...................................................................................... 4.0-1 5.0 ADMINISTRATIVE CONTROLS ................................................................ 5.0-1 5.1 Responsibility .................................................................................... 5.0-1 5.2 Organization ...................................................................................... 5.0-2 5.3 Unit Staff Qualifications ..................................................................... 5.0-5 5.4 Technical Specifications (TS) Bases Control .................................... 5.0-6 5.5 Procedures, Programs, and Manuals ................................................ 5.0-7 5.6 Safety Function Determination Program (SFDP) .............................. 5.0-15 5.7 Reporting Requirements.................................................................... 5.0-17 (continued)

ABWR TS iv Design Control Document/Tier 2

25A5675AU Revision 7 TABLE OF CONTENTS (continued)

B 2.0 SAFETY LIMITS (SLs) ............................................................................... B 2.0-1 B 2.1.1 Reactor Core SLs ........................................................................ B 2.0-1 B 2.1.2 Reactor Coolant System (RCS) Pressure SL .............................. B 2.0-6 B 3.0 LIMITING CONDITION FOR OPERATION (LCOs) AND SURVEILLANCE REQUIREMENTS (SRs) ....................................... B 3.0-1 B 3.1 REACTIVITY CONTROL SYSTEMS ................................................. B 3.1-1 B 3.1.1 Shutdown Margin (SDM) ............................................................. B 3.1-1 B 3.1.2 Reactivity Anomalies ................................................................... B 3.1-6 B 3.1.3 Control Rod OPERABILITY ......................................................... B 3.1-10 B 3.1.4 Control Rod Scram Times ........................................................... B 3.1-19 B 3.1.5 Control Rod Scram Accumulators ............................................... B 3.1-25 B 3.1.6 Rod Pattern Control ..................................................................... B 3.1-29 B 3.1.7 Standby Liquid Control (SLC) System ......................................... B 3.1-33 B 3.2 POWER DISTRIBUTION LIMITS ...................................................... B 3.2-1 B 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) ................................................................... B 3.2-1 B 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)........................... B 3.2-4 B 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)

(Non-GE Fuel) ....................................................................... B 3.2-8 B 3.3 INSTRUMENTATION ........................................................................ B 3.3-1 B 3.3.1.1 Safety System Logic and Control (SSLC) Sensor Instrumentation ...................................................................... B 3.3-1 B 3.3.1.2 Reactor Protection System (RPS) and Main Steam Isolation Valve (MSIV) Actuation .......................................................... B 3.3-74 B 3.3.1.3 Standby Liquid Control (SLC) and Feedwater Runback (FWRB) Actuation .................................................................. B 3.3-89 B 3.3.1.4 Engineered Safety Features (ESF) Actuation Instrumentation ...................................................................... B 3.3-96 B 3.3.2.1 Startup Range Neutron Monitor (SRNM) Instrumentation ........... B 3.3-130 B 3.3.3.1 Essential Multiplexing System (EMS) .......................................... B 3.3-139 B 3.3.4.1 Anticipated Transient Without Scram (ATWS) and End of Cycle Recirculation Pump Trip (EOC-RPT)

Instrumentation ...................................................................... B 3.3-144 B 3.3.4.2 Feedwater and Main Turbine Trip Instrumentation ...................... B 3.3-166 B 3.3.5.1 Control Rod Block Instrumentation .............................................. B 3.3-172 B 3.3.6.1 Post Accident Monitoring (PAM) Instrumentation ........................ B 3.3-181 B 3.3.6.2 Remote Shutdown System .......................................................... B 3.3-192 B 3.3.7.1 Control Room Habitability Area (CRHA) Emergency Filtration (EF) System Instrumentation .................................. B 3.3-202 B 3.3.8.1 Electric Power Monitoring ............................................................ B 3.3-209 B 3.3.8.2 Reactor Coolant Temperature Monitoring ................................... B 3.3-214 (continued)

ABWR TS v Design Control Document/Tier 2

25A5675AU Revision 7 TABLE OF CONTENTS B 3.0 LIMITING CONDITION FOR OPERATION (LCOs) AND SURVEILLANCE REQUIREMENTS (SRs) (continued)

B 3.4 REACTOR COOLANT SYSTEM (RCS) ............................................ B 3.4-1 B 3.4.1 Reactor Internal Pumps (RIPs) - Operating ................................ B 3.4-1 B 3.4.2 Safety/Relief Valves (S/RVs) ....................................................... B 3.4-4 B 3.4.3 RCS Operational LEAKAGE ........................................................ B 3.4-8 B 3.4.4 RCS Pressure Isolation Valve (PIV) Leakage ............................. B 3.4-12 B 3.4.5 RCS Leakage Detection Instrumentation .................................... B 3.4-17 B 3.4.6 RCS Specific Activity ................................................................... B 3.4-22 B 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ........................................................ B 3.4-27 B 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown ...................................................... B 3.4-31 B 3.4.9 RCS Pressure and Temperature (P/T) Limits .............................. B 3.4-35 B 3.4.10 Reactor Steam Dome Pressure ................................................... B 3.4-42 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) ....................... B 3.5-1 B 3.5.1 ECCS - Operating ....................................................................... B 3.5-1 B 3.5.2 ECCS - Shutdown ....................................................................... B 3.5-16 B 3.6 CONTAINMENT SYSTEMS .............................................................. B 3.6-1 B 3.6.1.1 Primary Containment ................................................................... B 3.6-1 B 3.6.1.2 Primary Containment Air Locks ................................................... B 3.6-5 B 3.6.1.3 Primary Containment Isolation Valves (PCIVs) ........................... B 3.6-12 B 3.6.1.4 Drywell Pressure.......................................................................... B 3.6-27 B 3.6.1.5 Drywell Air Temperature .............................................................. B 3.6-29 B 3.6.1.6 Wetwell-to-Drywell Vacuum Breakers ......................................... B 3.6-32 B 3.6.2.1 Suppression Pool Average Temperature..................................... B 3.6-37 B 3.6.2.2 Suppression Pool Water Level .................................................... B 3.6-42 B 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ......... B 3.6-45 B 3.6.2.4 Residual Heat Removal (RHR) Containment Spray .................... B 3.6-49 B 3.6.3.1 Primary Containment Hydrogen Recombiners ............................ B 3.6-53 B 3.6.3.2 Primary Containment Oxygen Concentration .............................. B 3.6-58 B 3.6.4.1 Secondary Containment .............................................................. B 3.6-61 B 3.6.4.2 Secondary Containment Isolation Valves (SCIVs) ...................... B 3.6-66 B 3.6.4.3 Standby Gas Treatment (SGT) System ....................................... B 3.6-72 B 3.7 PLANT SYSTEMS ............................................................................. B 3.7-1 B 3.7.1 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System, and Ultimate Heat Sink (UHS) - Operating ......................................................... B 3.7-1 B 3.7.2 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Shutdown ......................................................... B 3.7-9 (continued)

ABWR TS vi Design Control Document/Tier 2

25A5675AU Revision 7 TABLE OF CONTENTS B 3.7 PLANT SYSTEMS (continued)

B 3.7.3 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Refueling .......................................................... B 3.7-14 B 3.7.4 Control Room Habitability Area (CRHA) - Emergency Filtration (EF) System ............................................................ B 3.7-18 B 3.7.5 Control Room Habitability Area (CRHA) - Air Conditioning (AC) System .......................................................................... B 3.7-24 B 3.7.6 Main Condenser Offgas ............................................................... B 3.7-28 B 3.7.7 Main Turbine Bypass System ...................................................... B 3.7-31 B 3.7.8 Fuel Pool Water Level ................................................................. B 3.7-34 B 3.8 ELECTRICAL POWER SYSTEMS .................................................... B 3.8-1 B 3.8.1 AC Sources - Operating .............................................................. B 3.8-1 B 3.8.2 AC Sources - Refueling .............................................................. B 3.8-34 B 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air Subsystem ................ B 3.8-40 B 3.8.4 DC Sources - Operating.............................................................. B 3.8-48 B 3.8.5 DC Sources - Shutdown ............................................................. B 3.8-58 B 3.8.6 Battery Cell Parameters............................................................... B 3.8-61 B 3.8.7 Inverters - Operating ................................................................... B 3.8-66 B 3.8.8 Inverters - Shutdown ................................................................... B 3.8-70 B 3.8.9 Distribution Systems - Operating ................................................ B 3.8-73 B 3.8.10 Distribution Systems - Shutdown ................................................ B 3.8-82 B 3.8.11 AC Sources - Shutdown (Low Water Level) ............................... B 3.8-86 B 3.9 REFUELING OPERATIONS ............................................................. B 3.9-1 B 3.9.1 Refueling Equipment Interlocks ................................................... B 3.9-1 B 3.9.2 Refuel Position Rod-Out Interlock ............................................... B 3.9-4 B 3.9.3 Control Rod Position .................................................................... B 3.9-7 B 3.9.4 Control Rod Position Indication ................................................... B 3.9-9 B 3.9.5 Control Rod OPERABILITY - Refueling ...................................... B 3.9-12 B 3.9.6 Reactor Pressure Vessel (RPV) Water Level .............................. B 3.9-15 B 3.9.7 Residual Heat Removal (RHR) - High Water Level .................... B 3.9-17 B 3.9.8 Residual Heat Removal (RHR) - Low Water Level ..................... B 3.9-21 B 3.10 SPECIAL OPERATIONS ................................................................... B 3.10-1 B 3.10.1 Inservice Leak and Hydrostatic Testing Operation ...................... B 3.10-1 B 3.10.2 Reactor Mode Switch Interlock Testing ....................................... B 3.10-5 B 3.10.3 Control Rod Withdrawal - Hot Shutdown .................................... B 3.10-9 B 3.10.4 Control Rod Withdrawal - Cold Shutdown .................................. B 3.10-13 B 3.10.5 Control Rod Drive (CRD) Removal - Refueling........................... B 3.10-17 B 3.10.6 Multiple Control Rod Withdrawal - Refueling .............................. B 3.10-21 B 3.10.7 Control Rod Testing - Operating ................................................. B 3.10-24 B 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling.......................... B 3.10-27 B 3.10.9 Reactor Internal Pumps - Testing ............................................... B 3.10-31 (continued)

ABWR TS vii Design Control Document/Tier 2

25A5675AU Revision 7 TABLE OF CONTENTS B 3.10 SPECIAL OPERATIONS (continued)

B 3.10.10 Training Startups ......................................................................... B 3.10-34 B 3.10.11 Low Power PHYSICS TESTS...................................................... B 3.10-36 B 3.10.12 Multiple Control Rod Drive Subassembly Removal - Refueling ............................................................. B 3.10-40 ABWR TS viii Design Control Document/Tier 2

25A5675AU Revision 7 ABWR Design Control Document/Tier 2 16.0 Technical Specifications The NRC Policy Statement (Federal Register, Vol. 52, No.25, February 6, 1987) recognizes that:

The purpose of Technical Specifications is to impose conditions or limitations upon reactor operation necessary to obviate the possibility of an abnormal situation or event giving rise to an immediate threat to the public health and safety by establishing those conditions of operation which cannot be changed without prior Commission approval and by identifying those features which are of controlling importance to safety.

This set of proposed Technical Specifications establish these conditions and limitations for the ABWR. This set of Technical Specifications is intended to be used as a guide in the development of plant specific sets of Technical Specifications for license applications that reference the ABWR standard plant.

The NRC Policy Statement criteria stated below has been used to identify all structures, systems, and parameters for which Limiting Conditions for Operation (LCOs) have been included in the ABWR Technical Specifications:

1. Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.

2. A process variable that is an initial condition of a Design Basis Accident (DBA) or Transient Analyses that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

3. A structure, system or component that is part of the primary success path and which functions or actuates to mitigate a Design Basis Accident or Transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.

4. Structures, systems, and components which operating experience and probabilistic risk assessment have generally shown to be important to public health and safety.

The content of the ABWR Technical Specifications meets the 10CFR50.36, Technical Specifications, requirements and is consistent with the approach of the Standard Technical Specification for BWRs, NUREGs 1433 and 1434, Revision 0, dated September 28, 1992 to the maximum extent possible. In addition, NRCs draft technical specifications on low power and shutdown have been incorporated. This submittal replaces the Chapter 16 Technical Specifications previously submitted in Amendment 9 in its entirety and has been restructured in accordance with NUREGs 1433 and 1434, Revision 0.

Technical Specifications 16.0-1

25A5675AU Revision 7 ABWR Design Control Document/Tier 2 16.1 COL License Information This section outlines the information required to be provided by the COL applicant to complete its plant specific Technical Specifications.

16.1.1 COL Information Required for Plant Specific Technical Specifications In cases where the detailed design, equipment selection, or other efforts are required to establish the information to be specified in Technical Specifications, [ ] has been indicated. The COL applicant will evaluate their applicability and provide the required information to complete its plant specific Technical Specifications.

As part of the Technical Specification Improvement Program undertaken by the NRC and the industry, portions of Section 5.0, Administrative Controls, of NUREGs 1433 and 1434, could be relocated to licensee-controlled document. This improvement has been incorporated into the ABWR Technical Specifications. The COL applicant will have to ensure that the portions of Section 5.0 relocated to licensee-controlled documents are controlled in accordance with an administrative control system acceptable to the NRC.

16.0-2 Technical Specifications

25A5675AU Revision 7 Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions

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

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.

Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific planar height HEAT GENERATION RATE and is equal to the sum of the LHGRs heat generation rate (APLHGR) per unit length of fuel rod for all the fuel rods in the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.

CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel such that it responds within the necessary range and accuracy to specified values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

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

(continued)

ABWR TS 1.1-1 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 1.1 Definitions (continued)

CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST shall be the injection of a TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

COMPREHENSIVE A COMPREHENSIVE FUNCTIONAL TEST (CoFT) is a set of FUNCTIONAL TEST tests that exercises each RPS, ESF, and MSIV closure Function by simulating accident events that exercise the inputs and outputs of the SSLC, NMS, PRRM, RPS/MSIV actuation logic and ESF actuation logic. A CoFT also simulates power failures, measures CPU and network performance, runs microprocessor-specific and application-specific diagnostics.

Test inputs include out-of-range conditions to verify OPERABILITY of the SSLC electronics, alarms and displays.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or other reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel. Movement of startup range neutron monitors, local power range monitors, traversing incore probes, or special movable detectors (including undervessel replacement) is not considered a CORE ALTERATION. In addition, control rod movement with other than the normal control rod drive is not considered a CORE ALTERATION provided there are no fuel assemblies in the associated core cell. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.7.1.5. Plant operation within these limits is addressed in individual Specifications.

(continued)

ABWR TS 1.1-2 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 1.1 Definitions (continued)

DIVISION FUNCTIONAL TEST The injection of simulated or actual signals into a division as close to the sensors as practicable to verify OPERABILITY of SENSOR CHANNELS and LOGIC CHANNELS in that division. The DIVISION FUNCTIONAL TEST may be performed by means of a series of sequential or overlapping steps. The test shall comprise all the equipment from the DTM inputs to LOGIC CHANNEL outputs. This test shall also verify that the inputs to the DTMs are the same as the information presented at the control room indicators.

DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same thyroid dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844, AEC, 1962, Calculation of Distance Factors for Power and Test Reactor Sites or those listed in Table E-7 of Regulatory Guide 1.109, Rev. 1, NRC, 1977 or ICRP 30, Supplement to Part 1, pages 192-212, Table titled`

Committed Dose Equivalent in Target Organs or Tissues per Intake of Unit Activity.

-AVERAGE shall be the average (weighted in proportion to the DISINTEGRATION ENERGY concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half lives > 15 minutes, making up at least 95% of the total noniodine activity in the coolant.

EMERGENCY CORE The ECCS RESPONSE TIME shall be that time interval from COOLING SYSTEM (ECCS) when the monitored parameter exceeds its ECCS initiation RESPONSE TIME setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

(continued)

ABWR TS 1.1-3 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 1.1 Definitions (continued)

ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

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

2. LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b. Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c. Total LEAKAGE Sum of the identified and unidentified LEAKAGE;

d. Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

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

(continued)

ABWR TS 1.1-4 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 1.1 Definitions (continued)

LOGIC CHANNEL A LOGIC CHANNEL is defined as a set of interconnecting hardware and software components that process the inputs to produce an identifiable RPS trip signal or ESF actuation signal within a division. For the RPS, this includes the trip signals associated TLU 2-out-of-4 voters, TLU bistable functions, operator controls, interlocks, data transmission, alarms, displays, division-of-sensors bypass, transmission lines out to the OLU inputs. Each ESF function will have two ESF LOGIC CHANNELs to include one of the ESF actuation signals associated SLU 2-out-of-4 voters, SLU bistable functions, operator controls, interlocks, data transmission, alarms, displays, division-of-sensors bypass, EMS, and transmission lines out to the input of the 2-out-of-2 voters. The ESF actuation signal includes the system actuation signal and all its associated device actuation signals generated in the SLU out to the 2-out-of-2 voter.

LOGIC SYSTEM A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all FUNCTIONAL TEST required logic components (i.e., all required relays and contacts, trip functions, solid state logic elements, etc.) of a logic path, from as close to the sensor as practicable up to, but not including, the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total system steps so that the entire logic system is tested.

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

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

(continued)

ABWR TS 1.1-5 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 1.1 Definitions (continued)

OPERABLE - OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, displays, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

OUTPUT CHANNEL An OUTPUT CHANNEL is defined as a set of interconnected components that process outputs from associated LOGIC CHANNELS to produce an identifiable signal that deenergizes scram solenoids, deenergizes MSIV Isolation solenoids, or energizes ESF device actuators within a division. For the RPS, this includes the signals associated OLU, transmission lines, manual divisional trip and reset switches, trip logic output bypass switch, parallel load driver test switch, and scram pilot valve solenoid load drivers. For the MSIVs, this includes the signals associated OLU, data transmission, manual divisional isolation and reset switches, trip logic output bypass switch, and MSIV isolation pilot valve solenoid load drivers. For the ESF, this includes the signals associated 2-out-of-2 voter, ESF Output Channel Bypass switch, and data transmission out to the ESF device actuator.

OUTPUT CHANNEL An OUTPUT CHANNEL FUNCTIONAL TEST is the FUNCTIONAL TEST injection of simulated or actual signals into the OUTPUT CHANNEL to verify OPERABILITY.

PHYSICS TESTS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.

These tests are:

a. Described in Chapter 14, Initial Test Program of the DCD Tier 2;

b. Authorized under the provisions of 10 CFR 50.59; or

c. Otherwise approved by the Nuclear Regulatory Commission.

(continued)

ABWR TS 1.1-6 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 1.1 Definitions (continued)

PRESSURE AND The PTLR is the unit specific document that provides the TEMPERATURE LIMITS reactor vessel pressure and temperature limits, including REPORT (PTLR) heatup and cooldown rates, for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.7.1.6. Plant operation within these operating limits is addressed in LCO 3.4.9, RCS Pressure and Temperature (P/T) Limits.

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 3926 MWt.

REACTOR PUMP TRIP The RPT SYSTEM RESPONSE TIME shall be that time (RPT) SYSTEM interval from initial signal generation (by the associated RESPONSE TIME turbine stop valve limit switch or the turbine control valve hydraulic oil pressure switch) to the trip of the inverters associated with the reactor internal pumps adjustable speed drives. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

REACTOR PROTECTION The RPS RESPONSE TIME shall be that time interval from SYSTEM (RPS) RESPONSE when the monitored parameter exceeds its RPS trip setpoint at TIME the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

SENSOR CHANNEL A SENSOR CHANNEL is defined as a set of interconnected hardware and software components that process an identifiable sensor signal within a division. This includes the sensor, data acquisition, signal conditioning, data transmission, alarms, displays, and all transmission lines in the division and between divisions associated with the sensor signal up to an input of a 2-out-of-4 voter or an input of a bistable function within the TLU or SLU.

SENSOR CHANNEL A SENSOR CHANNEL CALIBRATION is the adjustment, as CALIBRATION necessary, of the SENSOR CHANNEL such that it responds within the specified range and accuracy to specified values of the parameter that the SENSOR CHANNEL monitors. The calibration may be performed by any series of sequential, (continued)

ABWR TS 1.1-7 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 1.1 Definitions SENSOR CHANNEL overlapping, or total SENSOR CHANNEL test steps so that CALIBRATION the entire SENSOR CHANNEL is calibrated. Calibration of (continued) instrument channels with resistance temperature detector (RTD) or thermocouple sensors shall consist of an inplace cross calibration of the sensing elements and normal calibration of the remaining adjustments in the channel.

Whenever a sensing element is replaced, the next required inplace cross calibration consists of comparing the other sensing elements with the recently installed sensing element.

SENSOR CHANNEL CHECK A SENSOR CHANNEL CHECK is the qualitative assessment, by observation, of a SENSOR CHANNELs behavior during operation. This observation shall include comparison of this SENSOR CHANNELs indication to other indications derived from independent SENSOR CHANNELS. This check shall be performed so as to examine as much of the SENSOR CHANNEL as practicable.

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

a. The reactor is xenon free;

b. The moderator temperature is 20°C; and c All control rods are fully inserted except for the control rod pair of highest reactivity worth, which is assumed to be fully withdrawn.

With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SDM.

NOTE: A control rod pair consists of two control rods which are connected to the same, shared scram accumulator. All control rods share an accumulator except for the center control rod which has its own accumulator.

(continued)

ABWR TS 1.1-8 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 1.1 Definitions (continued)

STAGGERED TEST BASIS A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

TURBINE BYPASS SYSTEM The TURBINE BYPASS SYSTEM RESPONSE TIME consists RESPONSE TIME of two components:

a. The time from initial movement of the main turbine stop valve or control valve until 80% of the turbine bypass capacity is established; and

b. The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.

The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

ABWR TS 1.1-9 Design Control Document/Tier 2

25A5675AU Revision 7 Definitions 1.1 Table 1.1-1 (page 1 of 1)

MODES AVERAGE REACTOR REACTOR MODE COOLANT MODE TITLE SWITCH POSITION TEMPERATURE

°C 1 Power Operation Run NA 2 Startup Refuel(a) or Startup/Hot Standby NA 3 Hot Shutdown(a) Shutdown > 93 4 Cold Shutdown(a) Shutdown 93 5 Refueling(b) Shutdown or Refuel NA (a) All reactor vessel head closure bolts fully tensioned.

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

ABWR TS 1.1-10 Design Control Document/Tier 2

25A5675AU Revision 7 Logical Connectors 1.2 1.0 USE AND APPLICATION 1.2 Logical Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.

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

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

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

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

EXAMPLES The following examples illustrate the use of logical connectors.

(continued)

ABWR TS 1.2-1 Design Control Document/Tier 2

25A5675AU Revision 7 Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-1 (continued)

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

AND A.2 Restore . . .

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

(continued)

ABWR TS 1.2-2 Design Control Document/Tier 2

25A5675AU Revision 7 Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. LCO not met. A.1 Trip . . .

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Align . . .

This example represents a more complicated use of logical connectors.

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

ABWR TS 1.2-3 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.0 USE AND APPLICATION 1.3 Completion Times PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

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

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

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

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

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

(continued)

ABWR TS 1.3-1 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued) a. Must exist concurrent with the first inoperability; and

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

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

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

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

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

The above Completion Time extension does not apply to a Completion Time with a modified time zero. This modified time zero may be expressed as a repetitive time (i.e., once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , where the Completion Time is referenced from a previous completion of the Required Action versus the time of Condition entry) or as a time modified by the phrase from discovery . . . Example 1.3-3 illustrates one use of this type of Completion Time. The 10 day Completion Time specified for Conditions A and B in Example 1.3-3 may not be extended.

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

(continued)

ABWR TS 1.3-2 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-1 (continued)

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

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

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

(continued)

ABWR TS 1.3-3 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

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

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

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

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

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

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

(continued)

ABWR TS 1.3-4 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

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

(continued)

ABWR TS 1.3-5 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X subsystem subsystem to AND inoperable. OPERABLE status. 10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y Function Y subsystem subsystem to AND inoperable. OPERABLE status. 10 days from discovery of failure to meet the LCO C. One C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function X Function X subsystem subsystem to inoperable. OPERABLE status.

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

When one Function X subsystem and one Function Y subsystem are inoperable, Condition A and Condition B are concurrently applicable. The Completion Times for Condition A and Condition B are tracked separately for each subsystem, starting from the time each subsystem was declared (continued)

ABWR TS 1.3-6 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued) inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second subsystem was declared inoperable (i.e., the time the situation described in Condition C was discovered).

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

The Completion Times of Conditions A and B are modified by a logical connector, with a separate 10 day Completion Time measured from the time it was discovered the LCO was not met. In this example, without the separate Completion Time, it would be possible to alternate between Conditions A, B, and C in such a manner that operation could continue indefinitely without ever restoring systems to meet the LCO. The separate Completion Time modified by the phrase from discovery of failure to meet the LCO is designed to prevent indefinite continued operation while not meeting the LCO. This Completion Time allows for an exception to the normal time zero for beginning the Completion Time clock. In this instance, the Completion Time time zero is specified as commencing at the time the LCO was initially not met, instead of at the time the associated Condition was entered.

(continued)

ABWR TS 1.3-7 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

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

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

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

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

(continued)

ABWR TS 1.3-8 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

ACTIONS

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

Separate Condition entry is allowed for each inoperable valve.

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

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

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

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

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

(continued)

ABWR TS 1.3-9 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-6 (continued)

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

OR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months A.2 Reduce THERMAL POWER to 50% RTP.

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

Entry into Condition A offers a choice between Required Action A.1 or A.2. Required Action A.1 has a once per Completion Time, which qualifies for the 25% extension, per SR 3.0.2, to each performance after the initial performance. The initial 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Action A.1 is entered and the initial performance of Required Action A.1 must be completed within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval. If Required Action A.1 is followed and the Required Action is not met within the Completion Time (plus the extension allowed by SR 3.0.2), Condition B is entered. If Required Action A.2 is followed and the Completion Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

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

(continued)

ABWR TS 1.3-10 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months subsystem subsystem inoperable. isolated. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status.

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

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

(continued)

ABWR TS 1.3-11 Design Control Document/Tier 2

25A5675AU Revision 7 Completion Times 1.3 1.3 Completion Times (continued)

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

TIME ABWR TS 1.3-12 Design Control Document/Tier 2

25A5675AU Revision 7 Frequency 1.4 1.0 USE AND APPLICATION 1.4 Frequency PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

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

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

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

Sometimes special situations dictate when the requirements of a Surveillance are to be met. They are otherwise stated conditions allowed by SR 3.0.1. They may be stated as clarifying Notes in the Surveillance, as part of the Surveillance, or both. Example 1.4-4 discusses these special situations.

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

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

SR 3.0.4 restrictions would not apply if both the following conditions are satisfied:

a. The Surveillance is not required to be performed; and

b. The Surveillance is not required to be met or, even if required to be met, is not known to be failed.

(continued)

ABWR TS 1.4-1 Design Control Document/Tier 2

25A5675AU Revision 7 Frequency 1.4 1.4 Frequency (continued)

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

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

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

If the interval as specified by SR 3.0.2 is exceeded while the unit is not in a MODE or other specified condition in the Applicability of the LCO for which performance of the SR is required, the Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition. Failure to do so would result in a violation of SR 3.0.4.

(continued)

ABWR TS 1.4-2 Design Control Document/Tier 2

25A5675AU Revision 7 Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-2 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance Frequency, and the second is of the type shown in Example 1.4-1. The logical connector AND indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

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

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

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

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

(continued)

ABWR TS 1.4-3 Design Control Document/Tier 2

25A5675AU Revision 7 Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-3 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP.

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

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

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

Therefore, if the Surveillance were not performed within the 7 day interval (plus the extension allowed by SR 3.0.2) but operation was < 25% RTP, it would not constitute a failure of the SR or failure to meet the LCO. Also, no violation of SR 3.0.4 occurs when changing MODES, even with the 7 day Frequency not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power 25% RTP.

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

(continued)

ABWR TS 1.4-4 Design Control Document/Tier 2

25A5675AU Revision 7 Frequency 1.4 1.4 Frequency EXAMPLES EXAMPLE 1.4-4 (continued)

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY

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

Only required to be met in MODE 1.

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

ABWR TS 1.4-5 Design Control Document/Tier 2

25A5675AU Revision 7 SLs 2.0 2.0 SAFETY LIMITS (SLs) 2.1 SLs 2.1.1 Reactor Core SLs 2.1.1.1 With the reactor steam dome pressure < 5.41 MPaG or core flow

< 10% rated core flow:

THERMAL POWER shall be 25% RTP.

2.1.1.2 With the reactor steam dome pressure 5.41 MPaG and core flow 10% rated core flow:

MCPR shall be 1.07.

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

2.1.2 Reactor Coolant System Pressure SL Reactor steam dome pressure shall be 9.13 MPaG.

2.2 SL Violations With any SL violation, the following actions shall be completed:

2.2.1 Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , notify the NRC Operations Center, in accordance with 10 CFR 50.72.

2.2.2 Within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

2.2.2.1 Restore compliance with all SLs; and 2.2.2.2 Insert all insertable control rods.

2.2.3 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , notify the [General Manager - Nuclear Plant and Vice President - Nuclear Operations] and the [offsite reviewers specified in Specification 5.5.2, [Offsite] Review and Audit].

2.2.4 Within 30 days, a Licensee Event Report (LER) shall be prepared pursuant to 10 CFR 50.73. The LER shall be submitted to the NRC, the [offsite reviewers specified in Specification 5.5.2], and the [General Manager - Nuclear Plant and Vice President - Nuclear Operations].

2.2.5 Operation of the unit shall not be resumed until authorized by the NRC.

ABWR TS 2.0-1 Design Control Document/Tier 2

25A5675AU Revision 7 LCO Applicability 3.0 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY LCO 3.0.1 LCOs shall be met during the MODES or other specified conditions in the Applicability, except as provided in LCO 3.0.2 and LCO 3.0.7.

LCO 3.0.2 Upon discovery of a failure to meet an LCO, the Required Actions of the associated Conditions shall be met, except as provided in LCO 3.0.5 and LCO 3.0.6.

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

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

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

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

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

Exceptions to this Specification are stated in the individual Specifications.

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

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

LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated ACTIONS to be entered permit continued operation in the MODE or other specified condition in the Applicability for an unlimited period of time. This Specification shall not prevent changes in MODES or other specified conditions in the Applicability that are required to comply with ACTIONS.

(continued)

ABWR TS 3.0-1 Design Control Document/Tier 2

25A5675AU Revision 7 LCO Applicability 3.0 3.0 LCO APPLICABILITY LCO 3.0.4 Exceptions to this Specification are stated in the individual Specifications.

(continued) These exceptions allow entry into MODES or other specified conditions in the Applicability when the associated ACTIONS to be entered allow unit operation in the MODE or other specified condition in the Applicability only for a limited period of time.

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

LCO 3.0.6 When a supported system LCO is not met solely due to a support system LCO not being met, the Conditions and Required Actions associated with this supported system are not required to be entered. Only the support system LCO ACTIONS are required to be entered. This is an exception to LCO 3.0.2 for the supported system. In this event, additional evaluations and limitations may be required in accordance with Specification 5.8, Safety Function Determination Program (SFDP). If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

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

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

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

ABWR TS 3.0-2 Design Control Document/Tier 2

25A5675AU Revision 7 SR Applicability 3.0 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY SR 3.0.1 SRs shall be met during the MODES or other specified conditions in the Applicability for individual LCOs, unless otherwise stated in the SR.

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

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

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

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

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

Exceptions to this Specification are stated in the individual Specifications.

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

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

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

(continued)

ABWR TS 3.0-3 Design Control Document/Tier 2

25A5675AU Revision 7 SR Applicability 3.0 3.0 SR APPLICABILITY (continued)

SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall not be made unless the LCOs Surveillances have been met within their specified Frequency. This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS.

ABWR TS 3.0-4 Design Control Document/Tier 2

25A5675AU Revision 7 SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 Shutdown Margin (SDM)

LCO 3.1.1 SDM shall be:

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

b. 0.28% k/k, with the highest worth control rod or rod pair determined by test.

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

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

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

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

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

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

(continued)

ABWR TS 3.1-1 Design Control Document/Tier 2

25A5675AU Revision 7 SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME D. (continued) AND D.3 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one standby gas treatment (SGT) subsystem to OPERABLE status.

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

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

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

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

AND (continued)

ABWR TS 3.1-2 Design Control Document/Tier 2

25A5675AU Revision 7 SDM 3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E. (continued) E.4 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one SGT subsystem to OPERABLE status.

AND E.5 Initiate action to restore 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one isolation valve and associated instrumentation to OPERABLE status in each required secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.1.1 Verify SDM is: Prior to each in vessel fuel

a. 0.38% k/k with the highest worth control rod movement during or control rod pair analytically determined; or fuel loading sequence

b. 0.28% k/k with the highest worth control rod or control rod pair determined by test. AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after criticality following fuel movement within the reactor pressure vessel or control rod replacement ABWR TS 3.1-3 Design Control Document/Tier 2

25A5675AU Revision 7 Reactivity Anomalies 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 The reactivity difference between the monitored core keff and the predicted core keff shall be within +/- 1% k/k.

APPLICABILITY: MODES 1 and 2.

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

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

ABWR TS 3.1-4 Design Control Document/Tier 2

25A5675AU Revision 7 Reactivity Anomalies 3.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify core reactivity difference between the Once within monitored core keff and the predicted core keff is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after within +/- 1% k/k. reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AND 1000 MW

d/t thereafter during operations in MODE 1 ABWR TS 3.1-5 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

Separate Condition entry is allowed for each control rod.

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

stuck. A stuck rod may be bypassed in the Rod Action and Position Information (RAPI) Subsystem in accordance with SR 3.3.5.1.7 if required to allow continued operation.

A.1 Disarm the associated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months control rod drive (CRD).

AND A.2 ------------NOTE--------------

Not applicable when less than or equal to the low power setpoint (LPSP) of the Rod Control and Information System (RCIS).

(continued)

ABWR TS 3.1-6 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod OPERABILITY 3.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) Perform SR 3.1.3.2 and 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.1.3.3 for each withdrawn OPERABLE control rod.

AND A.3 Perform SR 3.1.1.1. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Two or more withdrawn B.1 Disarm the associated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months control rods stuck. CRD.

AND B.2 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. One or more control rods ------------------NOTE----------------

inoperable for reasons 1. Inoperable control rods may other than Condition A or B. be bypassed in the RAPI Subsystem in accordance with SR 3.3.5.1.7, if required, to allow insertion of inoperable control rod and continued operation.

2. Inoperable control rods with failed motor drives can only be fully inserted by individual scram.

C.1 Fully insert inoperable 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months control rod.

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

(continued)

ABWR TS 3.1-7 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod OPERABILITY 3.1.3 ACTIONS (continued)

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

THERMAL POWER

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

control rods not in compliance with Ganged Withdrawal Sequence Restrictions (GWSR) and not separated by two or more OPERABLE control rods.

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

OR Nine or more control rods inoperable.

ABWR TS 3.1-8 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Determine the position of each control rod. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.1.3.2 -------------------------------NOTE------------------------------

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

Insert each fully withdrawn control rod two notches. 7 days SR 3.1.3.3 -------------------------------NOTE------------------------------

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

Insert each partially withdrawn control rod two 31 days notches.

SR 3.1.3.4 Verify each control rod scram time from fully In accordance withdrawn to 60% rod insertion position is with SR 3.1.4.1,

[ ] seconds. SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 SR 3.1.3.5 Verify each control rod does not go to the withdrawn Prior to declaring overtravel position. control rod OPERABLE after work on control rod or CRD System that could affect coupling AND Once the first time the control rod is withdrawn to full out position after the associated orificed fuel support has been moved ABWR TS 3.1-9 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4 a. No more than [8] OPERABLE control rods shall be slow, in accordance with Table 3.1.4-1; and

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

APPLICABILITY: MODES 1 and 2.

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

SURVEILLANCE REQUIREMENTS

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

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

SURVEILLANCE FREQUENCY SR 3.1.4.1 Verify each control rod scram time is within the limits Prior to exceeding of Table 3.1.4-1 with reactor steam dome pressure 40% RTP after fuel 6.55 MPaG. movement within the reactor pressure vessel AND (continued)

ABWR TS 3.1-10 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.4.1 (continued) Prior to exceeding 40% RTP after each reactor shutdown 120 days SR 3.1.4.2 Verify, for a representative sample, each tested 120 days control rod scram time is within the limits of cumulative Table 3.1.4-1 with reactor steam dome pressure operation in 6.55 MPaG. MODE 1 SR 3.1.4.3 Verify each affected control rod scram time is within Prior to declaring the limits of Table 3.1.4-1. control rod OPERABLE after work on control rod or CRD System that could affect scram time SR 3.1.4.4 Verify each affected control rod scram time is within Prior to exceeding the limits of Table 3.1.4-1 with reactor steam dome 40% RTP after pressure 6.55 MPaG. work on control rod or CRD System that could affect scram time ABWR TS 3.1-11 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Scram Times 3.1.4 Table 3.1.4-1 Control Rod Scram Times

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

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

2. Enter applicable Conditions and Required Actions of LCO 3.1.3, Control Rod Operability, for control rods with scram times > [ ] seconds to 60% rod insertion position. These control rods are inoperable, in accordance with SR 3.1.3.4, and are not considered slow.

SCRAM TIMES(a)

(seconds)

ROD POSITION REACTOR STEAM REACTOR STEAM REACTOR STEAM PERCENT DOME PRESSURE(b) DOME PRESSURE(b) DOME PRESSURE(b)

INSERTION 0 MPaG 6.55 MPaG 7.24 MPaG

(%)

10 (c) [ ] [ ]

40 (c) [ ] [ ]

60 [ ] [ ]

(a) Maximum scram time from fully withdrawn position, based on de-energization of scram pilot valve solenoids as time zero.

(b) For intermediate reactor steam dome pressures, the scram time criteria are determined by linear interpolation.

(c) For reactor steam dome pressure 6.55 MPaG, only 60% rod insertion position scram time limit applies.

ABWR TS 3.1-12 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Scram Accumulators 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Control Rod Scram Accumulators LCO 3.1.5 Each control rod scram accumulator shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One control rod scram A.1 Declare the associated 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months accumulator inoperable. control rod(s) inoperable.

B. Two or more control rod B.1 Declare the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months scram accumulators control rod(s) inoperable.

inoperable.

(continued)

ABWR TS 3.1-13 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)

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

associated Completion Not applicable if all Time of Required Action inoperable control rod A.1 or B.1 not met. scram accumulators are associated with fully inserted control rods.

Place the reactor mode Immediately switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.5.1 Verify each control rod scram accumulator pressure 7 days is 12.75 MPaG.

ABWR TS 3.1-14 Design Control Document/Tier 2

25A5675AU Revision 7 Rod Pattern Control 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Rod Pattern Control LCO 3.1.6 OPERABLE control rods shall comply with the requirements of the Ganged Withdrawal Sequence Restrictions (GWSR).

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

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

control rods not in Affected control rods may compliance with GWSR. be bypassed in the Rod Action and Position Information (RAPI)

Subsystem in accordance with SR 3.3.5.1.7.

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

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

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

control rods not in Affected control rods may compliance with GWSR. be bypassed in the RAPI Subsystem in accordance with SR 3.3.5.1.7 for insertion only.

Suspend withdrawal of Immediately control rods.

AND (continued)

ABWR TS 3.1-15 Design Control Document/Tier 2

25A5675AU Revision 7 Rod Pattern Control 3.1.6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the Shutdown position.

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

ABWR TS 3.1-16 Design Control Document/Tier 2

25A5675AU Revision 7 SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Concentration of boron in A.1 Restore concentration of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months solution not within limits. boron in solution to within limits. AND 10 days from discovery of failure to meet the LCO B. One SLC subsystem B.1 Restore SLC subsystem 7 days inoperable for reasons to OPERABLE status.

other than Condition A. AND 10 days from discovery of failure to meet the LCO C. Two SLC subsystems C.1 Restore one SLC 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable for reasons subsystem to OPERABLE other than Condition A. status.

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

ABWR TS 3.1-17 Design Control Document/Tier 2

25A5675AU Revision 7 SLC System 3.1.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium pentaborate 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months solution is 23.1 m3.

SR 3.1.7.2 Verify temperature of sodium pentaborate solution is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within the limits of Figure 3.1.7-1.

SR 3.1.7.3 Verify the concentration of boron in solution is within 31 days the limits of Figure 3.1.7-1.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after water or boron is added to solution AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after solution temperature is restored within the limits of Figure 3.1.7-1 SR 3.1.7.4 Verify each SLC subsystem manual, power 31 days operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.

SR 3.1.7.5 Verify each pump develops a flow rate 11.4 m3/h at 92 days a discharge pressure 8.43 MPaG.

(continued)

ABWR TS 3.1-18 Design Control Document/Tier 2

25A5675AU Revision 7 SLC System 3.1.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.1.7.6 Verify one complete cycle of each motor operated 92 days valve.

SR 3.1.7.7 Verify flow through one SLC subsystem from pump 18 months on a into reactor pressure vessel. STAGGERED TEST BASIS SR 3.1.7.8 Verify that simultaneous operation of both pumps 18 months develop a flow rate 22.7 m3/h at a pressure 8.43 MPaG.

ABWR TS 3.1-19 Design Control Document/Tier 2

25A5675AU Revision 7 SLC System 3.1.7 Figure 3.1.7-1 (Page 1 of 1)

Sodium Pentaborate Solution Temperature/Concentration Requirements ABWR TS 3.1-20 Design Control Document/Tier 2

25A5675AU Revision 7 APLHGR 3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR)

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

APPLICABILITY: THERMAL POWER 25% RTP.

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

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

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.1.1 Verify all APLHGRs are less than or equal to the Once within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter ABWR TS 3.2-1 Design Control Document/Tier 2

25A5675AU Revision 7 MCPR 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Minimum Critical Power Ratio (MCPR)

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

APPLICABILITY: THERMAL POWER 25% RTP.

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

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

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 Verify all MCPRs are greater than or equal to the Once within limits specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter ABWR TS 3.2-2 Design Control Document/Tier 2

25A5675AU Revision 7 LHGR (Non-GE Fuel) 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 Linear Heat Generation Rate (LHGR) (Non-GE Fuel)

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

APPLICABILITY: THERMAL POWER 25% RTP.

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

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

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.3.1 Verify all LHGRs are less than or equal to the limits Once within specified in the COLR. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter ABWR TS 3.2-3 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Safety System Logic and Control (SSLC) Sensor Instrumentation LCO 3.3.1.1 The SSLC instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Place SENSOR 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months one required SENSOR CHANNEL in trip.

CHANNEL inoperable.

OR A.2.1.1 -------------NOTE-------------

Applies only to Functions 3 through 33.

Place affected division in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months division of sensors bypass.

OR A.2.1.2 -------------NOTE-------------

Applies only to Functions 1 & 2.

Place channel in bypass 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months at Neutron Monitoring System.

AND (continued)

ABWR TS 3.3-1 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2.1 Restore required channel 30 days to OPERABLE status.

OR A.2.2.2 ------------NOTE--------------

1. Remove division of sensors bypass or NMS channel bypass after placing channel in trip.

2. Division of sensor bypass or NMS bypass is allowed for

[6] hours for restoring channel to OPERABLE status.

3. SENSOR CHANNEL(s) may be considered to remain in a tripped condition when a division containing tripped channel(s) is placed in division of sensors bypass due to subsequent entries into this condition.

Place channel in trip. 30 days (continued)

ABWR TS 3.3-2 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with B.1 Place one channel in trip. 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months two required SENSOR CHANNELS inoperable. AND B.2.1 -------------NOTE-------------

Applies only to Functions 3 through 33.

Place the other affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months division in division of sensors bypass.

OR B.2.2 -------------NOTE-------------

Applies only to Functions 1 & 2.

Place the other affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months channel in bypass.

AND B.3 Restore at least one 30 days required channel to OPERABLE status.

C. One or more Functions with C.1 Place one channel in trip. Immediately three required SENSOR CHANNELS inoperable. AND C.2 Restore at least one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months required channel to OPERABLE status.

(continued)

ABWR TS 3.3-3 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more Functions with D.1 Place one channel in trip. Immediately four required SENSOR CHANNELS inoperable. AND D.2 Restore at least one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months required channel to OPERABLE status.

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

F. As required by Required F.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Action E.1 and referenced POWER to below the in Table 3.3.1.1-1. level listed in Table 3.3.1.1-1 for the Function.

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

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

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

J. As required by Required J.1 Initiate action to place the Immediately Action E.1 and referenced reactor power/flow in Table 3.3.1.1-1. relationship outside of the region of applicability shown in Figure 3.3.1.1-1.

(continued)

ABWR TS 3.3-4 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K. As required by Required K.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action E.1 and referenced penetration flow path(s).

in Table 3.3.1.1-1.

L. As required by Required L.1 Isolate the affected Immediately Action E.1 and referenced penetration flow path(s).

in Table 3.3.1.1-1.

OR L.2.1 Suspend CORE Immediately ALTERATIONS.

AND L.2.2 -------------NOTE-------------

Applies only to Function 24.

Suspend movement of Immediately irradiated fuel assemblies in the containment.

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

M. As required by Required --------------------NOTE-------------------

Action E.1 and referenced Only applicable if RCIC and/or in Table 3.3.1.1-1. HPCF pump suction is not aligned to the suppression pool.

M.1 Align RCIC and HPCF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from suction to the suppression discovery of loss of pool. transfer capability (continued)

ABWR TS 3.3-5 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME N. As required by Required N.1 Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Action E.1 and referenced feature(s) inoperable.

in Table 3.3.1.1-1.

O. Required Action and O.1 Declare supported Immediately associated Completion feature(s) inoperable.

Time of Condition M.1 not met.

P. As required by Required P.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action E.1 and referenced in Table 3.3.1.1-1. AND P.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Q. As required by Required Q.1 Isolate the associated 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action E.1 and referenced penetration flow path(s) in Table 3.3.1.1-1.

OR Q.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Q.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months R. Required Action and R.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 K.1 not AND met.

R.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ABWR TS 3.3-6 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.1-1 to determine which SRs apply for each SSLC Sensor Instrumentation Function.

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

Only required to be met with THERMAL POWER 25% RTP.

Verify the absolute difference between the average [7] days power range monitor (APRM) channels and the calculated power is 2% RTP.

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

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

Perform DIVISION FUNCTIONAL TEST. [7] days SR 3.3.1.1.4 Perform DIVISION FUNCTIONAL TEST. [32] days SR 3.3.1.1.5 Perform DIVISION FUNCTIONAL TEST. [92] days SR 3.3.1.1.6 Perform CHANNEL FUNCTIONAL TEST. [92] days (continued)

ABWR TS 3.3-7 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.7 Calibrate the local power range monitors. 1000 MW*d/t average core exposure SR 3.3.1.1.8 ------------------------------NOTE------------------------------

1. Required to be met with THERMAL POWER 5% RTP prior to entry into MODE 1 from MODE 2.

2. Required to be met prior to entry into MODE 2 from MODE 1.

Verify the SRNM and APRM channels overlap within [7] days at least 1/2 decade.

SR 3.3.1.1.9 -------------------------------NOTE------------------------------

Radiation and Neutron detectors are excluded.

Perform COMPREHENSIVE FUNCTIONAL TEST. 18 months SR 3.3.1.1.10 ------------------------------NOTES-----------------------------

1. Neutron detectors are excluded.

2. SENSOR CHANNEL CALIBRATION shall include calibration of all parameters used to calculate setpoints (e.g., recirculation flow for TPM setpoint) and all parameters used for trip function bypasses (e.g., Turbine first stage pressure for TSV closure bypass).

Perform SENSOR CHANNEL CALIBRATION. 18 months (continued)

ABWR TS 3.3-8 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.11 Perform CHANNEL CALIBRATION. 18 months SR 3.3.1.1.12 -------------------------------NOTE------------------------------

Neutron detectors are excluded.

Verify RPS RESPONSE TIME is within limits. 18 months SR 3.3.1.1.13 Verify ECCS RESPONSE TIME is within limits. 18 months SR 3.3.1.1.14 -------------------------------NOTE------------------------------

Neutron detectors are excluded.

Verify ISOLATION RESPONSE TIME is within limits. 18 months ABWR TS 3.3-9 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 1 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE

1. Startup Range Neutron Monitors 1a. SRNM Neutron Flux 2 4 H SR 3.3.1.1.1 [ ]% RTP

- High SR 3.3.1.1.3 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.10 (a) 5 4 I SR 3.3.1.1.1 [ ]% RTP SR 3.3.1.1.4 SR 3.3.1.1.9 SR 3.3.1.1.10 1b. SRNM Neutron Flux 2(b) 4 H SR 3.3.1.1.1 [ ]

- Short Period SR 3.3.1.1.3 Seconds SR 3.3.1.1.8 (a) (b) 5 4 I SR 3.3.1.1.1 [ ]

SR 3.3.1.1.4 Seconds SR 3.3.1.1.9 SR 3.3.1.1.10 1c. SRNM ATWS 1,2 4 H SR 3.3.1.1.5 [ ] RTP for Permissive SR 3.3.1.1.9 [ ] min 1d. SRNM - Inop 1,2 4 H SR 3.3.1.1.3 NA (a) 5 4 I SR 3.3.1.1.4 SR 3.3.1.1.9

2. Average Power Range Monitors 2a. APRM Neutron Flux 2 4 H SR 3.3.1.1.1 [ ]% RTP

- High, Setdown SR 3.3.1.1.3 SR 3.3.1.1.7 SR 3.3.1.1.8 2b. APRM Simulated 1 4 G SR 3.3.1.1.1 [W + ]% RTP Thermal Power - SR 3.3.1.1.2 and [ ]% RTP High, Flow Biased SR 3.3.1.1.5 SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.12 ABWR TS 3.3-10 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 2 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE 2c. APRM Fixed 1 4 G SR 3.3.1.1.1 [ ]% RTP Neutron Flux - High SR 3.3.1.1.2 SR 3.3.1.1.5 SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.12 2d. APRM - Inop 1,2 4 H SR 3.3.1.1.5 NA SR 3.3.1.1.7 2e. Rapid Core Flow [80]% RTP 4 F SR 3.3.1.1.1 [ ]%/s Decrease SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.12 2f. Oscillation Power Per Figure 4 J SR 3.3.1.1.1 See Range Monitor 3.3.1.1-1 SR 3.3.1.1.5 footnote SR 3.3.1.1.9 (c)

SR 3.3.1.1.10 SR 3.3.1.1.12 2g. APRM ATWS ADS 1,2 4 H SR 3.3.1.1.5 [ ] RTP Permissive SR 3.3.1.1.9 for

[ ] min

3. Reactor Vessel Steam Dome Pressure - High 3a. RPS Trip Initiation 1,2 4 H SR 3.3.1.1.1 [ ]

SR 3.3.1.1.5 MPaG SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.12 3b. Isolation Initiation 1,2,3 4 K SR 3.3.1.1.1 [ ]

SR 3.3.1.1.5 MPaG SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 3c. SLCS and FWRB 1,2 4 G SR 3.3.1.1.1 [ ]

Initiation SR 3.3.1.1.6 MPaG SR 3.3.1.1.11 ABWR TS 3.3-11 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 3 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE

4. Reactor Steam Dome 1,2,3 4 N SR 3.3.1.1.1 [ ] MPaG Pressure - Low (Injection SR 3.3.1.1.5 Permissive) SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13

5. Reactor Vessel Water 1,2,3 4 N SR 3.3.1.1.1 [ ] cm Level - High, Level 8 4(e),5(e) SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

6. Reactor Vessel Water Level - Low, Level 3 6a. RPS Trip Initiation 1,2 4 H SR 3.3.1.1.1 [ ] cm SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.12 6b. Isolation Initiation 1,2,3 4 K SR 3.3.1.1.1 [ ] cm SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 (f) 4 L SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14

7. Reactor Vessel Water Level - Low, Level 2 7a. ESF Initiation 1,2,3 4 N SR 3.3.1.1.1 [ ] cm SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 ABWR TS 3.3-12 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 4 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE 7b. Isolation Initiation 1,2,3 4 K SR 3.3.1.1.1 [ ] cm SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 (f) 4 L SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 7c. SLCS and FWRB 1,2 4 G SR 3.3.1.1.1 [ ] cm Initiation SR 3.3.1.1.6 SR 3.3.1.1.11

8. Reactor Vessel Water Level - Low, Level 1.5 8a. ESF Initiation 1,2,3 4 N SR 3.3.1.1.1 [ ] cm 4(e),5(e) SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 8b. Isolation Initiation 1,2,3 4 Q SR 3.3.1.1.1 [ ] cm SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 8c. ATWS ADS Inhibit 1,2 4 H SR 3.3.1.1.1 [ ] cm SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 ABWR TS 3.3-13 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 5 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE

9. Reactor Vessel Water Level - Low, Level 1 9a. ADS A, CAMS A, 1,2,3 4 N SR 3.3.1.1.1 [ ] cm LPFL A & LPFL C 4(e),5(e) SR 3.3.1.1.5 Initiation SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 9b. ADS B, Diesel 1,2,3 4 N SR 3.3.1.1.1 [ ] cm Generator, RCW, 4(e),5(e) SR 3.3.1.1.5 CAMS B, & LPFL B SR 3.3.1.1.9 Initiation SR 3.3.1.1.10 SR 3.3.1.1.13 9c. Isolation Initiation 1,2,3 4 Q SR 3.3.1.1.1 [ ] cm SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14

10. Main Steam Isolation Valve 1 4 G SR 3.3.1.1.5 [ ]%

- Closure SR 3.3.1.1.9 closed SR 3.3.1.1.10 SR 3.3.1.1.12

11. Drywell Pressure - High 11a. RPS Initiation 1,2 4 H SR 3.3.1.1.1 [ ] MPaG SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.12 11b. ESF Initiation 1,2,3 4 P SR 3.3.1.1.1 [ ] MPaG SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.13 11c. Isolation Initiation 1,2,3 4 Q SR 3.3.1.1.1 [ ] MPaG SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 ABWR TS 3.3-14 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 6 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE

12. CRD Water Header 1,2 4 H SR 3.3.1.1.1 [ ] MPaG Charging Pressure - Low SR 3.3.1.1.5 5(a) 4 I SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

13. Turbine Stop Valve - [40]% RTP 4 F SR 3.3.1.1.5 Closure SR 3.3.1.1.9 [ ]%

SR 3.3.1.1.10 closed SR 3.3.1.1.12

14. Turbine Control Valve Fast [40]% RTP 4 F SR 3.3.1.1.1 [ ] MPaG Closure, Trip Oil Pressure SR 3.3.1.1.5 oil

- Low SR 3.3.1.1.9 pressure SR 3.3.1.1.10 SR 3.3.1.1.12

15. Main Steam Tunnel Radiation - High 15a. RPS Trip Initiation 1,2 4 H SR 3.3.1.1.5 [ ] gray SR 3.3.1.1.9 SR 3.3.1.1.10 15b. Isolation Initiation 1,2,3 4 Q SR 3.3.1.1.5 [ ] gray SR 3.3.1.1.9 SR 3.3.1.1.10

16. Suppression Pool Temperature - High 16a. RPS Initiation 1,2 4 H SR 3.3.1.1.1 [ ] °C SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.12 16b. ESF Initiation 1,2,3 4 N SR 3.3.1.1.1 [ ] °C SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 ABWR TS 3.3-15 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 7 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE

17. Condensate Storage Tank 1,2,3 4 M SR 3.3.1.1.1 [ ] cm Level - Low 4(e),5(e) SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

18. Suppression Pool Water 1,2,3 4 M SR 3.3.1.1.1 [ ] cm Level - High 4(e),5(e) SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

19. Main Steam Line Pressure 1 4 G SR 3.3.1.1.1 [ ] MPaG

- Low SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

20. Main Steam Line Flow -- 1,2,3 4 per MSL Q SR 3.3.1.1.1 kg/hr High SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14

21. Condenser Vacuum - Low 1,2(d),3(d) 4 Q SR 3.3.1.1.1 [ ] MPaG SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

22. Main Steam Tunnel 1,2,3 4 Q SR 3.3.1.1.1 [ ] °C Temperature - High SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

23. Main Turbine Area 1,2,3 4 Q SR 3.3.1.1.1 [ ] °C Temperature - High SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 24a. Reactor Building Area 1,2,3 4 K SR 3.3.1.1.1 [ ] gray Exhaust Air Radiation - SR 3.3.1.1.5 High (f), (g) 4 L SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14 ABWR TS 3.3-16 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 8 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE 24b. Fuel Handling Area 1,2,3 4 K SR 3.3.1.1.1 [ ] gray Exhaust Air Radiation - SR 3.3.1.1.5 High (f),(g) 4 L SR 3.3.1.1.1 SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 SR 3.3.1.1.14

25. RCIC Steam Line Flow - 1,2,3 4 K SR 3.3.1.1.1 kg/hr High SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

26. RCIC Steam Supply Line 1,2,3 4 K SR 3.3.1.1.1 [ ] MPaG Pressure - Low SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

27. RCIC Equipment Area 1,2,3 4 K SR 3.3.1.1.1 [ ] °C Temperature - High SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

28. RHR Area Temperature - 2,3 4 each K SR 3.3.1.1.1 [ ] °C High RHR area SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10

29. CUW Differential Flow - 1,2,3 4 K SR 3.3.1.1.1 [ ] Liters/min High SR 3.3.1.1.5 for < = [ ]

SR 3.3.1.1.9 Seconds SR 3.3.1.1.10

30. CUW Regenerative Heat 1,2,3 4 K SR 3.3.1.1.1 [ ] °C Exchanger Area SR 3.3.1.1.5 Temperature - High SR 3.3.1.1.9 SR 3.3.1.1.10

31. CUW non-regenerative 1,2,3 4 K SR 3.3.1.1.1 [ ] °C Heat Exchanger Area SR 3.3.1.1.5 Temperature - High SR 3.3.1.1.9 SR 3.3.1.1.10 ABWR TS 3.3-17 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Table 3.3.1.1-1 (Page 9 of 9)

SSLC Sensor Instrumentation APPLICABLE CONDITIONS MODES OR REFERENCED OTHER FROM SPECIFIED REQUIRED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS ACTIONS REQUIREMENTS VALUE

32. CUW Equipment Area 1,2,3 4 K SR 3.3.1.1.1 [ ] °C Temperature - High SR 3.3.1.1.5 SR 3.3.1.1.9 SR 3.3.1.1.10 4 each

33. RCW/RSW Heat (h) RCW/RSW K SR 3.3.1.1.1 [ ]m Exchanger Room Water HX Room SR 3.3.1.1.5 Level - High SR 3.3.1.1.9 SR 3.3.1.1.10 (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(b) Trip automatically bypassed within each SRNM and not required to be OPERABLE at reactor power levels [0.0001]% RTP.

(c) 1. Neutron flux oscillations within any OPRM cell have a period between [1.15] seconds and

[3.35] seconds that persists for [10] cycles with a peak to peak amplitude that is [10]% of point or greater.

2. Neutron flux oscillations within any OPRM cell that have a period between [0.31] and

[2.2] seconds become larger than [30]% of point within [3] periods or oscillations with the specified period range that are greater than [10%] of point grow by [30]% of point within

[3] cycles.

(d) With any Turbine Stop Valve not fully closed.

(e) When associated features are required to be operable.

(f) During CORE ALTERATIONS or operations with a potential for draining the reactor vessel.

(g) During movement of irradiated fuel assemblies in the secondary containment.

(h) When RSW pumps are required to be OPERABLE or in operation.

ABWR TS 3.3-18 Design Control Document/Tier 2

25A5675AU Revision 7 SSLC Sensor Instrumentation 3.3.1.1 Figure 3.3.1.1-1 (Page 1 of 1)

Oscillation Power Range Function Conditions of Operability ABWR TS 3.3-19 Design Control Document/Tier 2

25A5675AU Revision 7 RPS and MSIV Actuation 3.3.1.2 3.3 INSTRUMENTATION 3.3.1.2 Reactor Protection System (RPS) and Main Steam Isolation Valve (MSIV) Actuation LCO 3.3.1.2 The RPS and MSIV Actuation Functions in Table 3.3.1.2-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.2-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with --------------------NOTE-------------------

one channel inoperable. Only applicable to Functions 1a, 2a, and 5.

A.1 Place affected division in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months trip.

OR A.2.1 Place affected division in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months TLU logic output bypass.

AND A.2.2.1 Restore required 30 days channel(s) to OPERABLE status.

OR A.2.2.2 Place affected division in 30 days trip.

(continued)

ABWR TS 3.3-20 Design Control Document/Tier 2

25A5675AU Revision 7 RPS and MSIV Actuation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with --------------------NOTE-------------------

two channels inoperable. Only applicable to Functions 1a, 2a, and 5.

B.1 Place one affected 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months division in trip.

AND B.2 Place the other affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months division in TLU logic output bypass.

AND B.3 Restore at least one 30 days inoperable channel to OPERABLE status.

C. One or more Functions with --------------------NOTE-------------------

three channels inoperable. Only applicable to Functions 1a, 2a, and 5.

C.1 Place one affected Immediately division in trip.

AND C.2 Restore at least one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months inoperable channel to OPERABLE status.

(continued)

ABWR TS 3.3-21 Design Control Document/Tier 2

25A5675AU Revision 7 RPS and MSIV Actuation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more Functions with --------------------NOTE-------------------

four channels inoperable. Only applicable to Functions 1a, 2a, and 5.

D.1 Place one affected Immediately division in trip.

AND D.2 Restore at least one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable channel to OPERABLE status.

E. One or more Functions with --------------------NOTE-------------------

one OUTPUT CHANNEL Only applicable to Functions 1b and inoperable. 2b.

E.1 Place inoperable channel 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months in trip.

F. One or more Functions with --------------------NOTE-------------------

two OUTPUT CHANNELs Only applicable to Functions 1b and inoperable. 2b.

F.1 Place one inoperable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channel in trip.

AND F.2 Restore at least one 7 days inoperable channel to OPERABLE status.

(continued)

ABWR TS 3.3-22 Design Control Document/Tier 2

25A5675AU Revision 7 RPS and MSIV Actuation 3.3.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. One or more Functions with --------------------NOTE-------------------

three or more OUTPUT Only applicable to Functions 1b and CHANNELs inoperable. 2b.

G.1 Restore at least two 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channels to OPERABLE status.

H. One or more Reactor Mode H.1 Restore required channel 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Switch-Shutdown Position to OPERABLE status.

channels inoperable.

I. One RPS manual scram I.1 Place affected division in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months channel inoperable. trip.

AND I.2 Restore required channel 30 days to OPERABLE status.

J. Required Action and --------------------NOTE-------------------

associated Completion Only applicable to Functions 1, 3 Time not met for and 4.

Conditions A, B, C, D, E, F, ------------------------------------------------

G, H, or I in MODE 1 or 2.

J.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months K. Required Action and --------------------NOTE-------------------

associated Completion Only applicable to Functions 1, 3 Time not met for and 4.

Conditions A, B, C, D, E, F, ------------------------------------------------

G, H, or I in MODE 5 with any control rod withdrawn K.1 Initiate action to insert all Immediately in a core cell containing at insertable control rods in least one fuel assembly. core cells containing one or more fuel assemblies.

(continued)

ABWR TS 3.3-23 Design Control Document/Tier 2

25A5675AU Revision 7 RPS and MSIV Actuation 3.3.1.2 ACTIONS (continued)

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

associated Completion Only applicable to Functions 2 and Time not met for 5.

Conditions A, B, C, D, E, F ------------------------------------------------

or G.

L.1 Isolate the associated 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months penetration flow path(s).

OR L.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND L.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.2-1 to determine which SRs apply for each RPS and MSIV Actuation Function.

SURVEILLANCE FREQUENCY SR 3.3.1.2.1 Perform CHANNEL FUNCTIONAL TEST. [7] days SR 3.3.1.2.2 Perform DIVISION FUNCTIONAL TEST. [92] days SR 3.3.1.2.3 Perform CHANNEL FUNCTIONAL TEST. [92] days SR 3.3.1.2.4 Perform COMPREHENSIVE FUNCTIONAL TEST. 18 months SR 3.3.1.2.5 Perform OUTPUT CHANNEL FUNCTIONAL TEST. 18 months (continued)

ABWR TS 3.3-24 Design Control Document/Tier 2

25A5675AU Revision 7 RPS and MSIV Actuation 3.3.1.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.2.6 Verify RPS RESPONSE TIME is within limits. 18 months SR 3.3.1.2.7 Verify ISOLATION RESPONSE TIME is within limits. 18 months ABWR TS 3.3-25 Design Control Document/Tier 2

25A5675AU Revision 7 RPS and MSIV Actuation 3.3.1.2 Table 3.3.1.2-1 (Page 1 of 1)

RPS and MSIV Actuation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE FUNCTION CONDITIONS CHANNELS REQUIREMENTS

1. RPS Actuation

a. Logic Channels 1, 2, 5(a) 4 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.6

b. Output Channels 1, 2, 5(a) 4 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.6

2. MSIVs and MSL Drain Valves Actuation

a. Logic Channels 1, 2, 3 4 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.7

b. Output Channels 1, 2, 3 4 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7

3. Manual RPS Scram 1, 2, 5(a) 2 SR 3.3.1.2.1

4. Reactor Mode Switch-Shutdown 1, 2, 5(a) 2 SR 3.3.1.2.4 Position

5. Manual MSIV Actuation 1, 2, 3 4 SR 3.3.1.2.3 SR 3.3.1.2.4 (a) With any control rod withdrawn in a core cell containing at least one fuel assembly.

ABWR TS 3.3-26 Design Control Document/Tier 2

25A5675AU Revision 7 SLC and FWRB Actuation 3.3.1.3 3.3 INSTRUMENTATION 3.3.1.3 Standby Liquid Control (SLC) and Feedwater Runback (FWRB) Actuation LCO 3.3.1.3 The SLC and FWRB Actuation Functions in Table 3.3.1.3-1 shall be OPERABLE.

APPLICABILITY: MODES 1 AND 2.

ACTIONS

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

Separate condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with --------------------NOTE-------------------

one LOGIC CHANNEL Only applicable to Functions 1.a, inoperable. 2.a, and 3.

OR A.1 Place affected division in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months One division with one or ATWS logic output two manual ARI channels bypass.

inoperable.

AND A.2 Restore channel to 30 days OPERABLE status.

B. One or more Functions with --------------------NOTE-------------------

two LOGIC CHANNELS Only applicable to Functions 1.a, inoperable. 2.a, and 3.

OR B.1 Place one affected 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Two divisions with one or division in ATWS logic more manual ARI channels output bypass.

inoperable.

AND B.2 Restore the bypassed 7 days inoperable division to OPERABLE status.

(continued)

ABWR TS 3.3-27 Design Control Document/Tier 2

25A5675AU Revision 7 SLC and FWRB Actuation 3.3.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions with --------------------NOTE-------------------

one OUTPUT CHANNEL Only applicable to Functions 1.b inoperable. and 2.b.

C.1 Restore channel to 30 days OPERABLE status.

D. One or more Functions with --------------------NOTE-------------------

two OUTPUT CHANNELs Only applicable to Functions 1.b inoperable. and 2.b.

D.1 Restore at least one 7 days inoperable channel to OPERABLE status.

E. Required Action and E.1 Declare SLC System 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion inoperable.

Time not met for Conditions A, B, C, or D.

OR One or more Functions with three or more LOGIC CHANNELS or OUTPUT CHANNELS inoperable.

OR Three or more divisions with one or more manual ARI channels inoperable.

ABWR TS 3.3-28 Design Control Document/Tier 2

25A5675AU Revision 7 SLC and FWRB Actuation 3.3.1.3 SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.3-1 to determine which SRs apply for each Function.

SURVEILLANCE FREQUENCY SR 3.3.1.3.1 Perform DIVISION FUNCTIONAL TEST. [92] days SR 3.3.1.3.2 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months SR 3.3.1.3.3 Perform OUTPUT CHANNEL FUNCTIONAL TEST. 18 months ABWR TS 3.3-29 Design Control Document/Tier 2

25A5675AU Revision 7 SLC and FWRB Actuation 3.3.1.3 Table 3.3.1.3-1 (Page 1 of 1)

SLC and FWRB Actuation REQUIRED SURVEILLANCE FUNCTION CHANNELS REQUIREMENTS

1. SLC Actuation

a. Logic Channels 4 SR 3.3.1.3.1 SR 3.3.1.3.2

b. Output Channels 4 SR 3.3.1.3.2 SR 3.3.1.3.3

2. FWRB Actuation

a. Logic Channels 4 SR 3.3.1.3.1 SR 3.3.1.3.2

b. Output Channels 4 SR 3.3.1.3.2 SR 3.3.1.3.3

3. Manual ATWS-ARI/SLCS Initiation 2/division SR 3.3.1.3.1 SR 3.3.1.3.2 ABWR TS 3.3-30 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 3.3 INSTRUMENTATION 3.3.1.4 ESF Actuation Instrumentation LCO 3.3.1.4 The ESF Actuation Instrumentation for each Function in Table 3.3.1.4-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.1.4-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with A.1 Enter the Conditions Immediately one or more channels referenced in inoperable. Table 3.3.1.4-1.

B. One or more Functions with B.1 Place associated channel 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one LOGIC CHANNEL in bypass.

inoperable.

AND OR B.2.1 Restore channel to 30 days One or more Functions with OPERABLE status.

one manual initiation channel inoperable. OR B.2.2 Verify redundant 30 days feature(s) are OPERABLE.

(continued)

ABWR TS 3.3-31 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more Functions with C.1 Restore at least one 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one SENSOR CHANNEL required channel to inoperable. OPERABLE status.

OR One or more Functions with two LOGIC CHANNELS or two manual initiation channels inoperable.

D. One or more Functions with D.1 Restore ESF actuation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one or more OUTPUT capability for the affected CHANNELs inoperable. devices.

OR OR HPCF C manual initiation D.2 -------------NOTE-------------

channel inoperable. This Action applies only to Functions 10.b, 12.b, 13.b, and 14.b.

Actuate associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months device(s).

E. One or more Functions with E.1 Restore inoperable 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months one inoperable SENSOR channel.

CHANNEL.

OR E.2 Declare associated 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months device(s) inoperable.

F. One or more Functions with F.1 Restore at least one 7 days two manual initiation channel to OPERABLE channels inoperable. status.

(continued)

ABWR TS 3.3-32 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME G. Required Action and G.1 Declare supported 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion feature(s) inoperable.

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

H. One OUPUT CHANNEL H.1 Restore channel(s) to 3 days if only one inoperable on one or more OPERABLE status. high pressure ADS valves. ECCS subsystem is OPERABLE OR AND One or more ADS LOGIC CHANNELS inoperable in 7 days if two or one ADS division. more high pressure ECCS OR subsystems are OPERABLE One or more ADS manual initiation channels inoperable in one ADS division.

OR One or more ATWS manual ADS inhibit channels inoperable in one ADS division.

OR Five required ADS SENSOR CHANNELS inoperable in one ADS division.

(continued)

ABWR TS 3.3-33 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I. One or more SENSOR I.1 Declare associated ESF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CHANNELS inoperable. features inoperable.

OR One or more ADS valves with two OUTPUT CHANNELS inoperable.

OR One or more ADS LOGIC CHANNELS inoperable in two ADS divisions.

OR One or more ADS manual initiation channels inoperable in two ADS divisions.

OR One or more ATWS manual ADS inhibit channels inoperable in two ADS divisions.

OR Required Action and associated Completion Time of Condition H not met.

J. One or two required J.1 Restore required Prior to entering SENSOR CHANNELS channel(s) to OPERABLE MODE 2 following inoperable in one or more status. the next MODE 4 ADS divisions. entry (continued)

ABWR TS 3.3-34 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME K. Three required SENSOR K.1 Restore three required 7 days CHANNELS inoperable in channels to OPERABLE one or more ADS divisions. status.

L. Four required SENSOR L.1 Restore two required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months CHANNELS inoperable in channels to OPERABLE one or more ADS divisions. status.

M. ADS initiation capability not M.1 Declare ADS valves Immediately maintained in both ADS inoperable.

divisions.

OR Required Actions and associated Completion Times of Condition H, J, K, or L not met.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.1.4-1 to determine which SRs apply for each ESF Actuation Instrumentation Functions.

SURVEILLANCE FREQUENCY SR 3.3.1.4.1 Perform SENSOR CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.1.4.2 Perform OUTPUT CHANNEL FUNCTIONAL TEST. 18 months SR 3.3.1.4.3 Perform DIVISIONAL FUNCTIONAL TEST. [92] days (continued)

ABWR TS 3.3-35 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.4.4 Perform COMPREHENSIVE FUNCTIONAL TEST. 18 months SR 3.3.1.4.5 Perform ECCS RESPONSE TIME TEST. 18 months SR 3.3.1.4.6 Perform SENSOR CHANNEL CALIBRATION. 18 months SR 3.3.1.4.7 Perform Manual initiation CHANNEL FUNCTIONAL 18 months TEST.

ABWR TS 3.3-36 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 Table 3.3.1.4-1 (Page 1 of 7)

ESF Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

1. Low Pressure Core Flooder Actuation (a) 1.a LPFL Pump 1,2,3, 1 per pump C SR 3.3.1.4.1 [ ] MPaG (g) (g)

Discharge Pressure 4 ,5 SR 3.3.1.4.3

- High SR 3.3.1.4.4 SR 3.3.1.4.6 1.b LPFL Pump 1,2,3, 1 per pump(a) C SR 3.3.1.4.1 [ ] liters Discharge Flow - 4(g),5(g) SR 3.3.1.4.3 per min Low SR 3.3.1.4.4 SR 3.3.1.4.6 1.c LPFL System 1,2,3, 2 per B, C SR 3.3.1.4.3 NA Initiation 4(g),5(g) subsystem(b) SR 3.3.1.4.4 SR 3.3.1.4.5 1.d LPFL Device 1,2,3, 1 per D SR 3.3.1.4.2 NA Actuation 4(g),5(g) actuated SR 3.3.1.4.3 (c) device SR 3.3.1.4.4 SR 3.3.1.4.5 1.e LPFL Manual 1,2,3, 2 per B, F SR 3.3.1.4.3 NA Initiation 4(g),5(g) subsystem(d) SR 3.3.1.4.4 SR 3.3.1.4.7

2. High Pressure Core Flooder Actuation (a) 2.a HPCF Pump 1,2,3, 1 per pump C SR 3.3.1.4.1 [ ] MPaG (g) (g)

Discharge Pressure 4 ,5 SR 3.3.1.4.3

- High SR 3.3.1.4.4 SR 3.3.1.4.6 (a) 2.b HPCF Pump 1,2,3, 1 per pump C SR 3.3.1.4.1 [ ] liters (g) (g)

Discharge Flow - 4 ,5 SR 3.3.1.4.3 per min Low SR 3.3.1.4.4 SR 3.3.1.4.6 2.c HPCF Pump Suction 1,2,3, 1 per pump(a) C SR 3.3.1.4.1 [ ] MPaG Pressure - Low 4(g),5(g) SR 3.3.1.4.3 SR 3.3.1.4.4 SR 3.3.1.4.6 2.d HPCF System 1,2,3, 2 per B, C SR 3.3.1.4.3 NA (g) (g)

Initiation 4 ,5 subsystem(b) SR 3.3.1.4.4 SR 3.3.1.4.5 ABWR TS 3.3-37 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 Table 3.3.1.4-1 (Page 2 of 7)

ESF Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 2.e HPCF Device 1,2,3, 1 per D SR 3.3.1.4.2 NA Actuation 4(g),5(g) actuated SR 3.3.1.4.3 (c) device SR 3.3.1.4.4 SR 3.3.1.4.5 2.f HPCF B Manual 1,2,3, 2(d) B, F SR 3.3.1.4.3 NA Initiation 4(g),5(g) SR 3.3.1.4.4 SR 3.3.1.4.7 2.g HPCF C Manual 1,2,3, 1(d) D SR 3.3.1.4.3 NA (g) (g)

Initiation 4 ,5 SR 3.3.1.4.4 SR 3.3.1.4.7

3. Reactor Core Isolation Cooling System Actuation (e) (e) 3.a RCIC Pump 1,2 ,3 1(a) C SR 3.3.1.4.1 [ ] MPaG Discharge Pressure SR 3.3.1.4.3

- High SR 3.3.1.4.4 SR 3.3.1.4.6 3.b RCIC Pump 1,2(e),3(e) 1(a) C SR 3.3.1.4.1 [ ] liters Discharge Flow - SR 3.3.1.4.3 per min Low SR 3.3.1.4.4 SR 3.3.1.4.6 (e) (e) 3.c RCIC System 1,2 ,3 2(b) B, C SR 3.3.1.4.3 NA Initiation SR 3.3.1.4.4 SR 3.3.1.4.5 (e) (e) 3.d RCIC Device 1,2 ,3 1 per D SR 3.3.1.4.2 NA Actuation actuated SR 3.3.1.4.3 device(c) SR 3.3.1.4.4 SR 3.3.1.4.5 (e) (e) 3.e RCIC Manual 1,2 ,3 2(d) B, F SR 3.3.1.4.3 NA Initiation SR 3.3.1.4.4 SR 3.3.1.4.7 ABWR TS 3.3-38 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 Table 3.3.1.4-1 (Page 3 of 7)

ESF Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

4. Automatic Depressurization System 4.a ADS System 1,2,3, 2 per H, I SR 3.3.1.4.3 NA Initiation 4(f),5(f) subsystem(b) SR 3.3.1.4.4 4.b ADS Device 1,2,3, 2 per ADS H, I SR 3.3.1.4.2 NA Actuation 4(f),5(f) valve(c) SR 3.3.1.4.3 SR 3.3.1.4.4 SR 3.3.1.4.5 4.c ADS Manual 1,2,3, 2 per H, I SR 3.3.1.4.3 NA (f) (f)

Initiation 4 ,5 subsystem(d) SR 3.3.1.4.4 SR 3.3.1.4.7 4.d ADS Division I 1,2(f),3(f) 1 per each of H, J, K, SR 3.3.1.4.3 [ ] MPaG (a)

ECCS Pump 5 pumps L, M SR 3.3.1.4.4 Discharge Pressure SR 3.3.1.4.6

- High (permissive) 4.e ADS Division II 1,2(f),3(f) 1 per each of H, J, K, SR 3.3.1.4.3 [ ] MPaG (a)

ECCS Pump 5 pumps L, M SR 3.3.1.4.4 Discharge Pressure SR 3.3.1.4.6

- High (permissive) 4.f ATWS Manual ADS 1,2 2 per H, I SR 3.3.1.4.3 NA (d)

Inhibit subsystem SR 3.3.1.4.4 SR 3.3.1.4.7

5. Diesel-Generator Actuation 5.a Division I, II, & III 1,2,3, 1 per phase(a) C SR 3.3.1.4.1 [ ] V and Loss of Voltage - 4(h),5(h) SR 3.3.1.4.2 [ ] V for 6.9 kV SR 3.3.1.4.3 [ ] s and SR 3.3.1.4.4 [ ]s SR 3.3.1.4.5 SR 3.3.1.4.6 (a) 5.b Division I, II, & III 1,2,3, 1 per phase C SR 3.3.1.4.1 [ ] V and (h) (h)

Degraded Voltage - 4 ,5 SR 3.3.1.4.2 [ ] V for 6.9 kV SR 3.3.1.4.3 [ ] s and SR 3.3.1.4.4 [ ]s SR 3.3.1.4.5 SR 3.3.1.4.6 ABWR TS 3.3-39 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 Table 3.3.1.4-1 (Page 4 of 7)

ESF Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (b) 5.c DG System 1,2,3, 2 per DG B, C SR 3.3.1.4.3 NA Initiation 4(h),5(h) SR 3.3.1.4.4 SR 3.3.1.4.5 5.d DG Device 1,2,3, 1 per D SR 3.3.1.4.2 NA (h) (h)

Actuation 4 ,5 actuated SR 3.3.1.4.3 (c) device SR 3.3.1.4.4 (d) 5.e DG Manual 1,2,3, 2 per DG B, F SR 3.3.1.4.3 NA Initiation 4(h),5(h) SR 3.3.1.4.4 SR 3.3.1.4.7

6. Standby Gas Treatment System Actuation 6.a SGTS Initiation 1,2,3 1 per B, C SR 3.3.1.4.3 NA (i)(j) subsystem(b) SR 3.3.1.4.4 6.b SGTS Device 1,2,3 1 per D SR 3.3.1.4.2 NA Actuation (i)(j) actuated SR 3.3.1.4.3 device(c) SR 3.3.1.4.4

7. Reactor Building Cooling Water/Service Water Actuation 7.a RCW/RSW System 1,2,3, 2 per B, C SR 3.3.1.4.3 NA Initiation 4(g),5(g) subsystem(b) SR 3.3.1.4.4 7.b RCW/RSW Device 1,2,3, 1 per D SR 3.3.1.4.2 NA (g) (g)

Actuation 4 ,5 actuated SR 3.3.1.4.3 (c) device SR 3.3.1.4.4 7.c RCW/RSW Manual 1,2,3, 2 per B, F SR 3.3.1.4.3 NA (g) (g)

Initiation 4 ,5 subsystem(d) SR 3.3.1.4.4 SR 3.3.1.4.7 7.d Division I, II, & III 1,2,3, 1 per phase(a) C SR 3.3.1.4.1 [ ] V and Loss of Voltage - 4(h),5(h) SR 3.3.1.4.2 [ ] V for 6.9 kV SR 3.3.1.4.3 [ ] s and SR 3.3.1.4.4 [ ]s SR 3.3.1.4.5 SR 3.3.1.4.6 ABWR TS 3.3-40 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 Table 3.3.1.4-1 (Page 5 of 7)

ESF Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a) 7.e Division I, II, & III 1,2,3, 1 per phase C SR 3.3.1.4.1 [ ] V and Degraded Voltage - 4(h),5(h) SR 3.3.1.4.2 [ ] V for 6.9 kV SR 3.3.1.4.3 [ ] s and SR 3.3.1.4.4 [ ]s SR 3.3.1.4.5 SR 3.3.1.4.6

8. Containment Atmospheric Monitoring 8.a CAM System 1,2,3 2 per B, C SR 3.3.1.4.3 NA Initiation subsystem(b) SR 3.3.1.4.4 8.b CAM Device 1,2,3 1 per D SR 3.3.1.4.2 NA Actuation actuated SR 3.3.1.4.3 device(c) SR 3.3.1.4.4

9. Suppression Pool Cooling Actuation 9.a SPC System 1,2,3, 2 per B, C SR 3.3.1.4.3 NA Initiation 4(g),5(g) subsystem(b) SR 3.3.1.4.4 9.b SPC Device 1,2,3, 1 per D SR 3.3.1.4.2 NA (g) (g)

Actuation 4 ,5 actuated SR 3.3.1.4.3 device(c) SR 3.3.1.4.4 9.c SPC Manual 1,2,3, 2 per B, F SR 3.3.1.4.3 NA (g) (g)

Initiation 4 ,5 subsystem(d) SR 3.3.1.4.4 SR 3.3.1.4.7

10. Containment Isolation Valves Actuation 10.a CIV System 1,2,3 2 per B, C SR 3.3.1.4.3 NA (b)

Initiation (i)(j) division SR 3.3.1.4.4 10.b CIV Device 1,2,3 1 per D SR 3.3.1.4.2 NA Actuation (i)(j) actuated SR 3.3.1.4.3 device(c) SR 3.3.1.4.4 10.c Drywell Sump Drain 1,2,3 1(a) E SR 3.3.1.4.3 [ ] gray LCW Radiation - SR 3.3.1.4.4 High SR 3.3.1.4.6 ABWR TS 3.3-41 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 Table 3.3.1.4-1 (Page 6 of 7)

ESF Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE (a) 10.d Drywell Sump Drain 1,2,3 1 E SR 3.3.1.4.3 [ ] gray HCW Radiation - SR 3.3.1.4.4 High SR 3.3.1.4.6

11. CIV Divisional Manual 1,2,3 2 per B, C SR 3.3.1.4.3 NA (d)

Initiation (j) division SR 3.3.1.4.4 SR 3.3.1.4.7

12. Reactor Core Isolation Cooling Isolation Actuation 12.a RCIC System 1,2,3 2 per B, C SR 3.3.1.4.3 NA (b)

Isolation Initiation division SR 3.3.1.4.4 12.b RCIC Isolation 1,2,3 1 per D SR 3.3.1.4.2 NA Device Actuation actuated SR 3.3.1.4.3 device(c) SR 3.3.1.4.4 12.c RCIC Manual 1,2,3 2 per B, F SR 3.3.1.4.3 NA Isolation Initiation division(d) SR 3.3.1.4.4 SR 3.3.1.4.7 12.d RCIC Turbine 1,2,3 2 per I SR 3.3.1.4.1 Exhaust Diaphragm division(a) SR 3.3.1.4.3 [ ] MPaG Pressure - High SR 3.3.1.4.4 SR 3.3.1.4.6

13. Reactor Water Cleanup Isolation Actuation 13.a CUW System 1,2,3 2 per B, C SR 3.3.1.4.3 NA (b)

Isolation Initiation (i) division SR 3.3.1.4.4 13.b CUW Isolation 1,2,3 1 per D SR 3.3.1.4.2 NA Device Actuation (i) actuated SR 3.3.1.4.3 (c) device SR 3.3.1.4.4 13.c CUW Isolation on 1,2,3 1 per SLC E SR 3.3.1.4.4 NA (a)

SLC Initiation division ABWR TS 3.3-42 Design Control Document/Tier 2

25A5675AU Revision 7 ESF Actuation Instrumentation 3.3.1.4 Table 3.3.1.4-1 (Page 7 of 7)

ESF Actuation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED APPLICABLE SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE

14. Shutdown Cooling System Isolation Actuation 14.a SD Cooling System (i) 2 per B, C SR 3.3.1.4.3 NA 2,3, Isolation Initiation division(b) SR 3.3.1.4.4 14.b SD Cooling Isolation (i) 1 per D SR 3.3.1.4.2 NA 2,3, Device Actuation actuated SR 3.3.1.4.3 (c) device SR 3.3.1.4.4 (a) These are SENSOR CHANNEL Functions.

(b) These are LOGIC CHANNEL Functions.

(c) These are OUTPUT CHANNEL Functions.

(d) These are manual initiation channel Functions.

(e) With reactor pressure greater than 1.03 MPaG.

(f) With reactor pressure greater than 0.343 MPaG.

(g) When associated subsystems are required to be operable.

(h) When associated Diesel-Generator is required to be OPERABLE per LCO 3.8.2 AC Sources -

Shutdown.

(i) During CORE ALTERATIONS and operations with the potential for draining the reactor vessel.

(j) During movement of irradiated fuel assemblies in the secondary containment.

ABWR TS 3.3-43 Design Control Document/Tier 2

25A5675AU Revision 7 SRNM Instrumentation 3.3.2.1 3.3 INSTRUMENTATION 3.3.2.1 Startup Range Monitor (SRNM) Instrumentation LCO 3.3.2.1 The SRNM instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.2.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One required channel --------------------NOTE-------------------

inoperable in one or more LCO 3.0.4 is not applicable.

bypass groups. ------------------------------------------------

A.1 Place channel in bypass. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months OR A.2 Place channel in trip.

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

OR Four or more required channels inoperable.

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

MODE 3 or 4.

AND (continued)

ABWR TS 3.3-44 Design Control Document/Tier 2

25A5675AU Revision 7 SRNM Instrumentation 3.3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2 Place reactor mode switch 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months in the shutdown position.

D. One required SRNM D.1 Suspend CORE Immediately inoperable in MODE 5. ALTERATIONS except for control rod insertion.

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

And D.3 Initiate action to restore 7 days required SRNM to OPERABLE status.

E. Two required SRNMs E.1 Initiate action to restore one Immediately inoperable in MODE 5. required SRNM to OPERABLE status.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.2.1-1 to determine which SRs apply for each applicable MODE or other specified conditions.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

ABWR TS 3.3-45 Design Control Document/Tier 2

25A5675AU Revision 7 SRNM Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.2 ------------------------------NOTE----------------------------

1. Only required to be met during CORE ALTERATIONS.

2. Only part a. is required under the conditions specified in footnote (a) of Table 3.3.2.1-1.

3. One SRNM may be used to satisfy more than one of the following.

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

a. The fueled region; AND

b. The core quadrant where CORE Following a ALTERATIONS are being performed when the change in the associated SRNM is included in the fueled core quadrant region; and where CORE ALERATIONS are

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

SR 3.3.2.1.3 -------------------------------NOTE---------------------------

Not required to be met with four or less fuel assemblies adjacent to the SRNM and no other fuel assemblies in the associated core quadrant.

Verify count rate is 3.0 cps. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during CORE ALTERATIONS AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

ABWR TS 3.3-46 Design Control Document/Tier 2

25A5675AU Revision 7 SRNM Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.2.1.4 Perform CHANNEL FUNCTIONAL TEST. [7] days SR 3.3.2.1.5 Perform CHANNEL FUNCTIONAL TEST. [31] days SR 3.3.2.1.6 -------------------------------NOTE------------------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION. 18 months ABWR TS 3.3-47 Design Control Document/Tier 2

25A5675AU Revision 7 SRNM Instrumentation 3.3.2.1 Table 3.3.2.1-1 (page 1 of 1)

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

1. Startup Range Neutron Monitor 2 Group # 1 - 4 SR 3.3.2.1.1 Group # 2 - 3 SR 3.3.2.1.3 Group # 3 - 3 SR 3.3.2.1.5 SR 3.3.2.1.6 3,4 2 SR 3.3.2.1.1 SR 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.6 (a),(b) 5 2 SR 3.3.2.1.1 SR 3.3.2.1.2 SR 3.3.2.1.3 SR 3.3.2.1.4 SR 3.3.2.1.6 (a) Only one SRNM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRNM detector.

(b) Special movable detectors may be used in place of SRNMs if connected to normal SRNM circuits.

ABWR TS 3.3-48 Design Control Document/Tier 2

25A5675AU Revision 7 Essential Multiplexing System 3.3.3.1 3.3 INSTRUMENTATION 3.3.3.1 Essential Multiplexing System (EMS)

LCO 3.3.3.1 Four divisions of EMS data transmission shall be OPERABLE.

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

ACTIONS

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

Separate Condition entry is allowed for each division.

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

transmission segments LCO 3.0.4 is not applicable.

inoperable in one EMS ------------------------------------------------

division with data transmission maintained. A.1 Restore all data Prior to entering transmission segments to MODE 2 following OPERABLE status. next MODE 4 entry B. One or more data B.1 Restore all data [30] days transmission segments transmission segments in inoperable in two or more at least three EMS EMS divisions with data divisions to OPERABLE transmission maintained in status.

all divisions.

C. Required Actions and C.1 Verify data transmission 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion capability.

Times of Condition B not AND met.

AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter C.2 Initiate action in Immediately accordance with Specification 5.5.2.10.

(continued)

ABWR TS 3.3-49 Design Control Document/Tier 2

25A5675AU Revision 7 Essential Multiplexing System 3.3.3.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more EMS divisions --------------------NOTE-------------------

inoperable. LCO 3.0.4 is not applicable.

D.1 Declare affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Functions and supported Features inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.3.1.1 Verify the required data transmission path segments [92] days are OPERABLE.

SR 3.3.3.1.2 Perform a comprehensive network performance test. 18 months ABWR TS 3.3-50 Design Control Document/Tier 2

25A5675AU Revision 7 ATWS & EOC-RPT Instrumentation 3.3.4.1 3.3 INSTRUMENTATION 3.3.4.1 Anticipated Transient Without Scram (ATWS) and End-of-Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation LCO 3.3.4.1 The channels for each Function listed in Table 3.3.4.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.4.1-1.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions with -------------------NOTE--------------------

one inoperable channel. Applies only to Functions 1, 3, 5, 11, and 14 in Table 3.3.4.1-1.

A.1.1 Place channel(s) in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months bypass.

AND A.1.2.1 Restore channel(s) to 14 days OPERABLE status.

OR A.1.2.2 Place channel(s) in trip. 14 days OR A.2 Place channel(s) in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months (continued)

ABWR TS 3.3-51 Design Control Document/Tier 2

25A5675AU Revision 7 ATWS & EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more Functions with -------------------NOTE--------------------

two or more channels Applies only to Functions 1, 3, 5, inoperable. 11, and 14 in Table 3.3.4.1-1.

B.1 Restore two channels to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

C. One or more Functions with -------------------NOTE--------------------

one channel inoperable. Applies only to Functions 2, 4, and 9 in Table 3.3.4.1-1.

C.1.1 Place channel(s) in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months bypass.

AND C.1.2.1 Restore channel(s) to 30 days OPERABLE status.

OR C.1.2.2 Place channel(s) in trip. 30 days OR C.2 Place channel(s) in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months D. One or more Functions with -------------------NOTE--------------------

two channels inoperable. Applies only to Functions 2, 4, and 9 in Table 3.3.4.1-1.

D.1 Restore one inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months channel to OPERABLE status.

(continued)

ABWR TS 3.3-52 Design Control Document/Tier 2

25A5675AU Revision 7 ATWS & EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more Functions with -------------------NOTE--------------------

three or more channels Applies only to Functions 2, 4, inoperable. and 9 in Table 3.3.4.1-1.

E.1 Restore at least one [24] hours inoperable channel to OPERABLE status.

F. Required Action and -------------------NOTE--------------------

associated Completion Applies only to Function 4 in Time of Condition C, D, Table 3.3.4.1-1.

or E not met. ------------------------------------------------

F.1 Apply the MCPR limit for [2] hours inoperable EOC-RPT as specified in the COLR.

OR F.2 Reduce power to [2] hours 40% RTP.

G. One or more Functions with -------------------NOTE--------------------

one or more channels Applies only to Functions 6, 7, 8, inoperable. 10, 12, 13, 15, and 16 in Table 3.3.4.1-1.

G.1 Restore channels to [24] hours OPERABLE status.

(continued)

ABWR TS 3.3-53 Design Control Document/Tier 2

25A5675AU Revision 7 ATWS & EOC-RPT Instrumentation 3.3.4.1 ACTIONS (continued)

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

associated Completion Applies only to Functions Time not met. 6, 7, 8, and 16 in Table 3.3.4.1-1.

Declare affected Immediately Functions and supported Features inoperable.

OR H.2 --------------NOTE------------

Applies only to Function 1, 2, 3, 5, 9, 10, 12, 13, 14, and 15 in Table 3.3.4.1-1.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Be in MODE 3.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.4.1-1 to determine the applicability of the SRs to each RPT Function.

SURVEILLANCE FREQUENCY SR 3.3.4.1.1 Perform SENSOR CHANNEL CHECK. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.3.4.1.2 Perform CHANNEL FUNCTIONAL TEST. [92] days SR 3.3.4.1.3 Perform SENSOR CHANNEL CALIBRATION. 18 months SR 3.3.4.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months (continued)

ABWR TS 3.3-54 Design Control Document/Tier 2

25A5675AU Revision 7 ATWS & EOC-RPT Instrumentation 3.3.4.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.4.1.5 Verify the RPT SYSTEM RESPONSE TIME is within 18 months limits.

SR 3.3.4.1.6 Perform COMPREHENSIVE FUNCTIONAL TEST. 18 months SR 3.3.4.1.7 Perform CHANNEL FUNCTIONAL TEST. 7 days ABWR TS 3.3-55 Design Control Document/Tier 2

25A5675AU Revision 7 ATWS & EOC-RPT Instrumentation 3.3.4.1 Table 3.3.4.1-1 (page 1 of 2)

ATWS and EOC-RPT Instrumentation APPLICABLE MODES OR OTHER REQUIRED SPECIFIED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS CONDITIONS REQUIREMENTS VALUES

1. Feedwater Reactor Vessel Water 3 1,2 SR 3.3.4.1.1 [ ] cm Level - Low, Level 3 SR 3.3.4.1.2 SR 3.3.4.1.3 SR 3.3.4.1.4 SR 3.3.4.1.5

2. Reactor Water Vessel Level - 4 1,2 SR 3.3.4.1.1 [ ] cm Low, Level 2 SR 3.3.4.1.2 SR 3.3.4.1.3 SR 3.3.4.1.4 SR 3.3.4.1.5 SR 3.3.4.1.6

3. SB&PC Reactor Steam Dome 3 1,2 SR 3.3.4.1.1 [ ] MPaG Pressure - High SR 3.3.4.1.2 SR 3.3.4.1.3 SR 3.3.4.1.4 SR 3.3.4.1.5

4. EOC-RPT Initiation 4 40% RTP. SR 3.3.4.1.2 NA SR 3.3.4.1.5 SR 3.3.4.1.6

5. RPT Trip Initiation Function of the 3 1,2 SR 3.3.4.1.2 NA RFC SR 3.3.4.1.4

6. ASD Pump Trip Actuation 1 per ASD 1,2 SR 3.3.4.1.4 NA

7. ASD Pump Trip Timers 1 per ASD 1,2 SR 3.3.4.1.3 (a) footnote SR 3.3.4.1.4

8. ASD Pump Trip Load Interruption 1 per ASD 1,2 SR 3.3.4.1.4 NA

9. RPS Scram Follow Signal 4 1,2 SR 3.3.4.1.2 NA SR 3.3.4.1.4 SR 3.3.4.1.6

10. Manual ATWS-ARI/SLCS 2 1,2 SR 3.3.4.1.4 NA Initiation SR 3.3.4.1.7

11. ATWS-ARI Trip Initiation 3 1,2 SR 3.3.4.1.4 NA Function of the RFC

12. ATWS-FMCRD Initiation 2 1,2 SR 3.3.4.1.4 NA Function of the RCIS ABWR TS 3.3-56 Design Control Document/Tier 2

25A5675AU Revision 7 ATWS & EOC-RPT Instrumentation 3.3.4.1 Table 3.3.4.1-1 (page 2 of 2)

ATWS and EOC-RPT Instrumentation APPLICABLE MODES OR OTHER REQUIRED SPECIFIED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS CONDITIONS REQUIREMENTS VALUES

13. FMCRD Insertion Confirmatory 1 1,2 SR 3.3.4.1.4 Logic

14. ATWS-ARI Valve Actuation 3 1,2 SR 3.3.4.1.4 NA

15. FMCRD Emergency Insertion 1 per rod 1,2 SR 3.3.4.1.4 NA Invertor Control Logic

16. Recirculation Runback 1 per pump 1,2 SR 3.3.4.1.4 NA (a) [ ] seconds for RIPs [A, D, F, J, B, E, & H] and [ ] seconds for RIPs [C, G, & K].

ABWR TS 3.3-57 Design Control Document/Tier 2

25A5675AU Revision 7 Feedwater and Main Turbine Trip Instrumentation 3.3.4.2 3.3 INSTRUMENTATION 3.3.4.2 Feedwater and Main Turbine Trip Instrumentation LCO 3.3.4.2 Three channels of feedwater and main turbine trip instrumentation shall be OPERABLE.

APPLICABILITY: THERMAL POWER 25% RTP.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One feedwater and main A.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months turbine trip channel inoperable. OR A.2.1 Place channel in bypass. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months AND A.2.2.1 Restore channel to 14 days OPERABLE status.

OR A.2.2.2 Place channel in trip. 14 days B. Two or more feedwater and B.1 Restore two channels to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months main turbine trip channels OPERABLE status.

inoperable.

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

Time not met.

ABWR TS 3.3-58 Design Control Document/Tier 2

25A5675AU Revision 7 Feedwater and Main Turbine Trip Instrumentation 3.3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.4.2.1 Perform SENSOR CHANNEL CHECK. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.3.4.2.2 Perform CHANNEL FUNCTIONAL TEST. [92] days SR 3.3.4.2.3 Perform SENSOR CHANNEL CALIBRATION. The 18 months Allowable Value shall be [ ] inches.

SR 3.3.4.2.4 Perform LOGIC SYSTEM FUNCTIONAL TEST 18 months including [valve] actuation.

ABWR TS 3.3-59 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Block Instrumentation 3.3.5.1 3.3 INSTRUMENTATION 3.3.5.1 Control Rod Block Instrumentation LCO 3.3.5.1 The control rod block instrumentation for each Function in Table 3.3.5.1-1 shall be OPERABLE.

APPLICABILITY: According to Table 3.3.5.1-1.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Automated Thermal A.1 Restore channel to [72] hours Limit Motor (ATLM) channel OPERABLE status.

inoperable.

OR A.2 Verify the thermal limits 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months are met. AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter B. Two ATLM channels --------------------NOTE-------------------

inoperable. Removal of ATLM block under administrative control is permitted provided manual control of rod movement and thermal limits are verified by a second licensed operator.

B.1 Insert an ATLM block. Immediately AND B.2 Verify RCIS blocks control 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months rod movement by AND attempting to withdraw Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months one rod or one gang or thereafter rods.

(continued)

ABWR TS 3.3-60 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Block Instrumentation 3.3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One Rod Worth Minimizer C.1 Restore channel to [72] Hours (RWM) channel inoperable. OPERABLE status.

D. Two RWM channels D.1 Suspend control rod Immediately inoperable. movement, except by scram.

OR Required Actions and associated Completion Time of Condition C not met.

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

channels inoperable.

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

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.5.1-1 to determine which SRs apply for each Control Rod Block Function.

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 -------------------------------NOTE------------------------------

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

Perform CHANNEL FUNCTIONAL TEST. [92] days (continued)

ABWR TS 3.3-61 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Block Instrumentation 3.3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SR 3.3.5.1.2 -------------------------------NOTE------------------------------

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

Perform CHANNEL FUNCTIONAL TEST. [92] days SR 3.3.5.1.3 Verify the RWM is not bypassed when THERMAL 18 months POWER is [10]% RTP.

SR 3.3.5.1.4 Verify the ATLM is not bypassed when THERMAL 18 months POWER is [30]% RTP.

SR 3.3.5.1.5 -------------------------------NOTE------------------------------

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

Perform CHANNEL FUNCTIONAL TEST. 18 months SR 3.3.5.1.6 Perform CHANNEL CHECK of process parameter [24] hours and setpoint inputs to the ATLM.

SR 3.3.5.1.7 Verify the bypassing and movement of control rods Prior to and required to be bypassed in the Rod Action and during movement Position Information (RAPI) Subsystem by a second of control rods licensed operator or other qualified member of the bypassed in the technical staff. RAPI Subsystem ABWR TS 3.3-62 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Block Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 1)

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

1. Rod Control & Information System

a. Automated Thermal Limit Monitor [(a)] 2 SR 3.3.5.1.1 SR 3.3.5.1.4 SR 3.3.5.1.6

b. Rod Worth Minimizer 1(b), 2(b) 2 SR 3.3.5.1.2 SR 3.3.5.1.3

2. Reactor Mode Switch - Shutdown Position (c) 4 SR 3.3.5.1.5 (a) THERMAL POWER > [30]% RTP.

(b) With THERMAL POWER [10]% RTP.

(c) Reactor mode switch in the shutdown position.

ABWR TS 3.3-63 Design Control Document/Tier 2

25A5675AU Revision 7 PAM Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.6.1 The PAM instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

1. LCO 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

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

inoperable.

B. Required Action and B.1 Provide alternate method 14 days associated Completion of monitoring, determine Time of Condition A not the cause of the met. inoperability, and submit plans and schedule for restoring the instrumentation channels of the Functions to OPERABLE status to the NRC.

C. One or more Functions with --------------------NOTE-------------------

two required channels This Action is not applicable to inoperable. Functions 11 and 12.

C.1 Restore at least one 7 days inoperable channel to OPERABLE status.

(continued)

ABWR TS 3.3-64 Design Control Document/Tier 2

25A5675AU Revision 7 PAM Instrumentation 3.3.6.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Two required D.1 Restore one required 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months hydrogen/oxygen monitor hydrogen/oxygen monitor channels inoperable. channel to OPERABLE status.

E. Required Action and E.1 Enter the Condition Immediately associated Completion referenced in Time of Condition C or D Table 3.3.6.1-1 for the not met. channel.

F. As required by Required F.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Action E.1 and referenced in Table 3.3.6.1-1.

G. As required by Required G.1 Provide alternate method 14 days Action E.1 and referenced of monitoring, determine in Table 3.3.6.1-1. the cause of the inoperability, and submit plans and schedule for restoring the instrumentation channels of the Functions to OPERABLE status to the NRC.

ABWR TS 3.3-65 Design Control Document/Tier 2

25A5675AU Revision 7 PAM Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

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

1. These SRs apply to each Function in Table 3.3.6.1-1.

2. SR 3.3.6.1.1 does not apply to Function 8.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. [31] days

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

Neutron detectors are excluded.

SR 3.3.6.1.2 Perform CHANNEL CALIBRATION. 18 months ABWR TS 3.3-66 Design Control Document/Tier 2

25A5675AU Revision 7 PAM Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 1)

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

1. Reactor Steam Dome Pressure 2 F

2. Reactor Vessel Water Level - Wide Range 2 F

3. Reactor Vessel Water Level - Fuel Zone 2 F

4. Suppression Pool Water Level 2 F

5. Containment Pressure 5a. Drywell Pressure 2 F 5b. Wide Range Containment Pressure 2 F

6. Drywell Area Radiation 2 G

7. Wetwell Area Radiation 2 G

8. PCIV Position 2 per penetration F flow path (a),(b)

9. Startup Range Neutron Monitor - Neutron Flux 2(c) F (d)

10. Average Power Range Monitor - Neutron Flux 2 F

11. Containment Atmospheric Monitors - Drywell H2 & O2 Analyzer 2 F

12. Containment Atmospheric Monitors - Wetwell H2 & O2 Analyzer 2 F

13. Containment Water Level 2 F

14. Suppression Pool Water Temperature 2(e) F

15. Drywell Atmosphere Temperature 2 F

16. Main Steam Line Radiation 2 F (a) Only one position indication channel is required for penetration flow paths with only one installed control room indication channel.

(b) Not required for isolation valves whose associated penetration flow path is isolated by at least one closed and de-activated automatic valve, closed manual valve, blind flange, or check valve with flow through the valve secured.

(c) When power is [10]% RTP.

(d) When power is > [10]% RTP.

(e) Bulk average temperature.

ABWR TS 3.3-67 Design Control Document/Tier 2

25A5675AU Revision 7 Remote Shutdown System 3.3.6.2 3.3 INSTRUMENTATION 3.3.6.2 Remote Shutdown System LCO 3.3.6.2 The Remote Shutdown System (RSS) instrumentation for each Function listed in Table 3.3.6.2-1 shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS

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

1. LCO 3.0.4. is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED ACTION COMPLETION TIME A. One RSS division with one A.1 Restore required 90 days or more required Functions Functions to OPERABLE inoperable. status.

B. Two RSS divisions with one B.1 Restore required 30 days or more required Functions Functions to OPERABLE inoperable. status.

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

ABWR TS 3.3-68 Design Control Document/Tier 2

25A5675AU Revision 7 Remote Shutdown System 3.3.6.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.6.2.1 Perform CHANNEL CHECK for each required [31] days instrumentation channel.

SR 3.3.6.2.2 Verify each required control circuit and transfer 18 months switch is capable of performing the intended functions.

SR 3.3.6.2.3 Perform CHANNEL CALIBRATION for each required 18 months instrumentation channel.

ABWR TS 3.3-69 Design Control Document/Tier 2

25A5675AU Revision 7 Remote Shutdown System 3.3.6.2 Table 3.3.6.2-1 (page 1 of 2)

Remote Shutdown System Instrumentation REQUIRED NUMBER FUNCTION (INSTRUMENT OR CONTROL PARAMETER) OF DIVISIONS

1. Reactor Steam Dome Pressure 2

2. HPCF B Flow 1

3. HPCF B Controls 1(c)

4. HPCF B Pump Discharge Pressure 1

5. RHR Flow 2(a)

6. RHR Hx Inlet Temperature 2(a)

7. RHR Hx Outlet Temperature 2(a)

8. RHR Hx Bypass Valve Position 2(a)

9. RHR Hx Outlet Valve Position 2(a)

10. RHR Pump Discharge Pressure 2(a)

11. RHR Controls 2(a)(c)

12. RPV Wide Range Water Level 2

13. RPV Narrow Range Water Level 2

14. Reactor Building Cooling Water Flow 2

15. Reactor Building Cooling Water Controls 2(c)

16. Reactor Building Service Water System Controls 2(c)

17. Cooling Water Flow to Flammability Control System 1

18. Suppression Pool Water Level 2

19. Condensate Storage Tank Water Level 2 ABWR TS 3.3-70 Design Control Document/Tier 2

25A5675AU Revision 7 Remote Shutdown System 3.3.6.2 Table 3.3.6.2-1 (page 2 of 2)

Remote Shutdown System Instrumentation REQUIRED NUMBER FUNCTION (INSTRUMENT OR CONTROL PARAMETER) OF DIVISIONS

20. Suppression Pool Temperature 2

21. Electric Power Distribution Controls 2(c)

22. Diesel Generator Interlock and Monitors 2

23. SRV Controls (b)(c)

24. N2 Header Pressure 2

25. Drywell Pressure - Wide Range 2

26. Suppression Pool Water Level - Wide Range 2

27. RPV Wide Range Water Level - Cold 2 (a) RHR A for division I RSS panel, RHR B for division II RSS panel.

(b) Three on the Division I RSS, 1 on division II RSS.

(c) The specified number of channels are required to be OPERABLE for each device that can be controlled from the RSS panels.

ABWR TS 3.3-71 Design Control Document/Tier 2

25A5675AU Revision 7 CRHA EF System Instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3.3.7.1 Control Room Habitability Area (CRHA) Emergency Filtration (EF) System Instrumentation LCO 3.3.7.1 The CRHA EF System instrumentation for each Function in Table 3.3.7.1-1 shall be OPERABLE.

APPLICABILITY: a. MODES 1, 2, and 3.

b. During movement of irradiated fuel assemblies in the secondary containment.

c. During CORE ALTERATIONS.

d. During operations with a potential for draining the reactor vessel.

ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more EF divisions A.1 Place channel in trip. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with one control room ventilation radiation monitor OR channel inoperable.

A.2 Place channel in bypass. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months B. One or more EF divisions B.1 Place one channel in trip 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months with two control room and the other in bypass.

ventilation radiation monitor channels inoperable. AND B.2 Restore one channel to Prior to completion OPERABLE status. of next CHANNEL FUNCTIONAL TEST (continued)

ABWR TS 3.3-72 Design Control Document/Tier 2

25A5675AU Revision 7 CRHA EF System Instrumentation 3.3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Place the associated EF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months associated Completion division in the emergency Time of Condition A or B filtration mode of not met. operation.

OR OR One or more EF divisions C.2 Declare associated EF 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one or more Manual division inoperable.

Switch channel or low flow actuation channel inoperable.

OR One or more EF divisions with 3 or more control room radiation monitor channels inoperable.

SURVEILLANCE REQUIREMENTS

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

Refer to Table 3.3.7.1-1 to determine which SRs apply for each Function.

SURVEILLANCE FREQUENCY SR 3.3.7.1.1 Perform CHANNEL CHECK. [24] hours SR 3.3.7.1.2 Perform CHANNEL FUNCTIONAL TEST. [92] days SR 3.3.7.1.3 Perform CHANNEL CALIBRATION. 18 months SR 3.3.7.1.4 Perform LOGIC SYSTEM FUNCTIONAL TEST. 18 months ABWR TS 3.3-73 Design Control Document/Tier 2

25A5675AU Revision 7 CRHA EF System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)

Control Room Habitability Area - Emergency Filtration System Instrumentation REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Control Room Ventilation Radiation 4 per EF division SR 3.3.7.1.1 [ ] mGy/h Monitors SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4

2. Emergency Filtration System Low Flow 2 per EF division SR 3.3.7.1.2 [ ] kg/h SR 3.3.7.1.3 SR 3.3.7.1.4

3. Emergency Filtration System Manual 1 per EF division SR 3.3.7.1.2 NA Switch SR 3.3.7.1.4 (a) During operations with a potential for draining the reactor vessel.

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

ABWR TS 3.3-74 Design Control Document/Tier 2

25A5675AU Revision 7 Electric Power Monitoring 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Electric Power Monitoring LCO 3.3.8.1 Two Electric Power Monitoring assemblies shall be OPERABLE for each inservice Class 1E Constant Voltage Constant Frequency (CVCF) power supply.

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

ACTIONS

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

Separate Condition entry is allowed for each CVCF power supply.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more inservice A.1 Place the associated 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CVCF power supplies with Electric Power Monitoring one Electric Power assembly circuit breaker Monitoring assembly in the tripped condition.

inoperable.

B. One or more inservice B.1 Remove associated 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months CVCF power supplies with inservice power supply(s) both Electric Power from service.

Monitoring assemblies inoperable.

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

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

ABWR TS 3.3-75 Design Control Document/Tier 2

25A5675AU Revision 7 Electric Power Monitoring 3.3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Initiate action to fully Immediately associated Completion insert all insertable control Time of Condition A or B rods in core cells not met in MODE 4 or 5 containing one or more with any control rod fuel assemblies.

withdrawn from a core cell containing one or more fuel AND assemblies or with both RHR shutdown cooling D.2.1 Initiate action to restore Immediately isolation valves open. one Electric Power Monitoring assembly to OPERABLE status for inservice power supply(s).

OR D.2.2 Initiate action to isolate Immediately the Residual Heat Removal Shutdown Cooling Systems.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.1.1 Perform CHANNEL FUNCTIONAL TEST. [92] days SR 3.3.8.1.2 Perform CHANNEL CALIBRATION. The Allowable [92] days Values for Divisions I, II, III, and IV shall be:

a. Undervoltage: [108] VAC.

b. Overvoltage: [132] VAC.

c. Underfrequency: [57] Hz.

d. Overfrequency: [63] Hz.

SR 3.3.8.1.3 Perform SYSTEM FUNCTIONAL TEST. 18 months ABWR TS 3.3-76 Design Control Document/Tier 2

25A5675AU Revision 7 Reactor Coolant Temperature Monitoring - Shutdown 3.3.8.2 3.3 INSTRUMENTATION 3.3.8.2 Reactor Coolant Temperature Monitoring - Shutdown LCO 3.3.8.2 One Reactor Coolant Temperature Monitoring channel associated with each RHR subsystem operating in the Shutdown Cooling Mode shall be OPERABLE.

APPLICABILITY: When RHR is operating in the Shutdown Cooling Mode.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more reactor A.1 Verify at least one RHR Immediately coolant temperature subsystem is operating in monitoring channels the Shutdown Cooling inoperable. Mode.

AND A.2 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months method of reactor coolant temperature monitoring is AND available.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Initiate action to restore Immediately associated Completion reactor coolant Time of Condition A not temperature monitoring met. capability.

ABWR TS 3.3-77 Design Control Document/Tier 2

25A5675AU Revision 7 Reactor Coolant Temperature Monitoring - Shutdown 3.3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.3.8.2.1 Perform CHANNEL CHECK. [7] days SR 3.3.8.2.2 Perform CHANNEL FUNCTIONAL TEST. [92] days SR 3.3.8.2.3 Perform CHANNEL CALIBRATION. 18 months ABWR TS 3.3-78 Design Control Document/Tier 2

25A5675AU Revision 7 RIPs Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Reactor Internal Pumps (RIPs) - Operating LCO 3.4.1 At least nine RIPs shall be in operation.

[OR

[ ] RIPs may be in operation provided the following limits are applied when the associated LCO is applicable:

a. LCO 3.2.1, AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR), limits specified in the COLR for [ ] RIPs in operation; and

b. LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR), limits specified in the COLR for [ ] RIPs in operation; and

c. LCO 3.3.1.1, SSLC Sensor Instrumentation, Function 2.b (Average Power Range Monitors Flow Biased Simulated Thermal Power -

High), Allowable Value of Table 3.3.1.1-1 is reset for operation with

[ ] RIPs.]

APPLICABILITY: MODES 1 and 2.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify at least the required number of RIPs are 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE at any THERMAL POWER level.

ABWR TS 3.4-1 Design Control Document/Tier 2

25A5675AU Revision 7 S/RVs 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 Safety/Relief Valves (S/RVs)

LCO 3.4.2 The safety function of twelve S/RVs shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required S/RV A.1 Restore required S/RV to 14 day inoperable. OPERABLE status.

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

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

ABWR TS 3.4-2 Design Control Document/Tier 2

25A5675AU Revision 7 S/RVs 3.4.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.2.1 Verify the safety function lift setpoints of the required In accordance S/RVs are as follows: with the Inservice Testing Program Number of Setpoint S/RVs (MPaG) 2 7.92 +/- 0.0792 4 7.99 +/- 0.0799 4 8.06 +/- 0.0806 4 8.13 +/- 0.0813 4 8.19 +/- 0.0819 Following testing, lift settings shall be within +/- 1%.

SR 3.4.2.2 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is 6.55 MPaG.

Verify each required S/RV opens when manually 18 months actuated.

ABWR TS 3.4-3 Design Control Document/Tier 2

25A5675AU Revision 7 RCS Operational LEAKAGE 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Operational LEAKAGE LCO 3.4.3 RCS operational LEAKAGE shall be limited to:

a. No pressure boundary LEAKAGE,

b. 3.785 L/min unidentified LEAKAGE; and

c. 98.4 L/min total LEAKAGE averaged over the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period.

APPLICABILITY: MODES 1, 2, and 3.

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

OR Total LEAKAGE not within limit.

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

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

ABWR TS 3.4-4 Design Control Document/Tier 2

25A5675AU Revision 7 RCS Operational LEAKAGE 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1 Verify RCS unidentified and total LEAKAGE are 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months within limits.

ABWR TS 3.4-5 Design Control Document/Tier 2

25A5675AU Revision 7 RCS PIV Leakage 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.4 The leakage from each RCS PIV shall be within limit.

APPLICABILITY: MODES 1 and 2, MODE 3, except valves in the residual heat removal (RHR) shutdown cooling flowpath are not required to meet the requirements of this LCO when in the shutdown cooling mode of operation.

ACTIONS

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

1. Separate Condition entry is allowed for each flow path.

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

CONDITION REQUIRED ACTION COMPLETION TIME A. Leakage from one or more --------------------NOTE-------------------

RCS PIVs not within limit. Each valve used to satisfy Required Action A.1 and Required Action A.2 shall have been verified to meet SR 3.4.4.1 and be in the reactor coolant pressure boundary.

A.1 Isolate the high pressure 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months portion of the affected system from the low pressure portion by use of one closed manual, deactivated automatic, or check valve.

AND (continued)

ABWR TS 3.4-6 Design Control Document/Tier 2

25A5675AU Revision 7 RCS PIV Leakage 3.4.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Isolate the high pressure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months portion of the affected system from the low pressure portion by use of a second closed manual, deactivated automatic, or check valve.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 -------------------------------NOTE------------------------------

Not required to be performed in MODE 3.

Verify equivalent leakage of each RCS PIV is 18 months 1.9 L/min per 2.54 cm (nominal inch) of valve size up to a maximum of 19 L/min, at an RCS pressure 7.17 MPaG and 7.31 MPaG.

ABWR TS 3.4-7 Design Control Document/Tier 2

25A5675AU Revision 7 RCS Leakage Detection Instrumentation 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.5 RCS Leakage Detection Instrumentation LCO 3.4.5 The following RCS leakage detection instrumentation shall be OPERABLE:

a. Drywell floor drain sump monitoring system;

b. The airborne particulate channel of the drywell fission products monitoring system; and

c. The gaseous radioactivity channel of the drywell fission products monitoring system or the drywell air cooler condensate flow monitoring system.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell floor drain sump --------------------NOTE-------------------

monitoring system LCO 3.0.4 is not applicable.

inoperable. ------------------------------------------------

A.1 Restore drywell floor drain 30 days sump monitoring system to OPERABLE status.

B. Airborne particulate --------------------NOTE-------------------

channel of drywell fission LCO 3.0.4 is not applicable.

products monitoring system ------------------------------------------------

inoperable.

B.1 Analyze grab samples of Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months drywell atmosphere.

AND B.2 Restore airborne 30 days particulate channel of drywell fission product monitoring system to OPERABLE status.

(continued)

ABWR TS 3.4-8 Design Control Document/Tier 2

25A5675AU Revision 7 RCS Leakage Detection Instrumentation 3.4.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Gaseous radioactivity --------------------NOTE-------------------

channel of drywell fission LCO 3.0.4 is not applicable.

products monitoring system ------------------------------------------------

inoperable.

AND C.1 Restore gaseous 30 days radioactivity channel of Drywell air cooler drywell fission products condensate flow monitoring monitoring system to system inoperable. OPERABLE status.

OR C.2 Restore drywell air cooler 30 days condensate flow monitoring system to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, or AND C not met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. All required leakage E.1 Enter LCO 3.0.3. Immediately detection systems inoperable.

ABWR TS 3.4-9 Design Control Document/Tier 2

25A5675AU Revision 7 RCS Leakage Detection Instrumentation 3.4.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.5.1 Perform CHANNEL CHECK of required drywell 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months atmospheric monitoring system.

SR 3.4.5.2 Perform CHANNEL FUNCTIONAL TEST of required 31 days leakage detection instrumentation.

SR 3.4.5.3 Perform CHANNEL CALIBRATION of required 18 months leakage detection instrumentation.

ABWR TS 3.4-10 Design Control Document/Tier 2

25A5675AU Revision 7 RCS Specific Activity 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Specific Activity LCO 3.4.6 The specific activity of the reactor coolant shall be limited to:

a. DOSE EQUIVALENT I-131 specific activity 7400 Bq/g; and

b. Gross specific activity (3.7x106/) Bq/g.

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

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

activity > 7400 Bq/g and LCO 3.0.4 is not applicable.

148,000 Bq/g DOSE ------------------------------------------------

EQUIVALENT I-131.

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

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

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

Time of Condition A not met. AND OR B.2.1 Isolate all main steam 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months lines.

Reactor coolant specific activity OR

> 148,000 Bq/g DOSE EQUIVALENT I-131. B.2.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.2.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (continued)

ABWR TS 3.4-11 Design Control Document/Tier 2

25A5675AU Revision 7 RCS Specific Activity 3.4.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Reactor coolant specific C.1 Isolate all main steam 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months activity > (3.7x106/) Bq/g. lines.

OR C.2.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND C.2.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.6.1 Verify reactor coolant gross specific activity is 7 days (3.7x106/) Bq/g.

SR 3.4.6.2 -------------------------------NOTE------------------------------

Only required to be performed in MODE 1.

Verify reactor coolant DOSE EQUIVALENT I-131 31 days specific activity is 7400 Bq/g.

SR 3.4.6.3 -------------------------------NOTE------------------------------

Not required to be performed until 31 days after a minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

Determine from a sample taken in MODE 1 after a 184 days minimum of 2 effective full power days and 20 days of MODE 1 operation have elapsed since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

ABWR TS 3.4-12 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Shutdown Cooling System - Hot Shutdown 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.7 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown LCO 3.4.7 Three RHR shutdown cooling subsystems shall be OPERABLE, and, with less than 5 reactor internal pumps (RIPs) in operation, at least one RHR shutdown cooling subsystem shall be in operation.

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

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

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

APPLICABILITY: MODE 3 with reactor steam dome pressure < 0.932 MPaG.

ACTIONS

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

LCO 3.0.4 is not applicable.

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

AND (continued)

ABWR TS 3.4-13 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Shutdown Cooling System - Hot Shutdown 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 Initiate action to be in Immediately MODE 4.

AND A.3 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months method of decay heat removal is available for each required inoperable RHR shutdown cooling subsystem.

B. No RHR shutdown cooling B.1.1 Initiate action to restore Immediately subsystem in operation. one RHR shutdown cooling subsystem to AND operation.

Less than 5 RIPs in OR operation.

B.1.2 Initiate action to restore at Immediately least 5 RIPs to operation.

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

ABWR TS 3.4-14 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Shutdown Cooling System - Hot Shutdown 3.4.7 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.7.1 -------------------------------NOTE------------------------------

Not required to be met until 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after reactor steam dome pressure is < 0.932 MPaG.

Verify one RHR shutdown cooling subsystem or at 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months least 5 RIPs are operating.

ABWR TS 3.4-15 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Shutdown Cooling System - Cold Shutdown 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown LCO 3.4.8 Three RHR shutdown cooling subsystems shall be OPERABLE, and, with less than 5 reactor internal pumps (RIPs) in operation, at least one RHR shutdown cooling subsystem shall be in operation.

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

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

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

3. One RHR shutdown cooling subsystem may be inoperable after 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months from initial entry into MODE 4 from MODE 3.

APPLICABILITY: MODE 4.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required RHR A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months shutdown cooling method of decay heat subsystems inoperable. removal is available for AND each required inoperable RHR shutdown cooling Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months subsystem. thereafter (continued)

ABWR TS 3.4-16 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Shutdown Cooling System - Cold Shutdown 3.4.8 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. No RHR shutdown cooling B.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from subsystem in operation. circulating by an alternate discovery of no method. reactor coolant AND circulation Less than 5 RIPs in AND operation.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Monitor reactor coolant Once per hour temperature and pressure.

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

ABWR TS 3.4-17 Design Control Document/Tier 2

25A5675AU Revision 7 RCS P/T Limits 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.9 RCS Pressure and Temperature (P/T) Limits LCO 3.4.9 RCS pressure, RCS temperature, RCS heatup and cooldown rate requirements shall be maintained within the limits specified in the PTLR.

APPLICABILITY: At all times.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Restore parameter(s) to 30 minutes Required Action A.2 shall within limits.

be completed if this Condition is entered. AND A.2 Determine RCS is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Requirements of the acceptable for continued LCO not met in MODES 1, operation.

2, and 3.

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

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

Condition is entered.

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

ABWR TS 3.4-18 Design Control Document/Tier 2

25A5675AU Revision 7 RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.9.1 -------------------------------NOTE------------------------------

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

Verify RCS pressure, RCS temperature, and RCS 30 minutes heatup and cooldown rates are within the limits specified in the PTLR.

SR 3.4.9.2 Verify RCS pressure and RCS temperature are Once within within the criticality limits specified in the PTLR. 15 minutes prior to control rod withdrawal for the purpose of achieving criticality SR 3.4.9.3 -------------------------------NOTE------------------------------

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

Verify reactor vessel flange and head flange 30 minutes temperatures are within the limits specified in the PTLR.

SR 3.4.9.4 -------------------------------NOTE------------------------------

Not required to be performed until 30 minutes after RCS temperature [27°C] in MODE 4.

Verify reactor vessel flange and head flange 30 minutes temperatures are within the limits specified in the PTLR.

(continued)

ABWR TS 3.4-19 Design Control Document/Tier 2

25A5675AU Revision 7 RCS P/T Limits 3.4.9 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.4.9.5 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after RCS temperature [38°C] in MODE 4.

Verify reactor vessel flange and head flange 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months temperatures are within the limits specified in the PTLR.

ABWR TS 3.4-20 Design Control Document/Tier 2

25A5675AU Revision 7 Reactor Steam Dome Pressure 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.10 Reactor Steam Dome Pressure LCO 3.4.10 The reactor steam dome pressure shall be 7.17 MPaG.

APPLICABILITY: MODES 1 and 2.

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

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify reactor steam dome pressure is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 7.17 MPaG.

ABWR TS 3.4-21 Design Control Document/Tier 2

25A5675AU Revision 7 ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.1 ECCS - Operating LCO 3.5.1 Each ECCS subsystem and the Automatic Depressurization System (ADS) function of eight safety/relief valves shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3, except ADS valves and RCIC are not required to be OPERABLE with reactor steam dome pressure 0.343 MPaG for ADS and 1.03 MPaG for RCIC.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two ECCS A.1 Restore ECCS 14 days subsystems inoperable subsystem(s) to provided RCIC is OPERABLE status.

OPERABLE.

B. RCIC inoperable. B.1.1 Verify the CTG is 7 days functional by verifying the OR CTG starts and achieves steady state voltage and RCIC and any one other frequency within ECCS subsystem 2 minutes.

inoperable.

AND B.1.2 Verify the CTG circuit 7 days breakers are capable of being aligned to each of AND the ESF buses.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR thereafter B.2 Verify the ACIWA mode 7 days of RHR(B or C) subsystem is functional.

AND B.3 Restore ECCS 14 days subsystem(s) to OPERABLE status.

(continued)

ABWR TS 3.5-1 Design Control Document/Tier 2

25A5675AU Revision 7 ECCS - Operating 3.5.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. RCIC and any other two C.1.1.1 Verify the CTG is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ECCS subsystems functional by verifying the inoperable provided at least CTG starts and achieves one HPCF subsystem is steady state voltage and OPERABLE. frequency within 2 minutes.

AND C.1.1.2 Verify the CTG circuit 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months breakers are capable of being aligned to each of AND the ESF buses.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months OR thereafter C.1.2 Verify the ACIWA mode 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of RHR(B or C) subsystem is functional.

AND C.2 Restore one ECCS 7 days subsystem to OPERABLE status.

D. Any three ECCS D.1 Restore one ECCS 3 days subsystems inoperable subsystem to OPERABLE provided RCIC is status.

OPERABLE.

E. Three high pressure ECCS E.1 Restore one high 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months subsystems inoperable. pressure ECCS subsystem to OPERABLE status.

(continued)

ABWR TS 3.5-2 Design Control Document/Tier 2

25A5675AU Revision 7 ECCS - Operating 3.5.1 ACTIONS (continued)

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

F.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Any four ECCS subsystems inoperable.

G. ------------NOTE------------ G.1 Restore ADS valves to 14 days This Condition may exist OPERABLE status.

concurrently with Conditions A through D.

One or two ADS valves inoperable.

H. -----------NOTE----------- H.1 Restore one ADS valve to 7 days This Condition may exist OPERABLE status.

concurrently with Conditions A through C.

Three ADS valves inoperable.

I. Four or more ADS valves I.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable.

OR AND Required Action and I.2 Reduce reactor steam 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months associated Completion dome pressure to Time of Condition G or H 0.343 MPaG.

not met.

ABWR TS 3.5-3 Design Control Document/Tier 2

25A5675AU Revision 7 ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify, for each ECCS subsystem, the piping is filled 31 days with water from the pump discharge valve to the injection valve.

SR 3.5.1.2 ----------------------------NOTE---------------------------

Low pressure core flooder (LPFL) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than 0.932 MPaG in MODE 3, if capable of being manually realigned and not otherwise inoperable.

Verify each ECCS subsystem manual, power 31 days operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.1.3 Verify ADS nitrogen supply pressure is 1.11 MPaG. 31 days SR 3.5.1.4 Verify each motor driven ECCS pump develops the 92 days specified flow rate against a system head corresponding to the specified reactor pressure.

SYSTEM HEAD CORRESPONDING TO A REACTOR SYSTEM FLOW RATE PRESSURE OF LPFL 954 m3/h 0.275 MPaG HPCF 182 m3/h 8.12 MPaG SR 3.5.1.5 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is 6.55 MPaG.

Verify, with RCIC steam supply pressure 92 days 7.07 MPaG and 6.55 MPaG, the RCIC pump can develop a flow 182 m3/h against a system head corresponding to reactor pressure.

(continued)

ABWR TS 3.5-4 Design Control Document/Tier 2

25A5675AU Revision 7 ECCS - Operating 3.5.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.1.6 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is 1.03 MPaG.

Verify, with RCIC steam supply pressure 18 months 1.14 MPaG, the RCIC pump can develop a flow rate 182 m3/h against a system head corresponding to reactor pressure.

SR 3.5.1.7 -------------------------------NOTE------------------------------

Vessel injection may be excluded.

Verify each ECCS subsystem actuates on an actual 18 months or simulated automatic initiation signal.

SR 3.5.1.8 -------------------------------NOTE------------------------------

Valve actuation may be excluded.

Verify the ADS actuates on an actual or simulated 18 months automatic initiation signal.

SR 3.5.1.9 -------------------------------NOTE------------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after reactor steam dome pressure is 6.55 MPaG.

Verify each ADS valve opens when manually 18 months actuated.

ABWR TS 3.5-5 Design Control Document/Tier 2

25A5675AU Revision 7 ECCS - Shutdown 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS - Shutdown LCO 3.5.2 Two ECCS subsystems shall be OPERABLE.

APPLICABILITY: MODE 4, MODE 5 except with the reactor cavity to dryer/separator storage pool gate removed and water level 7.0 m over the top of the reactor pressure vessel flange.

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

B. Required Action and B.1 Initiate action to suspend Immediately associated Completion operations with a potential Time of Condition A not for draining the reactor met. vessel (OPDRVs).

C. Two required ECCS C.1 Initiate action to suspend Immediately subsystems inoperable. OPDRVs.

AND C.2 Restore one ECCS 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystem to OPERABLE status.

(continued)

ABWR TS 3.5-6 Design Control Document/Tier 2

25A5675AU Revision 7 ECCS - Shutdown 3.5.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action C.2 and D.1 Initiate action to restore Immediately associated Completion secondary containment to Time not met. OPERABLE status.

AND D.2 Initiate action to restore Immediately one standby gas treatment subsystem to OPERABLE status.

AND D.3 Initiate action to restore Immediately one isolation valve and associated instrumentation to OPERABLE status in each secondary containment penetration flow path not isolated.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.2.1 Verify, for each required Low Pressure Core Flooder 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (LPFL) subsystem, the suppression pool water level is 7.0 m.

SR 3.5.2.2 Verify, for the required High Pressure Core Flooder 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (HPCF) subsystem, the:

a. Suppression pool water level is 7.0 m, or

b. Condensate storage tank water level is [ ].

(continued)

ABWR TS 3.5-7 Design Control Document/Tier 2

25A5675AU Revision 7 ECCS - Shutdown 3.5.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.5.2.3 Verify, for each required ECCS subsystem, the 31 days piping is filled with water from the pump discharge valve to the injection valve.

SR 3.5.2.4 -------------------------------NOTE------------------------------

Low Pressure Core Flooder (LPFL) subsystem may be considered OPERABLE during alignment and operation in the decay heat removal shutdown cooling mode, if capable of being manually realigned and not otherwise inoperable.

Verify each required ECCS subsystem manual, 31 days power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.5.2.5 Verify each required ECCS pump develops the 92 days specified flow rate against a system head corresponding to the specified reactor pressure.

SYSTEM HEAD CORRESPONDING NO OF TO A REACTOR SYSTEM FLOW RATE PUMPS PRESSURE OF LPFL 954 m3/h 1 0.275 MPaG HPCF 182 m3/h 1 8.12 MPaG SR 3.5.2.6 -------------------------------NOTE------------------------------

Vessel injection may be excluded.

Verify each required ECCS subsystem actuates on 18 months an actual or simulated automatic initiation signal.

ABWR TS 3.5-8 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment 3.6.1.1 3.6 CONTAINMENT SYSTEMS 3.6.1.1 Primary Containment LCO 3.6.1.1 Primary containment shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore primary 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. containment to OPERABLE status.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ABWR TS 3.6-1 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment 3.6.1.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1.1 Perform required visual examinations and leakage -------NOTE-------

rate testing except for primary containment air lock SR 3.0.2 is not testing, in accordance with 10 CFR 50, Appendix J, applicable as modified by approved exemptions. ----------------------

The maximum allowable leakage rate, La, is 0.5% of In accordance primary containment air weight per day at the with 10 CFR 50, calculated peak containment pressure, Pa. Appendix J, as modified by approved exemptions SR 3.6.1.1.2 Verify drywell to suppression chamber differential 18 months pressure does not decrease at a rate > 12 mm water gauge per minute tested over a 15 minute period at AND an initial differential pressure of 0.031 MPaD.

NOTE-------

Only required after two consecutive tests fail and continues until two consecutive tests pass 9 months ABWR TS 3.6-2 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment Air Locks 3.6.1.2 3.6 CONTAINMENT SYSTEMS 3.6.1.2 Primary Containment Air Locks LCO 3.6.1.2 Two primary containment air locks shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS

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

1. Entry and exit is permissible to perform repairs of the affected air lock components.

2. Separate Condition entry is allowed for each air lock.

3. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, Primary Containment, when air lock leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more primary -------------------NOTES------------------

containment air locks with 1. Required Actions A.1, A.2, one primary containment and A.3 are not applicable if both air lock door inoperable. doors in the same air lock are inoperable and Condition C is entered.

2. Entry and exit is permissible for 7 days under administrative controls if both air locks are inoperable.

(continued)

ABWR TS 3.6-3 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment Air Locks 3.6.1.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1 Verify the OPERABLE door 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months is closed in the affected air lock(s).

AND A.2 Lock the OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock(s).

AND A.3 ---------------NOTE-------------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify the OPERABLE door Once per 31 days is locked closed in the affected air lock(s).

(continued)

ABWR TS 3.6-4 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment Air Locks 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One or more primary -------------------NOTES------------------

containment air locks with 1. Required Actions B.1, B.2, primary containment air and B.3 are not applicable if both lock interlock mechanism doors in the same air lock are inoperable. inoperable and Condition C is entered.

2. Entry into and exit from containment is permissible under the control of a dedicated individual.

B.1 Verify an OPERABLE 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months door is closed in the affected air lock(s).

AND B.2 Lock an OPERABLE door 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months closed in the affected air lock(s).

AND B.3 --------------NOTE------------

Air lock doors in high radiation areas or areas with limited access due to inerting may be verified locked closed by administrative means.

Verify an OPERABLE Once per 31 days door is locked closed in the affected air lock(s).

(continued)

ABWR TS 3.6-5 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment Air Locks 3.6.1.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more primary C.1 Initiate action to evaluate Immediately containment air locks primary containment inoperable for reasons overall leakage rate per other than Condition A or B. LCO 3.6.1.1, using current air lock test results.

AND C.2 Verify a door is closed in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months the affected air lock(s).

AND C.3 Restore air lock(s) to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ABWR TS 3.6-6 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment Air Locks 3.6.1.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.2.1 ------------------------------NOTES-----------------------------

1. An inoperable air lock door does not invalidate the previous successful performance of the overall air lock leakage test.

2. Results shall be evaluated against acceptance criteria of SR 3.6.1.1.1 in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.

Perform required primary containment air lock --------NOTE--------

leakage rate testing in accordance with 10 CFR 50, SR 3.0.2 is not Appendix J, as modified by approved exemptions. applicable The acceptance criteria for air lock testing are: In accordance with 10 CFR 50,

a. Overall air lock leakage rate is 0.05 La when Appendix J, as tested at Pa. modified by approved

b. For each door, leakage rate is 0.01 La when exemptions the gap between the door seals is pressurized to [ ] MPaG for at least 15 minutes.

SR 3.6.1.2.2 ------------------------------NOTE------------------------------

Only required to be performed upon entry into primary containment when the primary containment is de-inerted.

Verify only one door in the primary containment air 184 days lock can be opened at a time.

ABWR TS 3.6-7 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 3.6 CONTAINMENT SYSTEMS 3.6.1.3 Primary Containment Isolation Valves (PCIVs)

LCO 3.6.1.3 Each PCIV shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, When associated instrumentation is required to be OPERABLE per LCO 3.3.1.1, SSLC Sensor Instrumentation, and LCO 3.3.1.4, ESF Actuation Instrumentation.

ACTIONS

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

1. Penetration flow paths except for purge valve penetration flow paths may be unisolated intermittently under administrative controls.

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

3. Enter applicable Conditions and Required Actions for systems made inoperable by PCIVs.

4. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, Primary Containment, when PCIV leakage results in exceeding overall containment leakage rate acceptance criteria.

CONDITION REQUIRED ACTION COMPLETION TIME A. ------------NOTE------------ A.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for Only applicable to penetration flow path by main steam line penetration flow paths with use of at least one closed two PCIVs. and de-activated AND

automatic valve, closed manual valve, blind 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for main One or more penetration flange, or check valve steam line flow paths with one PCIV with flow through the inoperable except for purge valve secured.

valve leakage not within limit. AND (continued)

ABWR TS 3.6-8 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 --------------NOTE------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is for isolation isolated. devices outside primary containment, drywell, and steam tunnel AND Prior to entering MODE 2 or 3 from MODE 4, if primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days, for isolation devices inside primary containment (continued)

ABWR TS 3.6-9 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. ------------NOTE------------ B.1 Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Only applicable to penetration flow path by penetration flow paths with use of at least one closed two PCIVs. and de-activated

automatic valve, closed manual valve, or blind One or more penetration flange.

flow paths with two PCIVs inoperable except for purge valve leakage not within limit.

C. ------------NOTE------------ C.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months except for Only applicable to penetration flow path by excess flow check penetration flow paths with use of at least one closed valves (EFCVs) only one PCIV. and de-activated

automatic valve, closed AND manual valve, or blind One or more penetration flange. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for flow paths with one PCIV EFCVs inoperable.

AND C.2 --------------NOTE------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

(continued)

ABWR TS 3.6-10 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One or more penetration D.1 Isolate the affected 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months flow paths with one or more penetration flow path by containment purge valves use of at least one [closed not within purge valve and de-activated leakage limits. automatic valve, closed manual valve, or blind flange].

AND D.2 --------------NOTE------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is for isolation isolated. devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment AND D.3 Perform SR 3.6.1.3.7 for Once per [92] days the resilient seal purge valves closed to comply with Required Action D.1.

(continued)

ABWR TS 3.6-11 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Required Action and E.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, C, AND or D not met in MODE 1, 2, or 3. E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months F. Required Action and F.1 --------------NOTE------------

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

or D not met for PCIV(s) ----------------------------------

required to be OPERABLE during movement of Suspend movement of Immediately irradiated fuel assemblies irradiated fuel assemblies in the secondary in the secondary containment. containment.

G. Required Action and G.1 Suspend CORE Immediately associated Completion ALTERATIONS.

Time of Condition A, B, C, or D not met for PCIV(s) required to be OPERABLE during CORE ALTERATIONS.

H. Required Action and H.1 Initiate action to suspend Immediately associated Completion OPDRVs.

Time of Condition A, B, C, or D not met for PCIV(s) OR required to be OPERABLE during MODE 4 or 5 or H.2 Initiate action to restore Immediately during operations with a valve(s) to OPERABLE potential for draining the status.

reactor vessel (OPDRVs).

ABWR TS 3.6-12 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.1 -------------------------------NOTE------------------------------

Only required to be met in MODES 1, 2, and 3.

Verify each 550 mm primary containment purge 31 days valve is sealed closed except for one purge valve in a penetration flow path while in Condition D of this LCO.

SR 3.6.1.3.2 ------------------------------NOTES-----------------------------

1. Only required to be met in MODES 1, 2, and 3.

2. Not required to be met when the 550 mm primary containment purge valves are open for inerting, de-inerting, pressure control, ALARA or air quality considerations for personnel entry, or Surveillances that require the valves to be open.

Verify each 550 mm primary containment purge 31 days valve is closed.

SR 3.6.1.3.3 ------------------------------NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual 31 days valve and blind flange that is located outside primary containment and is required to be closed during accident conditions is closed.

(continued)

ABWR TS 3.6-13 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.4 ------------------------------NOTES------------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for PCIVs that are open under administrative controls.

Verify each primary containment isolation manual Prior to entering valve and blind flange that is located inside primary MODE 2 or 3 from containment and is required to be closed during MODE 4, if accident conditions is closed. primary containment was de-inerted while in MODE 4, if not performed within the previous 92 days SR 3.6.1.3.5 Verify continuity of the automatic traversing incore 31 days probe (ATIP) shear isolation valve explosive charge.

SR 3.6.1.3.6 Verify the isolation time of each power operated and In accordance each automatic PCIV, except MSIVs, is within limits. with the Inservice Testing Program SR 3.6.1.3.7 ------------------------------NOTES------------------------------

1. Only required to be met in MODES 1, 2, and 3.

2. Results shall be evaluated against acceptance criteria of SR 3.6.1.1.1 in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.

Perform leakage rate testing for each primary 184 days containment purge valve with resilient seals.

AND Once within 92 days after opening the valve (continued)

ABWR TS 3.6-14 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.8 Verify the isolation time (i.e., total closure time 3 months exclusive of electrical delays) of each MSIV is 3 seconds and 4.5 seconds.

SR 3.6.1.3.9 Verify each automatic PCIV actuates to the isolation 18 months position on an actual or simulated isolation signal.

SR 3.6.1.3.10 Verify each reactor instrumentation line EFCV 18 months actuates on a simulated instrument line break to restrict flow to 1.05 cm3/s.

SR 3.6.1.3.11 Remove and test the explosive squib from each 18 months on a shear isolation valve of the ATIP System. STAGGERED TEST BASIS SR 3.6.1.3.12 -------------------------------NOTE------------------------------

1. Only required to be met in MODES 1, 2, and 3.

2. Results shall be evaluated against acceptance criteria of SR 3.6.1.1.1 in accordance with 10 CFR 50, Appendix J, as modified by approved exemptions.

Verify the combined leakage rate of 0.277 cm3/hr 18 months times the total number of PCIVs through hydrostatically tested lines that penetrate the primary containment is not exceeded when these isolation valves are tested at 0.312 MPaG.

(continued)

ABWR TS 3.6-15 Design Control Document/Tier 2

25A5675AU Revision 7 PCIVs 3.6.1.3 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.1.3.13 -------------------------------NOTE------------------------------ --------NOTE--------

Results shall be evaluated against acceptance SR 3.0.2 is not criteria of SR 3.6.1.1.1 in accordance with applicable 10 CFR 50, Appendix J, as modified by approved ------------------------

exemptions.

Verify leakage rate through each MSIV is 1 m3/h In accordance when tested at 0.170 MPaG. with 10 CFR 50, Appendix J, as modified by approved exemptions SR 3.6.1.3.14 -------------------------------NOTE------------------------------

Only required to be met in MODES 1, 2, and 3.

Verify each [550 mm] primary containment purge 18 months valve is blocked to restrict the valve from opening

> [50]%.

ABWR TS 3.6-16 Design Control Document/Tier 2

25A5675AU Revision 7 Drywell Pressure 3.6.1.4 3.6 CONTAINMENT SYSTEMS 3.6.1.4 Drywell Pressure LCO 3.6.1.4 Drywell pressure shall be 5.20 kPaG.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell pressure not within A.1 Restore drywell pressure 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months limit. to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.4.1 Verify drywell pressure is within limit. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ABWR TS 3.6-17 Design Control Document/Tier 2

25A5675AU Revision 7 Drywell Air Temperature 3.6.1.5 3.6 CONTAINMENT SYSTEMS 3.6.1.5 Drywell Air Temperature LCO 3.6.1.5 Drywell average air temperature shall be 57°C.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Drywell average air A.1 Restore drywell average 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months temperature not within limit. air temperature to within limit.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.5.1 Verify drywell average air temperature is within limit. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ABWR TS 3.6-18 Design Control Document/Tier 2

25A5675AU Revision 7 Wetwell-to-Drywell Vacuum Breakers 3.6.1.6 3.6 CONTAINMENT SYSTEMS 3.6.1.6 Wetwell-to-Drywell Vacuum Breakers LCO 3.6.1.6 Eight wetwell-to-drywell vacuum breakers shall be OPERABLE.

AND Eight wetwell-to-drywell vacuum breakers shall be closed.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One wetwell-to-drywell A.1 Restore the inoperable 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months vacuum breaker inoperable vacuum breaker to for opening. OPERABLE status.

B. One or more wetwell-to- B.1 Verify closure of the 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months drywell vacuum breaker(s) vacuum breaker(s) by not closed. alternate methods.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ABWR TS 3.6-19 Design Control Document/Tier 2

25A5675AU Revision 7 Wetwell-to-Drywell Vacuum Breakers 3.6.1.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.6.1 -------------------------------NOTE------------------------------

Not required to be met for vacuum breakers when performing their intended function.

Verify each vacuum breaker is closed. 14 days AND Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after any discharge of steam to the wetwell from the safety/relief valves (S/RVs) or any operation that causes the wetwell-drywell differential pressure to be reduced by 0.69 kPaD SR 3.6.1.6.2 Perform a functional test of each vacuum breaker. 18 months SR 3.6.1.6.3 Verify each required vacuum breaker fully opens at 18 months 3.43 kPaD.

SR 3.6.1.6.4 Perform CHANNEL CALIBRATION of vacuum 18 months breaker position indication channel.

ABWR TS 3.6-20 Design Control Document/Tier 2

25A5675AU Revision 7 Suppression Pool Average Temperature 3.6.2.1 3.6 CONTAINMENT SYSTEMS 3.6.2.1 Suppression Pool Average Temperature LCO 3.6.2.1 Suppression pool average temperature shall be:

a. 35°C when THERMAL POWER is > 1% RTP and no testing that adds heat to the suppression pool is being performed;

b. 40.6°C when THERMAL POWER is > 1% RTP and testing that adds heat to the suppression pool is being performed; and

c. 43.3°C when THERMAL POWER is 1% RTP.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool average A.1 Verify suppression pool Once per hour temperature > 35°C but average temperature 43.3°C. 43.3°C.

AND AND THERMAL POWER is A.2 Restore suppression pool 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

> 1% RTP. average temperature to 35°C.

AND Not performing testing that adds heat to the suppression pool.

(continued)

ABWR TS 3.6-21 Design Control Document/Tier 2

25A5675AU Revision 7 Suppression Pool Average Temperature 3.6.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Reduce THERMAL 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion POWER to < 1% RTP.

Time of Condition A not met.

C. Suppression pool average C.1 Suspend all testing that Immediately temperature > 40.6°C. adds heat to the suppression pool.

AND THERMAL POWER

> 1% RTP.

AND Performing testing that adds heat to the suppression pool.

D. Suppression pool average D.1 Verify suppression pool Once per temperature > 43.3°C but average temperature is 30 minutes 48.9°C. 48.9°C.

E. Suppression pool average E.1 Depressurize the reactor 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months temperature > 48.9°C. vessel to < 1.38 MPaG.

AND E.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ABWR TS 3.6-22 Design Control Document/Tier 2

25A5675AU Revision 7 Suppression Pool Average Temperature 3.6.2.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.1.1 Verify suppression pool average temperature is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months within the applicable limits.

AND 5 minutes when performing testing that adds heat to the suppression pool ABWR TS 3.6-23 Design Control Document/Tier 2

25A5675AU Revision 7 Suppression Pool Water Level 3.6.2.2 3.6 CONTAINMENT SYSTEMS 3.6.2.2 Suppression Pool Water Level LCO 3.6.2.2 Suppression pool water level shall be 7 meters and 7.1 meters.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Suppression pool water A.1 Restore suppression pool 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level not within limits. water level to within limits.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.2.1 Verify suppression pool water level is within limits. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ABWR TS 3.6-24 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Suppression Pool Cooling 3.6.2.3 3.6 CONTAINMENT SYSTEMS 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling LCO 3.6.2.3 Three RHR suppression pool cooling subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR suppression pool A.1 Restore RHR suppression 14 days cooling subsystem pool cooling subsystem to inoperable. OPERABLE status.

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

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Two or more RHR suppression pool cooling subsystems inoperable.

ABWR TS 3.6-25 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Suppression Pool Cooling 3.6.2.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.3.1 Verify each RHR suppression pool cooling 31 days subsystem manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.3.2 Verify each RHR pump develops a flow rate 92 days 954 m3/h through the associated heat exchanger while operating in the suppression pool cooling mode.

ABWR TS 3.6-26 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Containment Spray 3.6.2.4 3.6 CONTAINMENT SYSTEMS 3.6.2.4 Residual Heat Removal (RHR) Containment Spray LCO 3.6.2.4 Two RHR containment spray subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RHR containment A.1 Verify the ACIWA mode 7 days spray subsystem of RHR(B or C) inoperable. subsystem is functional.

AND A.2 Restore RHR 14 days containment spray subsystem to OPERABLE status.

B. Two RHR containment B.1 Restore one RHR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months spray subsystems containment spray inoperable. subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ABWR TS 3.6-27 Design Control Document/Tier 2

25A5675AU Revision 7 RHR Containment Spray 3.6.2.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.2.4.1 Verify each RHR containment spray subsystem 31 days manual, power operated, and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position or can be aligned to the correct position.

SR 3.6.2.4.2 Verify each associated (i.e., in subsystems B & C) 92 days RHR pump develops a flow rate 114 m3/h and

< 160 m3/h through the wetwell spray sparger.

ABWR TS 3.6-28 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment Hydrogen Recombiners 3.6.3.1 3.6 CONTAINMENT SYSTEMS 3.6.3.1 Primary Containment Hydrogen Recombiners LCO 3.6.3.1 Two primary containment hydrogen recombiners shall be OPERABLE.

APPLICABILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One primary containment A.1 --------------NOTE-------------

hydrogen recombiner LCO 3.0.4 is not inoperable. applicable.

Restore primary 30 days containment hydrogen recombiner to OPERABLE status.

B. Two primary containment B.1 Verify by administrative 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months hydrogen recombiners means that the hydrogen inoperable. control function is AND maintained.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND B.2 Restore one primary 7 days containment hydrogen recombiner to OPERABLE status.

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

ABWR TS 3.6-29 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment Hydrogen Recombiners 3.6.3.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.1.1 Perform a system functional test for each primary 6 months containment hydrogen recombiner.

SR 3.6.3.1.2 Perform a system functional test for each primary 18 months containment hydrogen recombiner.

SR 3.6.3.1.3 Visually examine each primary containment 18 months hydrogen recombiner enclosure and verify there is no evidence of abnormal conditions.

SR 3.6.3.1.4 Perform a resistance to ground test for each heater 18 months phase.

ABWR TS 3.6-30 Design Control Document/Tier 2

25A5675AU Revision 7 Primary Containment Oxygen Concentration 3.6.3.2 3.6 CONTAINMENT SYSTEMS 3.6.3.2 Primary Containment Oxygen Concentration LCO 3.6.3.2 The primary containment oxygen concentration shall be < 3.5 volume percent.

APPLICABILITY: MODE 1 during the time period:

a. From 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after THERMAL POWER is > 15% RTP following startup, to

b. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing THERMAL POWER to < 15% RTP prior to the next scheduled reactor shutdown.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Primary containment A.1 Restore oxygen 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months oxygen concentration not concentration to within within limit. limit.

B. Required Action and B.1 Reduce THERMAL 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months associated Completion POWER to 15% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.3.2.1 Verify primary containment oxygen concentration is 7 days within limits.

ABWR TS 3.6-31 Design Control Document/Tier 2

25A5675AU Revision 7 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 irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months inoperable in MODE 1, 2, containment to OPERABLE or 3. status.

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

B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C. Secondary containment C.1 ---------------NOTE-------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated -------------------------------------

fuel assemblies in the Suspend movement of Immediately secondary containment, irradiated fuel assemblies during CORE in the secondary ALTERATIONS, or during containment.

OPDRVs.

AND C.2 Suspend CORE Immediately ALTERATIONS.

AND C.3 Initiate action to suspend Immediately OPDRVs.

ABWR TS 3.6-32 Design Control Document/Tier 2

25A5675AU Revision 7 Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 6.4 mm 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months water gauge.

SR 3.6.4.1.2 Verify all secondary containment equipment hatches 31 days are closed and sealed.

SR 3.6.4.1.3 Verify each secondary containment access door is 31 days closed, except when the access opening is being used for entry and exit, then at least one door shall be closed.

SR 3.6.4.1.4 Verify each standby gas treatment (SGT) subsystem 18 months on a will draw down the secondary containment to STAGGERED 6.4 mm water gauge vacuum in 120 seconds. TEST BASIS SR 3.6.4.1.5 Verify each SGT subsystem can maintain 6.4 mm 18 months on a water gauge vacuum in the secondary containment STAGGERED for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months at a flow rate 6800 m3/h. TEST BASIS ABWR TS 3.6-33 Design Control Document/Tier 2

25A5675AU Revision 7 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 irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

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

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

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

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

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more penetration A.1 Isolate the affected 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months flow paths with one SCIV penetration flow path by inoperable. use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND (continued)

ABWR TS 3.6-34 Design Control Document/Tier 2

25A5675AU Revision 7 SCIVs 3.6.4.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2 --------------NOTE------------

Valves and blind flanges in high radiation areas may be verified by use of administrative means.

Verify the affected Once per 31 days penetration flow path is isolated.

B. ------------NOTE------------ B.1 Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Only applicable to penetration flow path by penetration flow paths with use of at least one closed two isolation valves. and de-activated

automatic valve, closed manual valve, or blind One or more penetration flange.

flow paths with two SCIVs inoperable.

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

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

ABWR TS 3.6-35 Design Control Document/Tier 2

25A5675AU Revision 7 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 or B applicable.

not met during movement ----------------------------------

of irradiated fuel assemblies in the Suspend movement of Immediately secondary containment, irradiated fuel assemblies during CORE in the secondary ALTERATIONS, or during containment.

OPDRVs.

AND D.2 Suspend CORE Immediately ALTERATIONS.

AND D.3 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.2.1 ------------------------------NOTES-----------------------------

1. Valves and blind flanges in high radiation areas may be verified by use of administrative means.

2. Not required to be met for SCIVs that are open under administrative controls.

Verify each secondary containment isolation manual 31 days valve and blind flange that is required to be closed during accident conditions is closed.

SR 3.6.4.2.2 Verify the isolation time of each power operated and 92 days each automatic SCIV is within limits.

(continued)

ABWR TS 3.6-36 Design Control Document/Tier 2

25A5675AU Revision 7 SCIVs 3.6.4.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.6.4.2.3 Verify each automatic SCIV actuates to the isolation 18 months position on an actual or simulated actuation signal.

ABWR TS 3.6-37 Design Control Document/Tier 2

25A5675AU Revision 7 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 trains shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SGT subsystem A.1 Restore SGT train to 7 days inoperable. OPERABLE status.

B. Two SGT trains inoperable B.1 Restore one SGT train to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months in MODES 1, 2, or 3. OPERABLE status.

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

ABWR TS 3.6-38 Design Control Document/Tier 2

25A5675AU Revision 7 SGT System 3.6.4.3 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 irradiated fuel assemblies D.1 Place OPERABLE SGT Immediately in the secondary train in operation.

containment, during CORE ALTERATIONS, or during OR OPDRVs.

D.2.1 Suspend movement of Immediately irradiated fuel assemblies in secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to suspend Immediately OPDRVs.

E. Two SGT subsystems E.1 --------------NOTE------------

inoperable during LCO 3.0.3 is not movement of irradiated fuel applicable.

assemblies in the ----------------------------------

secondary containment, during CORE Suspend movement of Immediately ALTERATIONS, or during irradiated fuel assemblies OPDRVs. in secondary containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to suspend Immediately OPDRVs.

ABWR TS 3.6-39 Design Control Document/Tier 2

25A5675AU Revision 7 SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT train for 10 continuous hours 31 days with heaters operating.

SR 3.6.4.3.2 Perform required SGT filter testing in accordance In accordance with the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.6.4.3.3 Verify each SGT train actuates on an actual or 18 months simulated initiation signal.

SR 3.6.4.3.4 Verify each SGT filter cooler bypass damper can be 18 months opened and the fan started.

ABWR TS 3.6-40 Design Control Document/Tier 2

25A5675AU Revision 7 RCW/RSW System and UHS - Operating 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Operating LCO 3.7.1 Divisions A, B and C of the RCW/RSW System and the UHS shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RCW pump and/or A.1 Restore pump(s) and/or 14 days one RSW pump and/or one heat exchanger and/or RCW/RSW heat exchanger UHS [spray network] to and/or one [spray network] OPERABLE status.

in the UHS inoperable in a single division.

B. One RCW/RSW division B.1 Declare associated Immediately inoperable for reasons supported required other than Condition A. feature(s) inoperable and enter applicable OR Conditions and Required Actions of the LCOs for Both [spray networks] in the inoperable required one UHS division feature(s).

inoperable.

AND B.2 Initiate action to restore Immediately RCW/RSW division or UHS [spray networks] to OPERABLE status.

(continued)

ABWR TS 3.7-1 Design Control Document/Tier 2

25A5675AU Revision 7 RCW/RSW System and UHS - Operating 3.7.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Condition A exists in two or C.1 Restore one inoperable 7 days more RCW/RSW or UHS RCW/RSW or UHS [spray

[spray network] divisions. network] division to OPERABLE status.

AND C.2 Restore two inoperable 14 days RCW/RSW or UHS [spray network] divisions to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B or C AND not met.

D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months OR Two or more RCW/RSW divisions inoperable for reasons other than Condition C.

OR UHS inoperable.

OR Two or more UHS [spray network] divisions inoperable for reasons other than Condition C.

ABWR TS 3.7-2 Design Control Document/Tier 2

25A5675AU Revision 7 RCW/RSW System and UHS - Operating 3.7.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.1.1 Verify the water level of each UHS [spray pond] is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

[ ] m.

SR 3.7.1.2 Verify the water level in each RSW pump well of the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months intake structure is [ ] m.

SR 3.7.1.3 Verify the RSW water temperature at the inlet to the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RCW/RSW heat exchangers is [33.3]°C.

SR 3.7.1.4 -------------------------------NOTE------------------------------

Isolation of flow to individual components does not render RCW/RSW System inoperable.

Verify each RCW/RSW division and associated UHS 31 days

[spray network] division manual, power operated, and automatic valve in the flow path servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.1.5 Verify each RCW/RSW division and associated UHS 18 months

[spray network] division actuate on an actual or simulated initiation signal.

ABWR TS 3.7-3 Design Control Document/Tier 2

25A5675AU Revision 7 RCW/RSW System and UHS - Shutdown 3.7.2 3.7 PLANT SYSTEMS 3.7.2 Reactor Building Cooling Water (RCW) System, Reactor Service Water (RSW) System and Ultimate Heat Sink (UHS) - Shutdown LCO 3.7.2 Three RCW/RSW divisions and UHS shall be OPERABLE.

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

One RCW/RSW division may be inoperable in MODE 5, and after 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months from initial entry into MODE 4 from MODE 3.

APPLICABILITY: MODE 4, MODE 5 except with the reactor cavity to dryer/separator storage pool gate removed and water level 7.0 m over the top of the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One RCW pump and/or A.1 Restore pump(s) and/or 14 days one RSW pump and/or one heat exchanger and/or RCW/RSW heat exchanger UHS [spray network] to and/or one [spray network] OPERABLE status.

in the UHS in one division inoperable.

B. Condition A exists in two or B.1 Restore one inoperable 7 days more RCW/RSW or UHS RCW/RSW or UHS [spray

[spray network] divisions. network] division to OPERABLE status.

AND B.2 Restore two inoperable 14 days RCW/RSW or UHS [spray network] divisions to OPERABLE status.

(continued)

ABWR TS 3.7-4 Design Control Document/Tier 2

25A5675AU Revision 7 RCW/RSW System and UHS - Shutdown 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. One or more required C.1 Enter applicable Immediately RCW/RSW or UHS [spray Conditions and Required network] divisions Actions of LCO 3.8.11, inoperable for reasons AC Sources - Shutdown other then Condition A or B. (Low Water Level) for diesel generator(s) made OR inoperable by RCW/RSW.

UHS inoperable. AND OR C.2 Enter applicable Immediately Conditions and Required Required Action and Actions of LCO 3.4.8, associated Completion Residual Heat Removal Time of Condition A or B (RHR) - MODE 4, or not met. LCO 3.9.8, RHR - Low Water Level, for RHR shutdown cooling made inoperable by RCW/RSW.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.2.1 Verify the water level of each UHS [spray pond] is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

[ ] m.

SR 3.7.2.2 Verify the water level in each RSW pump well of the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months intake structure is [ ] m.

SR 3.7.2.3 Verify the RSW water temperature at the inlet to the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RCW/RSW heat exchangers is [33.3]°C.

(continued)

ABWR TS 3.7-5 Design Control Document/Tier 2

25A5675AU Revision 7 RCW/RSW System and UHS - Shutdown 3.7.2 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.2.4 -------------------------------NOTE----------------------------

Isolation of flow to individual components does not render RCW/RSW System inoperable.

Verify each RCW/RSW division and associated UHS 31 days

[spray network] division manual, power operated, and automatic valve in the flow path servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position, is in the correct position.

SR 3.7.2.5 Verify each RCW/RSW division and associated UHS 18 months

[spray network] division actuate on an actual or simulated initiation signal.

ABWR TS 3.7-6 Design Control Document/Tier 2

25A5675AU Revision 7 RCW/RSW System and UHS - Refueling 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Reactor Building Cooling Water (RCW) System and Reactor Service Water (RSW)

System and Ultimate Heat Sink (UHS) - Refueling LCO 3.7.3 One RCW/RSW division and UHS shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor cavity to dryer/separator storage pool gate removed and water level 7.0 m over the top of the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No RCW/RSW division A.1 Enter applicable Immediately OPERABLE. Conditions and Required Actions of LCO 3.8.2, AC OR Sources-Refueling for the diesel generator made UHS inoperable. inoperable by RCW/RSW.

OR AND Associated divisional UHS A.2 Enter applicable Immediately

[spray networks] Conditions and Required inoperable. Actions of LCO 3.9.7, RHR-High Water Level, for RHR-Shutdown Cooling made inoperable by RCW/RSW.

ABWR TS 3.7-7 Design Control Document/Tier 2

25A5675AU Revision 7 RCW/RSW System and UHS - Refueling 3.7.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify the water level of each UHS [spray pond] is 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

[ ] m.

SR 3.7.3.2 Verify the water level in each RSW pump well of the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months intake structure is [ ] m.

SR 3.7.3.3 Verify the RSW water temperature at the inlet to the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months RCW/RSW heat exchangers is [33.3]°C.

SR 3.7.3.4 -------------------------------NOTE----------------------------

Isolation of flow to individual components does not render RCW/RSW System inoperable.

Verify RCW/RSW division and associated UHS 31 days

[spray network] division manual, power operated, and automatic valve in the flow path servicing safety related systems or components, that is not locked, sealed, or otherwise secured in position is in the correct position.

SR 3.7.3.5 Verify each RCW/RSW division and associated UHS 18 months

[spray network] division actuate on an actual or simulated initiation signal.

ABWR TS 3.7-8 Design Control Document/Tier 2

25A5675AU Revision 7 CRHA EF System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Habitability Area (CRHA) - Emergency Filtration (EF) System LCO 3.7.4 Two divisions of the CRHA EF Systems shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One EF division inoperable. A.1 Restore EF division to 7 days OPERABLE status.

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

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

ABWR TS 3.7-9 Design Control Document/Tier 2

25A5675AU Revision 7 CRHA EF System 3.7.4 ACTIONS (continued)

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

associated Completion LCO 3.0.3 is not applicable.

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

met during movement of irradiated fuel assemblies C.1 Place OPERABLE EF Immediately in the secondary division in standby mode.

containment, during CORE ALTERATIONS, or during OR OPDRVs.

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

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

AND C.2.3 Initiate action to suspend Immediately OPDRVs.

D. Two EF divisions D.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3.

(continued)

ABWR TS 3.7-10 Design Control Document/Tier 2

25A5675AU Revision 7 CRHA EF System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two EF divisions --------------------NOTE-------------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel ------------------------------------------------

assemblies in the secondary containment, E.1 Suspend movement of Immediately during CORE irradiated fuel assemblies ALTERATIONS, or during in the secondary OPDRVs. containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each EF division for 10 continuous hours 31 days with the heaters operating.

SR 3.7.4.2 Perform required EF filter testing in accordance with In accordance the Ventilation Filter Testing Program (VFTP). with the VFTP SR 3.7.4.3 Verify each EF division actuates on an actual or 18 months simulated initiation signal.

SR 3.7.4.4 Verify each EF division can maintain a positive 18 months on a pressure of 3.2 mm water gauge relative to the STAGGERED atmosphere during the isolation mode of operation at TEST BASIS a flow rate of 360 m3/h.

ABWR TS 3.7-11 Design Control Document/Tier 2

25A5675AU Revision 7 Control Room AC System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Control Room Habitability Area (CRHA) - Air Conditioning (AC) System LCO 3.7.5 Two divisions of the CRHA AC System shall be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC division A.1 Restore AC division to 30 days inoperable. OPERABLE status.

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

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

associated Completion LCO 3.0.3 is not applicable.

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

met during movement of irradiated fuel assemblies C.1 Place OPERABLE AC Immediately in the secondary division in operation.

containment, during CORE ALTERATIONS, or during OR OPDRVs.

(continued)

ABWR TS 3.7-12 Design Control Document/Tier 2

25A5675AU Revision 7 Control Room AC System 3.7.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment.

AND C.2.2 Suspend CORE Immediately ALTERATIONS.

AND C.2.3 Initiate action to suspend Immediately OPDRVs.

D. Two AC divisions D.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3.

E. Two AC divisions --------------------NOTE-------------------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel ------------------------------------------------

assemblies in the secondary containment, E.1 Suspend movement of Immediately during CORE irradiated fuel assemblies ALTERATIONS, or during in the secondary OPDRVs. containment.

AND E.2 Suspend CORE Immediately ALTERATIONS.

AND E.3 Initiate action to suspend Immediately OPDRVs.

ABWR TS 3.7-13 Design Control Document/Tier 2

25A5675AU Revision 7 Control Room AC System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.1 Verify each CRHA AC division has the capability to 18 months remove the assumed heat load.

SR 3.7.5.2 Verify each CRHA AC division actuates on an actual 18 months or simulated initiation signal.

ABWR TS 3.7-14 Design Control Document/Tier 2

25A5675AU Revision 7 Main Condenser Offgas 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Main Condenser Offgas LCO 3.7.6 The gross gamma activity rate of the noble gases measured at the offgas recombiner effluent shall be 14.8 GBq/second after decay of 30 minutes.

APPLICABILITY: MODE 1, MODES 2 and 3 with any main steam line not isolated and steam jet air ejector (SJAE) in operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Gross gamma activity rate A.1 Restore gross gamma 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months of the noble gases not activity rate of the noble within limit. gases to within limit.

B. Required Action and B.1 Isolate all main steam 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion lines.

Time not met.

OR B.2 Isolate SJAE. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months OR B.3.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND B.3.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ABWR TS 3.7-15 Design Control Document/Tier 2

25A5675AU Revision 7 Main Condenser Offgas 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 -------------------------------NOTE------------------------------

Not required to be performed until 31 days after any main steam line not isolated and SJAE in operation.

Verify the gross gamma activity rate of the noble 31 days gases is 14.8 GBq/second after decay of 30 minutes. AND Once within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after a 50% increase in the nominal steady state fission gas release after factoring out increases due to changes in THERMAL POWER level ABWR TS 3.7-16 Design Control Document/Tier 2

25A5675AU Revision 7 Main Turbine Bypass System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Main Turbine Bypass System LCO 3.7.7 The Main Turbine Bypass System shall be OPERABLE.

OR LCO 3.2.2, MINIMUM CRITICAL POWER RATIO (MCPR), limits for an inoperable Main Turbine Bypass System, as specified in the Core Operating Limits Report (COLR), are made applicable.

APPLICABILITY: THERMAL POWER 40% RTP.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Satisfy the requirements 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months not met or Main Turbine of the LCO or restore Bypass System inoperable. Main Turbine Bypass System to OPERABLE status.

B. Required Action and B.1 Reduce THERMAL 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion POWER to 40% RTP.

Time not met.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Perform bypass valve opening test to 10% position 31 days for each turbine bypass valve.

(continued)

ABWR TS 3.7-17 Design Control Document/Tier 2

25A5675AU Revision 7 Main Turbine Bypass System 3.7.7 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.7.2 Perform a system functional test. 18 months SR 3.7.7.3 Verify the TURBINE BYPASS SYSTEM RESPONSE 18 months TIME is within limits.

ABWR TS 3.7-18 Design Control Document/Tier 2

25A5675AU Revision 7 Fuel Pool Water Level 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Fuel Pool Water Level LCO 3.7.8 The fuel pool water level shall be 7.0 m over the top of irradiated fuel assemblies seated in the spent fuel storage pool.

APPLICABILITY: During movement of irradiated fuel assemblies in the associated fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel pool water level not A.1 --------------NOTE------------

within limit. LCO 3.0.3 is not applicable.

Suspend movement of Immediately irradiated fuel assemblies in the associated fuel storage pool(s).

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1 Verify the fuel pool water level is 7.0 m over the top 7 days of irradiated fuel assemblies seated in the storage racks.

ABWR TS 3.7-19 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 3.8 ELECTRICAL POWER SYSTEMS 3.8.1 AC Sources - Operating LCO 3.8.1 The following AC electrical power sources shall be OPERABLE:

a. Two qualified circuits between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and

b. Three diesel generators (DGs).

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One of two offsite AC A.1 Verify affected ESF bus is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power sources to one ESF powered from the other bus inoperable. operable offsite AC AND circuit.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Verify the CTG is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months functional by verifying the CTG starts and achieves AND steady state voltage and frequency within Once per 7 days 2 minutes. thereafter AND A.3 Verify the CTG circuit 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months breakers are aligned to the affected ESF bus. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND (continued)

ABWR TS 3.8-1 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.4 Restore inoperable offsite 30 days AC power to affected ESF bus.

B. One required offsite circuit B.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE required offsite circuit. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND B.2 Declare required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months from feature(s) with no power discovery of no available from an power available OPERABLE offsite circuit from an OPERABLE inoperable when the offsite circuit to one redundant required division concurrent feature(s) are inoperable. with inoperability of redundant required feature(s)

AND B.3 Verify the combustion 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months turbine generator (CTG) is functional by verifying the CTG starts and achieves steady state voltage and frequency within 2 minutes.

AND B.4 Verify the CTG circuit 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months breakers are capable of being aligned to each of AND the ESF buses.

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

ABWR TS 3.8-2 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.5 Restore required offsite 14 days circuit to OPERABLE status. AND 1 day from discovery of two divisions with no power available from an OPERABLE offsite circuit AND 15 days from discovery of failure to meet the LCO C. ------------NOTE------------ C.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Required Action C.3.1 OPERABLE required or C.3.2 shall be completed offsite circuit(s). AND if this Condition is entered.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter One required DG inoperable. AND C.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s), supported by discovery of the inoperable DG, Condition C inoperable when the concurrent with redundant required inoperability of features(s) are redundant required inoperable. feature(s)

AND C.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR (continued)

ABWR TS 3.8-3 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.3.2 Perform SR 3.8.1.2 for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s).

AND C.4 Verify the combustion 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months turbine generator (CTG) is functional by verifying the CTG starts and achieves steady state voltage and frequency within 2 minutes.

AND C.5 Verify the CTG circuit 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months breakers are aligned to the ESF bus associated AND with the inoperable DG.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND C.6 Restore required DG to 14 days OPERABLE status.

AND 15 days from discovery of failure to meet the LCO D. Two required offsite circuits D.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from inoperable. feature(s) inoperable discovery of when the redundant Condition D required feature(s) are concurrent with inoperable. inoperability of redundant required feature(s)

AND D.2 Restore one required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months offsite circuit to OPERABLE status.

(continued)

ABWR TS 3.8-4 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One required offsite circuit --------------------NOTE-------------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.9, AND Distribution Systems - Operating, when Condition D is entered with no One required DG required AC power source to one inoperable. division.

E.1 Verify the combustion 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months turbine generator (CTG) is functional by verifying the CTG starts and achieves steady state voltage and frequency within 2 minutes.

AND E.2 Verify the CTG circuit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months breakers are aligned to the ESF bus associated AND with the inoperable DG.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND E.3.1 Restore required offsite 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months circuit to OPERABLE status.

OR E.3.2 Restore required DG to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months OPERABLE status.

(continued)

ABWR TS 3.8-5 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two required DGs F.1 Verify the combustion 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. turbine generator (CTG) is functional by verifying the CTG starts and achieves steady state voltage and frequency within 2 minutes.

AND F.2 Verify the CTG circuit 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months breakers are aligned to one ESF bus associated AND with an inoperable DG and capable of being Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months aligned to the other ESF thereafter bus associated with an inoperable DG.

AND F.3 Restore one required DG 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to OPERABLE status.

G. Required Action and G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A, B, C, AND D, E or F not met.

G.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months H. Three or more required AC H.1 Enter LCO 3.0.3. Immediately sources inoperable.

ABWR TS 3.8-6 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated 7 days power availability for each required offsite circuit.

SR 3.8.1.2 ------------------------------NOTES-----------------------------

1. Performance of SR 3.8.1.7 satisfies this SR.

2. All DG starts may be preceded by an engine prelube period and followed by a warmup period prior to loading.

3. A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR as recommended by the manufacturer. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met.

Verify each DG starts from standby conditions and As specified in achieves steady state voltage [6210] V and Table 3.8.1-1

[7590] V and frequency [58.8] Hz and

[61.2] Hz.

SR 3.8.1.3 ------------------------------NOTES-----------------------------

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by, and immediately follow, without shutdown, a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each DG is synchronized and loaded and As specified in operates for 60 minutes at a load 5000 kW and Table 3.8.1-1

[ ] kW.

(continued)

ABWR TS 3.8-7 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.4 Verify each day tank contains [ ] liters of fuel oil. 31 days SR 3.8.1.5 Check for and remove accumulated water from each 31 days day tank.

SR 3.8.1.6 Verify the fuel oil transfer system operates to 92 days automatically transfer fuel oil from the storage tank to the day tank.

SR 3.8.1.7 -------------------------------NOTE------------------------------

All DG starts may be preceded by an engine prelube period.

Verify each DG starts from standby condition and 184 days achieves, in 20 seconds, voltage [6210] V and

[7590] V and frequency [58.8] Hz and

[61.2] Hz.

SR 3.8.1.8 ------------------------------NOTES-----------------------------

1. This Surveillance shall not be performed in MODE 1 or 2.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify manual transfer of the [unit power supply] from 18 months the normal offsite circuit to each required alternate offsite circuit.

(continued)

ABWR TS 3.8-8 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.9 ------------------------------NOTES---------------------------

1. This Surveillance shall not be performed in MODE 1 or 2.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG operating at a power factor 0.9 18 months rejects a load 540 kW for Division 1 and 1400 kW for Divisions 2 and 3, and:

a. Following load rejection, the frequency is

[ ] Hz;

b. Within 3 seconds following load rejection, the voltage is [6210] V and [7590] V; and

c. Within 3 seconds following load rejection, the frequency is 58.8 Hz and 61.2 Hz.

SR 3.8.1.10 ------------------------------NOTES-----------------------------

1. This Surveillance shall not be performed in MODE 1 or 2.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG operating at a power factor 0.9 18 months does not trip and voltage is maintained [ ]V during and following a load rejection of a load

[5000] V and [ ] kW.

(continued)

ABWR TS 3.8-9 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.11 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1, 2, or 3.

3. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated loss of offsite power 18 months signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 20 seconds,

2. sequentially energizes auto-connected shutdown loads,

3. maintains steady state voltage

[6210] V and [7590] V,

4. maintains steady state frequency

[58.8] Hz and [61.2] Hz, and

5. supplies permanently connected and auto-connected shutdown loads for 5 minutes.

(continued)

ABWR TS 3.8-10 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.12 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1 or 2.

3. Credit may be taken for unplanned events that satisfy this SR.

Verify on an actual or simulated Emergency Core 18 months Cooling System (ECCS) initiation signal each DG auto-starts from standby condition and:

a. In 20 seconds after auto-start and during tests, achieves voltage [6210] V and

[7590] V;

b. In 20 seconds after auto-start and during tests, achieves frequency [58.8] Hz and

[61.2] Hz;

c. Operates for 5 minutes;

d. Permanently connected loads remain energized from the offsite power system; and

e. Emergency loads are sequentially energized from the offsite power system.

(continued)

ABWR TS 3.8-11 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.13 ------------------------------NOTES-----------------------------

1. This Surveillance shall not be performed in MODE 1, 2, or 3.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify each DGs automatic trips are bypassed on 18 months actual or simulated loss of voltage signal on the emergency bus concurrent with an actual or simulated ECCS initiation signal except:

a. Engine overspeed; and

b. Generator differential current.

SR 3.8.1.14 ------------------------------NOTES-----------------------------

1. Momentary transients outside the load and power factor ranges do not invalidate this test.

2. This Surveillance shall not be performed in MODE 1 or 2.

3. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG operating at a power factor 0.9, 18 months operates for 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:

a. For 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded, 5225 kW and 5500 kW; and

b. For the remaining hours of the test loaded 5000 kW and [ ].

(continued)

ABWR TS 3.8-12 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.15 ------------------------------NOTES-----------------------------

1. This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months loaded 5225 kW and 5500 kW.

Momentary transients outside of load range do not invalidate this test.

2. All DG starts may be preceded by an engine prelube period.

Verify each DG starts and achieves, in 20 seconds, 18 months voltage [6210] V and [7590] V and frequency

[58.8] Hz and [61.2] Hz.

SR 3.8.1.16 ------------------------------NOTES-----------------------------

1. This Surveillance shall not be performed in MODE 1, 2, or 3.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify each DG: 18 months

a. Synchronizes with offsite power source while loaded with emergency loads upon a simulated restoration of offsite power;

b. Transfers loads to offsite power source; and

c. Returns to ready-to-load operation.

(continued)

ABWR TS 3.8-13 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.17 ------------------------------NOTES-----------------------------

1. This Surveillance shall not be performed in MODE 1, 2, or 3.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify, with a DG operating in test mode and 18 months connected to its bus, an actual or simulated ECCS initiation signal overrides the test mode by:

a. Returning DG to ready-to-load operation; and

b. Automatically energizing the emergency load from offsite power.

SR 3.8.1.18 ------------------------------NOTES-----------------------------

1. This Surveillance shall not be performed in MODE 1, 2, or 3.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify interval between each sequenced load block is 18 months within +/- 10% of design interval for each load sequencer timer.

(continued)

ABWR TS 3.8-14 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.19 ------------------------------NOTES-----------------------------

1. All DG starts may be preceded by an engine prelube period.

2. This Surveillance shall not be performed in MODE 1, 2, or 3.

3. Credit may be taken for unplanned events that satisfy this SR.

Verify, on an actual or simulated loss of offsite power 18 months signal in conjunction with an actual or simulated ECCS initiation signal:

a. De-energization of emergency buses;

b. Load shedding from emergency buses; and

c. DG auto-starts from standby condition and:

1. energizes permanently connected loads in 20 seconds,

2. sequentially energizes auto-connected emergency loads,

3. achieves steady state voltage [6210] V and [7590] V,

4. achieves steady state frequency

[58.8] Hz and [61.2] Hz, and

5. supplies permanently connected and auto-connected emergency loads for 5 minutes.

(continued)

ABWR TS 3.8-15 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.1.20 -------------------------------NOTE------------------------------

All DG starts may be preceded by an engine prelube period.

Verify, when started simultaneously from standby 10 years during condition, each Division 1, 2, and 3 DG achieves, in shutdown 20 seconds, voltage [6210] V and [7590] V and frequency [58.8] Hz and [61.2] Hz.

ABWR TS 3.8-16 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Operating 3.8.1 Table 3.8.1-1 (page 1 of 1)

Diesel Generator Test Schedule NUMBER OF FAILURES IN LAST 25 VALID TESTS (a) FREQUENCY 3 31 days 4 7 days(b) (but 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )

(a) Criteria for determining number of failures and valid tests shall be in accordance with Regulatory Position C.2.1 of Regulatory Guide 1.9, Revision 3, where the number of tests and failures is determined on a per DG basis.

(b) This test frequency shall be maintained until seven consecutive failure free starts from standby conditions and load and run tests have been performed. This is consistent with Regulatory Position [ ], of Regulatory Guide 1.9, Revision 3. If, subsequent to the 7 failure free tests, 1 or more additional failures occur such that there are again 4 or more failures in the last 25 tests, the testing interval shall again be reduced as noted above and maintained until 7 consecutive failure free tests have been performed.

ABWR TS 3.8-17 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Refueling 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources - Refueling LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10, Distribution Systems - Shutdown; and

b. One or more diesel generator(s) (DG) capable of supplying at least one division of the required OPERABLE features via the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.10.

APPLICABILITY: MODE 5 with water level in the refueling cavity 7.0 meters above the reactor pressure vessel flange, or during movement of irradiated fuel assemblies in secondary containment.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required offsite circuit --------------------NOTE-------------------

inoperable. Enter applicable Condition and Required Actions of LCO 3.8.10, with one required division de-energized as a result of Condition B.

A.1 Initiate action to restore Immediately required offsite circuit to OPERABLE status supplying power to all required ESF buses.

AND (continued)

ABWR TS 3.8-18 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Refueling 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.1.2 Declare affected required Immediately feature(s) with no power available from an OPERABLE offsite circuit inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

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

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

AND A.2.4 Initiate action to restore Immediately required offsite circuit to OPERABLE status supplying power to all required ESF buses.

B. One or more required DGs B.1 Suspend CORE Immediately inoperable. ALTERATIONS.

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

AND (continued)

ABWR TS 3.8-19 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Refueling 3.8.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to suspend Immediately OPDRVs.

AND B.4 Initiate action to restore Immediately required DG(s) to OPERABLE status.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 -------------------------------NOTE------------------------------

1. SR 3.8.1.3 is only required when more than the minimum number of AC sources required by LCO 3.8.2 are available, but at least every six months.

2. SR 3.8.1.12, SR 3.8.1.13, SR 3.8.1.17, and SR 3.8.1.19 are only required when the associated ECCS loads are required to be OPERABLE.

For AC sources required to be OPERABLE, the SRs In accordance of Specification 3.8.1, except SR 3.8.1.8, with applicable SR 3.8.1.14, and SR 3.8.1.20 are applicable. SRs ABWR TS 3.8-20 Design Control Document/Tier 2

25A5675AU Revision 7 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air LCO 3.8.3 The stored diesel fuel oil, lube oil, and starting air subsystem shall be within limits for each required diesel generator (DG).

APPLICABILITY: When associated DG is required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each DG.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with fuel A.1 Restore fuel oil level to 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months oil level < [ ] liters and within limits.

[ ] liters in storage tank.

B. One or more DGs with lube B.1 Restore lube oil inventory 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months oil inventory < [ ] liters and to within limits.

[ ] liters.

C. One or more DGs with C.1 Restore fuel oil total 7 days stored fuel oil total particulates to within limit.

particulates not within limit.

D. One or more DGs with new D.1 Restore stored fuel oil 30 days fuel oil properties not within properties to within limits.

limits.

(continued)

ABWR TS 3.8-21 Design Control Document/Tier 2

25A5675AU Revision 7 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. One or more DGs with E.1 Restore starting air 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months starting air receiver receiver pressure to pressure < [ ] kPaG and [ ] kPaG.

[ ] kPaG.

F. Required Actions and F.1 Declare associated DG Immediately associated Completion inoperable.

Time not met.

OR One or more DGs with diesel fuel oil, lube oil, or starting air subsystem not within limits for reasons other than Condition A, B, C, D, or E.

ABWR TS 3.8-22 Design Control Document/Tier 2

25A5675AU Revision 7 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.3.1 Verify each fuel oil storage tank contains [ ] liters. 31 days SR 3.8.3.2 Verify lube oil inventory for each DG is [ ] liters. 31 days SR 3.8.3.3 Verify fuel oil properties of new and stored fuel oil In accordance are tested in accordance with, and maintained within with the Diesel the limits of, the Diesel Fuel Oil Testing Program. Fuel Oil Testing Program SR 3.8.3.4 Verify each DG air start receiver pressure is 31 days

[ ] kPaG.

SR 3.8.3.5 Check for and remove accumulated water from each 31 days fuel oil storage tank.

SR 3.8.3.6 For each fuel oil storage tank: 10 years

a. Drain the fuel oil;

b. Remove the sediment; and

c. Clean the tank.

ABWR TS 3.8-23 Design Control Document/Tier 2

25A5675AU Revision 7 DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - Operating LCO 3.8.4 The Division I, Division II, Division III, and Division IV DC electrical power subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One DC electrical power A.1 Determine OPERABLE 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months subsystem (either DC electrical subsystems Division I, II, or III) are not inoperable due to inoperable. common cause failure.

AND A.2 Declare affected required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months features inoperable.

AND A.3 Verify the combustion 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months turbine generator (CTG) is functional by verifying the CTG starts and achieves steady state voltage and frequency within 2 minutes.

AND A.4 Verify the CTG circuit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months breakers are capable of being aligned to the two AND unaffected ESF buses.

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

ABWR TS 3.8-24 Design Control Document/Tier 2

25A5675AU Revision 7 DC Sources - Operating 3.8.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.5 Restore inoperable DC 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months electrical power subsystem to OPERABLE status.

B. Division IV DC electrical B.1 Determine OPERABLE 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power subsystem DC electrical subsystems inoperable. are not inoperable due to common cause failure.

AND B.2 Declare affected required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months features inoperable.

C. One DC electrical power C.1 Restore inoperable DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months subsystem (either electrical power Division I, II, or III) subsystem (other than inoperable. Division IV) to OPERABLE status.

AND OR Division IV DC electrical power subsystem C.2 Restore Division IV DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inoperable. electrical power subsystem to OPERABLE status.

D. Required Action and D.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time not met. AND D.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ABWR TS 3.8-25 Design Control Document/Tier 2

25A5675AU Revision 7 DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is [ ] V on float 7 days charge.

SR 3.8.4.2 Verify no visible corrosion at terminals and 92 days connectors.

OR Verify connection resistance is

[ ] ohms for inter-cell connections,

[ ] ohms for inter-rack connections,

[ ] ohms for inter-tier connections, and

[ ] ohms for terminal connections.

SR 3.8.4.3 Verify cells, cell plates, and battery racks show no 12 months visual indication of physical damage or abnormal deterioration.

SR 3.8.4.4 Remove visible corrosion, and verify cell to cell and 12 months terminal connections are coated with anti-corrosion material.

SR 3.8.4.5 Verify connection resistance is 12 months

[ ] ohms for inter-cell connections,

[ ] ohms for inter-rack connections,

[ ] ohms for inter-tier connections, and

[ ] ohms for terminal connections.

SR 3.8.4.6 ------------------------------NOTES-----------------------------

1. This Surveillance shall not be performed in MODE 1, 2, or 3.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify each required battery charger supplies 18 months

[ ] amps at 125 V for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(continued)

ABWR TS 3.8-26 Design Control Document/Tier 2

25A5675AU Revision 7 DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.4.7 ------------------------------NOTES-----------------------------

1. The modified performance discharge test in SR 3.8.4.8 may be performed every 60 months in lieu of a service test in SR 3.8.4.7.

2. This Surveillance shall not be performed in MODE 1, 2, or 3.

3. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is adequate to supply, and 18 months maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.

SR 3.8.4.8 ------------------------------NOTES-----------------------------

1. This Surveillance shall not be performed in MODE 1, 2, or 3.

2. Credit may be taken for unplanned events that satisfy this SR.

Verify battery capacity is 80% of the 60 months manufacturers rating when subjected to a performance discharge test or a modified AND performance discharge test.

NOTE--------

Only applicable when battery shows degradation or has reached 85%

of expected life 12 months ABWR TS 3.8-27 Design Control Document/Tier 2

25A5675AU Revision 7 DC Sources - Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources - Shutdown LCO 3.8.5 DC electrical power subsystem(s) shall be OPERABLE to support the required OPERABLE features and the electrical power distribution subsystem(s) required by LCO 3.8.10, Distribution Systems - Shutdown.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required DC A.1 Declare affected required Immediately electrical power feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

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

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

AND A.2.4 Initiate action to restore Immediately required DC electrical power subsystems to OPERABLE status.

ABWR TS 3.8-28 Design Control Document/Tier 2

25A5675AU Revision 7 DC Sources - Shutdown 3.8.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 For DC sources required to be OPERABLE the In accordance following SRs are applicable: with applicable SRs SR 3.8.4.1 SR 3.8.4.4 SR 3.8.4.7 SR 3.8.4.2 SR 3.8.4.5 SR 3.8.4.8.

SR 3.8.4.3 SR 3.8.4.6 ABWR TS 3.8-29 Design Control Document/Tier 2

25A5675AU Revision 7 Battery Cell Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters LCO 3.8.6 Battery cell parameters for the Division 1, 2, 3, and 4 batteries shall be within the Category A and B limits of Table 3.8.6-1.

APPLICABILITY: When associated DC electrical power subsystems are required to be OPERABLE.

ACTIONS

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

Separate Condition entry is allowed for each battery.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more batteries with A.1 Verify pilot cells 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months one or more battery cell electrolyte level and float parameters not within voltage meet Table 3.8.6-limits. 1 Category C limits.

AND A.2 Verify battery cell 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months parameters meet Table 3.8.6-1 Category C limits.

AND A.3 Restore battery cell 31 days parameters to Category A and B limits of Table 3.8.6-1.

(continued)

ABWR TS 3.8-30 Design Control Document/Tier 2

25A5675AU Revision 7 Battery Cell Parameters 3.8.6 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Declare associated Immediately associated Completion battery inoperable.

Time of Condition A not met.

OR One or more batteries with average electrolyte temperature of the representative cells < 10°C.

OR One or more batteries with one or more battery cell parameters not within Category C limits.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.6.1 Verify battery cell parameters meet Table 3.8.6-1 7 days Category A limits.

(continued)

ABWR TS 3.8-31 Design Control Document/Tier 2

25A5675AU Revision 7 Battery Cell Parameters 3.8.6 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8.6.2 Verify battery cell parameters meet Table 3.8.6-1 92 days Category B limits.

AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after battery discharge

<[ ]V AND Once within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after battery overcharge

>[ ]V SR 3.8.6.3 Verify average electrolyte temperature of 92 days representative cells is 10°C.

ABWR TS 3.8-32 Design Control Document/Tier 2

25A5675AU Revision 7 Battery Cell Parameters 3.8.6 Table 3.8.6-1 (page 1 of 1)

Battery Cell Parameter Requirements CATEGORY A:

LIMITS FOR EACH CATEGORY B: CATEGORY C:

DESIGNATED PILOT LIMITS FOR EACH LIMITS FOR EACH PARAMETER CELL CONNECTED CELL CONNECTED CELL Electrolyte Level > Minimum level > Minimum level Above top of plates, indication mark, and indication mark, and and not overflowing 6 mm above 6 mm above maximum level maximum level indication mark(a) indication mark(a)

Float Voltage 2.13 V 2.13 V > 2.07 V Specific Gravity (b)(c) [ ] [ ] Not more than 0.020 below average of all AND connected cells Average of all AND connected cells

>[ ] Average of all connected cells

[ ]

(a) It is acceptable for the electrolyte level to temporarily increase above the specified maximum level during equalizing charges provided it is not overflowing.

(b) Corrected for electrolyte temperature and level.

(c) Or battery charging current is < [ ] amps when on float charge. This is acceptable only during a maximum of [ ] days following a battery recharge.

ABWR TS 3.8-33 Design Control Document/Tier 2

25A5675AU Revision 7 Inverters - Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters - Operating LCO 3.8.7 The Division I, Division II, Division III, and Division IV inverters shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One inverter inoperable. --------------------NOTE-------------------

Immediately enter applicable Conditions and Required Actions of LCO 3.8.9 Distribution Systems -

Operating for de-energized AC Vital buses.

A.1 Restore inverters to 7 days OPERABLE status.

AND A.2 Declare affected required 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months features inoperable.

(continued)

ABWR TS 3.8-34 Design Control Document/Tier 2

25A5675AU Revision 7 Inverters - Operating 3.8.7 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One inverter (either --------------------NOTE-------------------

Division I, II, or III) Immediately enter applicable inoperable. Conditions and Required Actions of LCO 3.8.9 Distribution Systems -

AND Operating, for de-energized AC Vital buses.

Division IV inverter ------------------------------------------------

inoperable.

B.1 Restore inoperable 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inverter (other than Division IV) to OPERABLE status.

OR B.2 Restore Division IV 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months inverter to OPERABLE status.

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

C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.7.1 Verify correct inverter voltage, frequency, and 7 days alignment to required AC vital buses.

ABWR TS 3.8-35 Design Control Document/Tier 2

25A5675AU Revision 7 Inverters - Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters - Shutdown LCO 3.8.8 Inverter(s) shall be OPERABLE to support required OPERABLE features and the onsite Class 1E AC vital bus electrical power distribution subsystem(s) required by LCO 3.8.10, Distribution Systems - Shutdown.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare affected required Immediately inverters inoperable. feature(s) inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

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

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

AND A.2.4 Initiate action to restore Immediately required inverters to OPERABLE status.

ABWR TS 3.8-36 Design Control Document/Tier 2

25A5675AU Revision 7 Inverters - Shutdown 3.8.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct inverter voltage, frequency, and 7 days alignments to required AC vital buses.

ABWR TS 3.8-37 Design Control Document/Tier 2

25A5675AU Revision 7 Distribution Systems - Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems - Operating LCO 3.8.9 Division I, II, and III AC, Divisions I, II, III, and IV DC, and Divisions I, II, III, and IV AC vital bus electrical power distribution subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC electrical power A.1 Declare affected required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months distribution subsystem features inoperable.

inoperable.

AND A.2 Verify the combustion 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months turbine generator (CTG) is functional by verifying the CTG starts and achieves steady state voltage and frequency within 2 minutes.

AND A.3 Verify the CTG circuit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months breakers are capable of being aligned to the AND OPERABLE 6.9 kV essential AC buses. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.4 Restore AC electrical 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power distribution subsystem to OPERABLE AND status.

7 days from discovery of failure to meet LCO (continued)

ABWR TS 3.8-38 Design Control Document/Tier 2

25A5675AU Revision 7 Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME B. One AC vital bus electrical B.1 Declare affected required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power distribution features inoperable.

subsystem inoperable.

AND B.2 Restore AC vital bus 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months electrical power distribution subsystem to AND OPERABLE status.

7 days from discovery of failure to meet LCO C. One AC vital bus electrical C.1 Restore inoperable AC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power distribution vital bus (other than subsystem (either Division IV) to Division I, II, or III) OPERABLE status.

inoperable.

OR AND C.2 Restore inoperable 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Division IV AC vital bus Division IV AC vital bus to inoperable. OPERABLE status.

(continued)

ABWR TS 3.8-39 Design Control Document/Tier 2

25A5675AU Revision 7 Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. One DC electrical power D.1 Declare affected required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months distribution subsystem features inoperable.

(either Division I, II, or III) inoperable. AND D.2 Verify the combustion 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months turbine generator (CTG) is functional by verifying the CTG starts and achieves steady state voltage and frequency within 2 minutes.

AND D.3 Verify the CTG circuit 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months breakers are capable of being aligned to the two AND unaffected 6.9 kV essential AC buses. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND D.4 Restore DC electrical 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months power distribution subsystems to AND OPERABLE status.

7 days from discovery of failure to meet LCO E. Division IV DC electrical E.1 Declare affected required 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months power distribution features inoperable.

subsystem inoperable.

(continued)

ABWR TS 3.8-40 Design Control Document/Tier 2

25A5675AU Revision 7 Distribution Systems - Operating 3.8.9 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. One DC electrical power F.1 Restore inoperable DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months distribution subsystem electrical power (either Division I, II, or III) distribution subsystems inoperable. (other than Division IV) to OPERABLE status.

AND OR Division IV DC electrical power distribution F.2 Restore Division IV DC 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months subsystem inoperable. electrical power distribution subsystems to OPERABLE status.

G. Required Action and G.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months associated Completion Time of Condition A, B, C, AND D, E, or F not met.

G.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.9.1 Verify correct breaker alignments and voltage to 7 days required AC, DC, and AC vital bus electrical power distribution subsystems.

ABWR TS 3.8-41 Design Control Document/Tier 2

25A5675AU Revision 7 Distribution Systems - Shutdown 3.8.10 3.8 ELECTRICAL POWER SYSTEMS 3.8.10 Distribution Systems - Shutdown LCO 3.8.10 The necessary portions of the Divisions I, II, and III AC, Divisions I, II, III, and IV DC, and Divisions I, II, III, and IV AC vital bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

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

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required AC, A.1 Declare associated Immediately DC, or AC vital bus supported required electrical power distribution feature(s) inoperable.

subsystems inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

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

AND (continued)

ABWR TS 3.8-42 Design Control Document/Tier 2

25A5675AU Revision 7 Distribution Systems - Shutdown 3.8.10 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.3 Initiate action to suspend Immediately operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate actions to restore Immediately required AC, DC, and AC vital bus electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated Immediately required shutdown cooling subsystem(s) inoperable and not in operation.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.10.1 Verify correct breaker alignments and voltage to 7 days required AC, DC, and AC vital bus electrical power distribution subsystems.

ABWR TS 3.8-43 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Shutdown (Low Water Level) 3.8.11 3.8 ELECTRICAL POWER SYSTEMS 3.8.11 AC Sources - Shutdown (Low Water Level)

LCO 3.8.11 The following AC electrical power sources shall be OPERABLE:

a. One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystems required by LCO 3.8.10, Distribution Systems - Shutdown;

b. Two or more diesel generators (DGs) capable of supplying the required OPERABLE features via the onsite Class 1E AC electrical power distribution subsystems required by LCO 3.8.10.

APPLICABILITY: MODE 4 and MODE 5 with water level in the refueling cavity < 7.0 meters above the reactor pressure vessel flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required offsite circuit --------------------NOTE-------------------

inoperable. Enter applicable Condition and Required Actions of LCO 3.8.10, with one required division de-energized as a result of Condition A.

A.1.1 Initiate action to restore Immediately required offsite circuit to OPERABLE status supplying power to all required ESF buses.

AND A.1.2 Declare affected required 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months feature(s) with no power available from an OPERABLE offsite circuit inoperable.

(continued)

ABWR TS 3.8-44 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Shutdown (Low Water Level) 3.8.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) OR A.2.1 Suspend CORE 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ALTERATIONS.

AND A.2.2 Suspend movement of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months irradiated fuel assemblies in secondary containment.

AND A.2.3 Initiate action to suspend 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months operations with a potential for draining the reactor vessel (OPDRVs).

AND A.2.4 Initiate action to restore Immediately required offsite circuit to OPERABLE status supplying power to all required ESF buses.

B. One required DG B.1 Verify the combustion 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. turbine generator (CTG) is functional by verifying the CTG starts and achieves steady state voltage and frequency within 2 minutes.

AND B.2 Verify the CTG circuit 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months breakers are aligned to the 6.9 kV essential AC AND bus associated with the inoperable required DG. Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND (continued)

ABWR TS 3.8-45 Design Control Document/Tier 2

25A5675AU Revision 7 AC Sources - Shutdown (Low Water Level) 3.8.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Restore required DG to 14 days OPERABLE status.

C. Required Action and C.1 Suspend CORE Immediately Completion Time of ALTERATIONS.

Condition B not met.

AND OR C.2 Suspend movement of Immediately Two or more required DGs irradiated fuel assemblies inoperable. in secondary containment.

AND C.3 Initiate action to suspend Immediately OPDRVs.

AND C.4 Initiate action to restore Immediately required DG(s) to OPERABLE status.

AND C.5 Declare affected required 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months features supported by the inoperable DG(s) inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.11.1 For AC sources required to be OPERABLE, the SRs In accordance of Specification 3.8.2 are applicable. with applicable SRs ABWR TS 3.8-46 Design Control Document/Tier 2

25A5675AU Revision 7 Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 The refueling equipment interlocks shall be OPERABLE.

APPLICABILITY: During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Suspend in-vessel fuel Immediately refueling equipment movement with interlocks inoperable. equipment associated with the inoperable interlock(s).

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each of 7 days the following required refueling equipment interlock inputs:

a. All-rods-in,

b. Refuel machine position, and

c. Refuel machine main hoist, fuel loaded.

ABWR TS 3.9-1 Design Control Document/Tier 2

25A5675AU Revision 7 Refuel Position Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position Rod-Out Interlock LCO 3.9.2 The refuel position rod-out interlock shall be OPERABLE.

APPLICABILITY: MODE 5 with the reactor mode switch in the refuel position and any control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Refuel position rod-out A.1 Suspend control rod Immediately interlock inoperable. withdrawal.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel position. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months SR 3.9.2.2 -------------------------------NOTE------------------------------

Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn.

Perform CHANNEL FUNCTIONAL TEST. 7 days ABWR TS 3.9-2 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY: When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more control rods A.1 Suspend loading fuel Immediately not fully inserted. assemblies into the core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ABWR TS 3.9-3 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 One control rod full-in position indication channel for each control rod shall be OPERABLE in core cells containing one or more fuel assemblies.

APPLICABILITY: MODE 5.

ACTIONS

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

Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1.1 Suspend in-vessel fuel Immediately control rod position movement.

indication channels inoperable. AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

OR A.2.1 Initiate action to fully Immediately insert the control rod associated with the inoperable position indicator.

AND (continued)

ABWR TS 3.9-4 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Position Indication 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.2.2 Initiate action to disarm Immediately the associated fully inserted control rod drive.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the required channel has no full-in indication Each time the on each control rod that is not full-in. control rod is withdrawn from the full-in position ABWR TS 3.9-5 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod OPERABILITY - Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY - Refueling LCO 3.9.5 Each withdrawn control rod shall be OPERABLE.

APPLICABILITY: MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more withdrawn A.1 Initiate action to fully Immediately control rods inoperable. insert inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Insert each withdrawn control rod at least one step. 7 days SR 3.9.5.2 Verify each withdrawn control rod scram accumulator 7 days pressure is 10.49 MPaG.

ABWR TS 3.9-6 Design Control Document/Tier 2

25A5675AU Revision 7 RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 RPV water level shall be 7.0 m above the top of the RPV flange.

APPLICABILITY: During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RPV water level not within A.1 Suspend movement of Immediately limit. fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is 7.0 m above the top of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the RPV flange.

ABWR TS 3.9-7 Design Control Document/Tier 2

25A5675AU Revision 7 RHR - High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR) - High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

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

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

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and with the water level 7.0 m above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat inoperable. removal is available. AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B. Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel assemblies Time of Condition A not into the RPV.

met.

AND B.2 Initiate action to restore Immediately the secondary containment to OPERABLE status.

AND (continued)

ABWR TS 3.9-8 Design Control Document/Tier 2

25A5675AU Revision 7 RHR - High Water Level 3.9.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore Immediately one standby gas treatment subsystem to OPERABLE status.

AND B.4 Initiate action to restore Immediately one secondary containment isolation valve and associated instrumentation to OPERABLE status in each associated penetration flow path not isolated.

C. Required RHR shutdown C.1 Establish reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from cooling subsystem not in circulation by an alternate discovery of no operation. method. reactor coolant circulation AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating and circulating reactor coolant.

ABWR TS 3.9-9 Design Control Document/Tier 2

25A5675AU Revision 7 RHR - Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR) - Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.

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

The required operating shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY: MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and with the water level < 7.0 m above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or two RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystems method of decay heat inoperable. removal is available for AND each inoperable RHR shutdown cooling Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months subsystem. thereafter B. Required Action and B.1 Initiate action to restore Immediately associated Completion the secondary Time of Condition A not containment to met. OPERABLE status.

AND B.2 Initiate action to restore Immediately one standby gas treatment subsystem to OPERABLE status.

AND (continued)

ABWR TS 3.9-10 Design Control Document/Tier 2

25A5675AU Revision 7 RHR - Low Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.3 Initiate action to restore Immediately one secondary containment isolation valve and associated instrumentation to OPERABLE status in each associated penetration flow path not isolated.

C. No RHR shutdown cooling C.1 Establish reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from subsystem in operation. circulation by an alternate discovery of no method. reactor coolant circulation AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating and circulating reactor coolant.

ABWR TS 3.9-11 Design Control Document/Tier 2

25A5675AU Revision 7 Inservice Leak and Hydrostatic Testing Operation 3.10.1 3.10 SPECIAL OPERATIONS 3.10.1 Inservice Leak and Hydrostatic Testing Operation LCO 3.10.1 The average reactor coolant temperature specified in Table 1.1-1 for MODE 4 may be changed to NA, and operation considered not to be in MODE 3; and the requirements of LCO 3.4.8, Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown, may be suspended, to allow performance of an inservice leak or hydrostatic test provided the following MODE 3 LCOs are met:

a. LCO 3.3.1.1, SSLC Sensor Instrumentation, Functions 7b, 24a and 24b;

b. LCO 3.3.1.4, ESF Actuation Instrumentation, Function 11;

c. LCO 3.6.4.1, Secondary Containment;

d. LCO 3.6.4.2, Secondary Containment Isolation Valves (SCIVs); and

e. LCO 3.6.4.3, Standby Gas Treatment (SGT) System.

APPLICABILITY: MODE 4 with average reactor coolant temperature > 93°C.

ABWR TS 3.10-1 Design Control Document/Tier 2

25A5675AU Revision 7 Inservice Leak and Hydrostatic Testing Operation 3.10.1 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 --------------NOTE------------

requirements not met. Required Actions to be in MODE 4 include reducing average reactor coolant temperature to 93°C.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Suspend activities that Immediately could increase the average reactor coolant temperature or pressure.

AND A.2.2 Reduce average reactor 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months coolant temperature to 93°C.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.1.1 Perform the applicable SRs for the required MODE 3 According to the LCOs. applicable SRs ABWR TS 3.10-2 Design Control Document/Tier 2

25A5675AU Revision 7 Reactor Mode Switch Interlock Testing 3.10.2 3.10 SPECIAL OPERATIONS 3.10.2 Reactor Mode Switch Interlock Testing LCO 3.10.2 The reactor mode switch position specified in Table 1.1-1 (Section 1.1, Definitions) for MODES 3, 4, and 5 may be changed to include the run, startup/hot standby, and refuel position, and operation considered not to be in MODE 1 or 2, to allow testing of instrumentation associated with the reactor mode switch interlock functions, provided:

a. All control rods remain fully inserted in core cells containing one or more fuel assemblies; and

b. No CORE ALTERATIONS are in progress.

APPLICABILITY: MODES 3 and 4 with the reactor mode switch in the run, startup/hot standby, or refuel position, MODE 5 with the reactor mode switch in the run or startup/hot standby position.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Suspend CORE Immediately requirements not met. ALTERATIONS except for control rod insertion.

AND A.2 Fully insert all insertable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months control rods in core cells containing one or more fuel assemblies.

AND A.3.1 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

OR (continued)

ABWR TS 3.10-3 Design Control Document/Tier 2

25A5675AU Revision 7 Reactor Mode Switch Interlock Testing 3.10.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) A.3.2 --------------NOTE------------

Only applicable in MODE 5.

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

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.2.1 Verify all control rods are fully inserted in core cells 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months containing one or more fuel assemblies.

SR 3.10.2.2 Verify no CORE ALTERATIONS are in progress. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ABWR TS 3.10-4 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Withdrawal - Hot Shutdown 3.10.3 3.10 SPECIAL OPERATIONS 3.10.3 Control Rod Withdrawal - Hot Shutdown LCO 3.10.3 The reactor mode switch position specified in Table 1.1-1 for MODE 3 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod or control rod pair, provided the following requirements are met:

a. LCO 3.9.2, Refuel Position Rod-Out Interlock;

b. LCO 3.9.4, Control Rod Position Indication;

c. All other control rods are fully inserted; and

d. 1. LCO 3.3.1.1, SSLC Sensor Instrumentation, MODE 5 requirements for Functions 1.a, 1.d, 2.a, and 2.d of Table 3.3.1.1-1, and LCO 3.3.1.2, RPS and MSIV Trip Actuation, Functions 1.a, 1.b, 3, and 4, and LCO 3.9.5, Control Rod OPERABILITY - Refueling, OR

2. All other control rods in a five by five array centered on each control rod being withdrawn are disarmed, and LCO 3.1.1, SHUTDOWN MARGIN (SDM), MODE 5 requirements, except the single control rod or pair to be withdrawn may be assumed to be the highest worth control rod.

APPLICABILITY: MODE 3 with the reactor mode switch in the refuel position.

ABWR TS 3.10-5 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Withdrawal - Hot Shutdown 3.10.3 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 -------------NOTES-----------

requirements not met. 1. Required Actions to fully insert all insertable control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to fully Immediately insert all insertable control rods.

AND A.2.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

ABWR TS 3.10-6 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Withdrawal - Hot Shutdown 3.10.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.3.1 Perform the applicable SRs for the required LCOs. According to the applicable SRs SR 3.10.3.2 -------------------------------NOTE------------------------------

Not required to be met if SR 3.10.3.1 is satisfied for LCO 3.10.3.d.1 requirements.

Verify all control rods, other than the control rod or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months rod pair being withdrawn, in a five by five array centered on each control rod being withdrawn, are disarmed.

SR 3.10.3.3 Verify all control rods, other than the control rod or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months rod pair being withdrawn, are fully inserted.

ABWR TS 3.10-7 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Withdrawal - Cold Shutdown 3.10.4 3.10 SPECIAL OPERATIONS 3.10.4 Control Rod Withdrawal - Cold Shutdown LCO 3.10.4 The reactor mode switch position specified in Table 1.1-1 for MODE 4 may be changed to include the refuel position, and operation considered not to be in MODE 2, to allow withdrawal of a single control rod or control rod pair, and subsequent removal of the associated control rod drives (CRD) if desired, provided the following requirements are met:

a. All other control rods are fully inserted;

b. 1. LCO 3.9.2, Refuel Position Rod-Out Interlock, and LCO 3.9.4, Control Rod Position Indication, OR

2. A control rod withdrawal block is inserted; and

c. 1. LCO 3.3.1.1, SSLC Sensor Instrumentation, MODE 5 requirements for Functions 1.a, 1.d, 2.a, and 2.d, of Table 3.3.1.1-1, LCO 3.3.1.2, RPS and MSIV Trip Actuation, Functions 1.a, 1.b, 3, and 4; and LCO 3.9.5, Control Rod OPERABILITY - Refueling, OR

2. All other control rods in a five by five array centered on the control rod being withdrawn are disarmed, and LCO 3.1.1, SHUTDOWN MARGIN (SDM), MODE 5 requirements, except the single control rod or control rod pair to be withdrawn may be assumed to be the highest worth control rod or control rod pair.

APPLICABILITY: MODE 4 with the reactor mode switch in the refuel position.

ABWR TS 3.10-8 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS

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

Separate Condition entry is allowed for each requirement of the LCO.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 -------------NOTES-----------

requirements not met with 1. Required Actions to the affected control rod(s) fully insert all insertable. insertable control rods include placing the reactor mode switch in the shutdown position.

2. Only applicable if the requirement not met is a required LCO.

Enter the applicable Immediately Condition of the affected LCO.

OR A.2.1 Initiate action to fully Immediately insert all insertable control rods.

AND A.2.2 Place the reactor mode 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months switch in the shutdown position.

B. One or more of the above B.1 Suspend withdrawal of Immediately requirements not met with the control rod(s) and the affected control rod(s) removal of associated not insertable. CRD(s).

AND B.2.1 Initiate action to fully Immediately insert all control rods.

OR (continued)

ABWR TS 3.10-9 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Withdrawal - Cold Shutdown 3.10.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.4.1 Perform the applicable SRs for the required LCOs. According to applicable SRs SR 3.10.4.2 -------------------------------NOTE------------------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.c.1 requirements.

Verify all control rods, other than the control rod or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months rod pair being withdrawn, in a five by five array centered on each control rod being withdrawn, are disarmed.

SR 3.10.4.3 Verify all control rods, other than the control rod or 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months rod pair being withdrawn, are fully inserted.

SR 3.10.4.4 -------------------------------NOTE------------------------------

Not required to be met if SR 3.10.4.1 is satisfied for LCO 3.10.4.b.1 requirements.

Verify a control rod withdrawal block is inserted. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ABWR TS 3.10-10 Design Control Document/Tier 2

25A5675AU Revision 7 CRD Removal - Refueling 3.10.5 3.10 SPECIAL OPERATIONS 3.10.5 Control Rod Drive (CRD) Removal - Refueling LCO 3.10.5 The requirements of Functions 1.a, 1.b, 1.d, 2.a, 2.d and 12 of LCO 3.3.1.1, SSLC Sensor Instrumentation; Functions 1.a, 1.b, 3, and 4 of LCO 3.3.1.2, RPS and MSIV Actuation; LCO 3.3.8.1, Electric Power Monitoring; LCO 3.9.1, Refueling Equipment Interlocks; LCO 3.9.2, Refueling Position Rod-Out Interlock; LCO 3.9.4, Control Rod Position Indication; and LCO 3.9.5, Control Rod OPERABILITY - Refueling, may be suspended in MODE 5 to allow the removal of a single CRD or CRD pair associated with control rod(s) withdrawn from core cell(s) containing one or more fuel assemblies, provided the following requirements are met:

a. All other control rods are fully inserted;

b. All other control rods in a five by five array centered on the control rod being removed are disarmed;

c. A control rod withdrawal block is inserted;

d. LCO 3.1.1, SHUTDOWN MARGIN (SDM), MODE 5 requirements, except the single control rod (or pair) to be withdrawn may be assumed to be the highest worth control rod pair; and

e. No other CORE ALTERATIONS are in progress.

APPLICABILITY: MODE 5 with LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Suspend removal of the Immediately requirements not met. control rod(s) and associated CRD mechanism.

AND A.2.1 Initiate action to fully Immediately insert all control rods.

(continued)

ABWR TS 3.10-11 Design Control Document/Tier 2

25A5675AU Revision 7 CRD Removal - Refueling 3.10.5 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued) OR A.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.5.1 Verify all control rods, other than the control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months withdrawn for the removal of the associated CRD, are fully inserted.

SR 3.10.5.2 Verify all control rods, other than the control rod 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months withdrawn for the removal of the associated CRD, in a five by five array centered on each control rod withdrawn for the removal of the associated CRD, are disarmed.

SR 3.10.5.3 Verify a control rod withdrawal block is inserted. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months SR 3.10.5.4 Perform SR 3.1.1.1. According to SR 3.1.1.1 SR 3.10.5.5 Verify no CORE ALTERATIONS, other than the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months single control rod or control rod pair being removed, are in progress.

ABWR TS 3.10-12 Design Control Document/Tier 2

25A5675AU Revision 7 Multiple Control Rod Withdrawal - Refueling 3.10.6 3.10 SPECIAL OPERATIONS 3.10.6 Multiple Control Rod Withdrawal - Refueling LCO 3.10.6 The requirements of LCO 3.9.3, Control Rod Position; LCO 3.9.4, Control Rod Position Indication; and LCO 3.9.5, Control Rod OPERABILITY - Refueling, may be suspended, and the full in position indicators may be bypassed for any number of control rods in MODE 5, to allow withdrawal of these control rods, removal of associated control rod drives (CRDs), or both, provided the following requirements are met:

a. The four fuel assemblies are removed from the core cells associated with each control rod or CRD to be removed;

b. All other control rods in core cells containing one or more fuel assemblies are fully inserted; and

c. Fuel assemblies shall only be loaded in compliance with an approved spiral reload sequence.

APPLICABILITY: MODE 5 with LCO 3.9.3, LCO 3.9.4, or LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Suspend withdrawal of Immediately requirements not met. control rods and removal of associated CRDs.

AND A.2.1 Initiate action to fully Immediately insert all control rods in core cells containing one or more fuel assemblies.

OR A.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

ABWR TS 3.10-13 Design Control Document/Tier 2

25A5675AU Revision 7 Multiple Control Rod Withdrawal - Refueling 3.10.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.6.1 Verify the four fuel assemblies are removed from 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months core cells associated with each control rod or CRD removed.

SR 3.10.6.2 Verify all other control rods in core cells containing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months one or more fuel assemblies are fully inserted.

SR 3.10.6.3 -------------------------------NOTE------------------------------

Only required to be met during fuel loading.

Verify fuel assemblies being loaded are in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months compliance with an approved spiral reload sequence.

ABWR TS 3.10-14 Design Control Document/Tier 2

25A5675AU Revision 7 Control Rod Testing - Operating 3.10.7 3.10 SPECIAL OPERATIONS 3.10.7 Control Rod Testing - Operating LCO 3.10.7 The requirements of LCO 3.1.6, Rod Pattern Control, may be suspended and control rods bypassed in the Rod Action and Position Information (RAPI) Subsystem as allowed by SR 3.3.5.1.7, to allow performance of SDM demonstrations, control rod scram time testing, control rod friction testing, and the Startup Test Program, provided conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.

APPLICABILITY: MODES 1 and 2 with LCO 3.1.6 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the LCO A.1 Suspend performance of Immediately not met. the test and exception to LCO 3.1.6.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.7.1 Verify movement of control rods is in compliance During control rod with the approved control rod sequence for the movement specified test by a second licensed operator or other qualified member of the technical staff.

ABWR TS 3.10-15 Design Control Document/Tier 2

25A5675AU Revision 7 SDM Test - Refueling 3.10.8 3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling LCO 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are met:

a. LCO 3.3.1.1, SSLC Sensor Instrumentation, MODE 2 requirements for Function 2.a and 2.d of Table 3.3.1.1-1;

b. 1. LCO 3.3.5.1, Control Rod Block Instrumentation, MODE 2 requirements for Function 1.b of Table 3.3.5.1-1, OR

2. Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff;

c. Each withdrawn control rod shall be coupled to the associated CRD;

d. All control rod withdrawals that are not in compliance with the Ganged Withdrawal Sequence Restrictions (GWSR) shall be made using either the NOTCH withdrawal mode or the STEP withdrawal mode; and

e. No other CORE ALTERATIONS are in progress.

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

ABWR TS 3.10-16 Design Control Document/Tier 2

25A5675AU Revision 7 SDM Test - Refueling 3.10.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Place the reactor mode Immediately requirements not met, for switch in the shutdown or reasons other than refuel position.

Condition B.

B. One control rod not coupled B.1 Declare the affected Immediately to its associated CRD. control rod inoperable.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the applicable SRs for LCO 3.3.1.1, According to the Functions 2.a and 2.d. applicable SRs SR 3.10.8.2 -------------------------------NOTE------------------------------

Not required to be met if SR 3.10.8.3 satisfied.

Perform the applicable SRs for LCO 3.3.5.1, According to the Function 1.b. applicable SRs SR 3.10.8.3 -------------------------------NOTE------------------------------

Not required to be met if SR 3.10.8.2 satisfied.

Verify movement of control rods is in compliance During control with the approved control rod sequence for the SDM rod movement test by a second licensed operator or other qualified member of the technical staff.

(continued)

ABWR TS 3.10-17 Design Control Document/Tier 2

25A5675AU Revision 7 SDM Test - Refueling 3.10.8 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months progress.

SR 3.10.8.5 Verify each withdrawn control rod does not go to the Prior to satisfying withdrawn overtravel position. LCO 3.10.8.c requirement after work on control rod or CRD System that could affect coupling AND Once the first time the control rod is withdrawn to full out position after the associated orificed fuel support has been moved ABWR TS 3.10-18 Design Control Document/Tier 2

25A5675AU Revision 7 Reactor Internal Pumps - Testing 3.10.9 3.10 SPECIAL OPERATIONS 3.10.9 Reactor Internal Pumps (RIPs) - Testing LCO 3.10.9 The requirements of LCO 3.4.1, Reactor Internal Pumps Operating, may be suspended for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to allow:

a. PHYSICS TESTS, provided THERMAL POWER is 5% RTP; and

b. Performance of the Startup Test Program.

APPLICABILITY: MODES 1 and 2 with less than nine RIPs in operation.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCO 3.4.1 A.1 Insert all insertable 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months not met for > 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . control rods.

B. Requirements of the B.1 Place the reactor mode Immediately LCO not met for reasons switch in the shutdown other than Condition A. position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.9.1 Verify LCO 3.4.1 requirements suspended for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 24 hours.

SR 3.10.9.2 Verify THERMAL POWER is 5% RTP during 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months PHYSICS TESTS.

ABWR TS 3.10-19 Design Control Document/Tier 2

25A5675AU Revision 7 Training Startups 3.10.10 3.10 SPECIAL OPERATIONS 3.10.10 Training Startups LCO 3.10.10 The low pressure core flooder (LPFL) OPERABILITY requirements specified in LCO 3.5.1, ECCS - Operating, may be changed to allow one residual heat removal subsystem to be aligned in the shutdown cooling mode for training startups, provided the following requirements are met:

a. REACTOR THERMAL POWER 1% RTP; and

b. Average reactor coolant temperature is < 93°C.

APPLICABILITY: MODE 2 with one LPFL subsystem suction valve closed.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Place the reactor mode Immediately requirements not met. switch in the shutdown position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.10.1 Verify REACTOR THERMAL POWER 1% RTP. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.10.10.2 Verify average reactor coolant temperature is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

< 93°C.

ABWR TS 3.10-20 Design Control Document/Tier 2

25A5675AU Revision 7 Low Power PHYSICS TEST 3.10.11 3.10 SPECIAL OPERATIONS 3.10.11 Low Power PHYSICS TEST LCO 3.10.11 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/hot standby position, and operation considered not to be in MODE 2, to allow Low Power PHYSICS TEST, provided the following requirements are met:

a. 1. LCO 3.3.5.1, Control Rod Block Instrumentation, MODE 2 requirements for Function 1.b of Table 3.3.5.1-1, OR

2. Conformance to the approved control rod sequence for the Low Power PHYSICS TEST is verified by a second licensed operator or other qualified member of the technical staff;

b. Each withdrawn control rod shall be coupled to the associated CRD;

c. All control rod withdrawals that are not in compliance with the Ganged Withdrawal Sequence Restrictions (GWSR) shall be made using either the NOTCH withdrawal mode or the STEP withdrawal mode;

d. No other CORE ALTERATIONS are in progress;

e. REACTOR THERMAL POWER 1% RTP; and

f. Average reactor coolant temperature 93°C (200°F).

APPLICABILITY: MODE 5 with the reactor mode switch in startup/hot standby position.

ABWR TS 3.10-21 Design Control Document/Tier 2

25A5675AU Revision 7 Low Power PHYSICS TEST 3.10.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Place the reactor mode Immediately requirements not met. switch in the shutdown or refuel position.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.11.1 -------------------------------NOTE------------------------------

Not required to be met if SR 3.10.11.2 satisfied.

Perform the applicable SRs for LCO 3.3.5.1, According to the Function 1.b. applicable SRs SR 3.10.11.2 -------------------------------NOTE------------------------------

Not required to be met if SR 3.10.11.1 satisfied.

Verify movement of control rods is in compliance During control with the approved control rod sequence for the Low rod movement Power PHYSICS TEST by a second licensed operator or other qualified member of the technical staff.

SR 3.10.11.3 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months progress.

(continued)

ABWR TS 3.10-22 Design Control Document/Tier 2

25A5675AU Revision 7 Low Power PHYSICS TEST 3.10.11 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.10.11.4 Verify each withdrawn control rod does not go to the Prior to satisfying withdrawn overtravel position. LCO 3.10.11.b requirement after work on control rod or CRD System that could affect coupling AND Once the first time the control rod is withdrawn to full out position after the associated orificed fuel support has been moved SR 3.10.11.5 Verify REACTOR THERMAL POWER 1% RTP. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months SR 3.10.11.6 Verify average reactor coolant temperature is 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 93°C.

ABWR TS 3.10-23 Design Control Document/Tier 2

25A5675AU Revision 7 Multiple Control Rod Drive Subassembly Removal - Refueling 3.10.12 3.10 SPECIAL OPERATIONS 3.10.12 Multiple Control Rod Drive Subassembly Removal - Refueling LCO 3.10.12 The requirements of LCO 3.9.3, Control Rod Position; LCO 3.9.4, Control Rod Position Indication; and LCO 3.9.5, Control Rod OPERABILITY - Refueling, may be suspended, and the full in position indicators may be bypassed for any number of control rods in MODE 5, to allow removal of control rod drive subassemblies with the control rods maintained fully inserted by their anti-rotation devices, provided the following requirements are met:

a. No two adjacent (face or diagonal) control rod drives are to have their subassemblies removed concurrently unless one of the two adjacent control rods has its four fuel assemblies removed from its associated core cell, and

b. All other control rods in core cells containing one or more fuel assemblies are fully inserted.

APPLICABILITY: MODE 5 with LCO 3.9.3, LCO 3.9.4, or LCO 3.9.5 not met.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more of the above A.1 Suspend removal of Immediately requirements not met. associated CRD subassemblies.

AND A.2.1 Initiate action to fully Immediately insert all control rods in core cells containing one or more fuel assemblies.

OR A.2.2 Initiate action to satisfy Immediately the requirements of this LCO.

ABWR TS 3.10-24 Design Control Document/Tier 2

25A5675AU Revision 7 Multiple Control Rod Drive Subassembly Removal - Refueling 3.10.12 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.10.12.1 Verify the anti-rotation devices associated with each 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months CRD subassembly removed are in the correct position to maintain the control rod fully inserted.

SR 3.10.12.2 For each control rod with its associated CRD 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months subassembly removed, verify from over the reactor vessel that the top of the control rod is visible at its fully inserted position.

SR 3.10.12.3 Verify all other control rods in core cells containing 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months one or more fuel assemblies are fully inserted.

ABWR TS 3.10-25 Design Control Document/Tier 2

25A5675AU Revision 7 Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site and Exclusion Area Boundaries The site and exclusion area boundaries [shall be as described or as shown in Figure 4.1-1].

4.1.2 Low Population Zone (LPZ)

The LPZ [shall be as described or as shown in Figure 4.1-2].

4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 872 fuel assemblies. Each assembly shall consist of a matrix of zirconium alloy fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material, and water rods. Limited substitutions of zirconium alloy rods for fuel rods, in accordance with approved applications of fuel rod configurations, may be used. Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.

4.2.2 Control Rod Assemblies The reactor core shall contain 205 cruciform shaped control rod assemblies. The control material shall be boron carbide and/or hafnium metal as approved by the NRC.

4.3 Fuel Storage 4.3.1 Criticality The spent fuel storage racks are designed and shall be maintained with:

a. Fuel assemblies having a maximum k-infinity of 1.35 in the normal reactor core configuration at cold conditions;

b. keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the DCD Tier 2.

(continued)

ABWR TS 4.0-1 Design Control Document/Tier 2

25A5675AU Revision 7 Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.2 Drainage The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below 3.1 m above the top of the active fuel.

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no less than 2354 fuel assemblies (270% of full core discharge).

ABWR TS 4.0-2 Design Control Document/Tier 2

25A5675AU Revision 7 Design Features 4.0 (This figure shall be supplied by the COL applicant.)

This figure shall consist of [a map of] the site area and provide, as a minimum, the information described in Section

[2.1.2] of the FSAR relating to [the map].

Figure 4.1-1 (page 1 of 1)

Site and Exclusion Area Boundaries ABWR TS 4.0-3 Design Control Document/Tier 2

25A5675AU Revision 7 Design Features 4.0 (This figure shall be supplied by the COL applicant.)

This figure shall consist of [a map of] the site area showing the LPZ boundary. Features such as towns, roads, and recreational areas shall be indicated in sufficient detail to allow identification of significant shifts in population distribution within the LPZ.

Figure 4.1-2 (page 1 of 1)

Low Population Zone ABWR TS 4.0-4 Design Control Document/Tier 2

25A5675AU Revision 7 Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The [Plant Superintendent] shall be responsible for overall unit operation and shall delegate in writing the succession to this responsibility during his absence.

The [Plant Superintendent], or his designee, in accordance with approved administrative procedures, shall approve, prior to implementation, each proposed test or experiment and proposed changes and modifications to unit systems or equipment that affect nuclear safety.

5.1.2 The [Shift Supervisor (SS)] shall be responsible for the control room command function. A management directive to this effect, signed by the [highest level of corporate or site management] shall be issued annually to all station personnel.

During any absence of the [SS] from the control room while the unit is in MODE 1, 2, 3, or 4, an individual with an active Senior Reactor Operator (SRO) license shall be designated to assume the control room command function.

During any absence of the [SS] from the control room while the unit is in MODE 5, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.

ABWR TS 5.0-1 Design Control Document/Tier 2

25A5675AU Revision 7 Organization 5.2 5.0 ADMINISTRATIVE CONTROLS 5.2 Organization 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be defined and established throughout highest management levels, intermediate levels, and all operating organization positions. These relationships shall be documented and updated, as appropriate, in organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation. These requirements shall be documented in the

[applicants FSAR];

b. The [Plant Superintendent] shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant;

c. The [a specified corporate executive position] shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety; and

d. The individuals who train the operating staff, carry out health physics, or perform quality assurance functions may report to the appropriate onsite manager; however, these individuals shall have sufficient organizational freedom to ensure their independence from operating pressures.

5.2.2 Unit Staff The unit staff organization shall include the following:

a. An auxiliary operator shall be assigned to each reactor containing fuel and an additional auxiliary operator shall be assigned for each control room from which a reactor is operating.1 1 Two unit sites with both units shutdown or defueled require a total of three auxiliary operators for the two units (continued)

ABWR TS 5.0-2 Design Control Document/Tier 2

25A5675AU Revision 7 Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

b. At least one licensed Reactor Operator (RO) shall be present in the control room when fuel is in the reactor. In addition, while the unit is in MODE 1, 2, 3, or 4, at least one licensed Senior Reactor Operator (SRO) shall be present in the control room.

c. A [Health Physics Technician] shall be on site when fuel is in the reactor.

The position may be vacant for not more than 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to provide for unexpected absence, provided immediate action is taken to fill the required position.

d. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety related functions (e.g.,

licensed SROs, licensed ROs, health physicists, auxiliary operators, and key maintenance personnel).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have operating personnel work an

[8 or 12] hour day, nominal 40 hour4.62963e-4 days 0.0111 hours 6.613757e-5 weeks 1.522e-5 months week, while the unit is operating.

However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major plant modification, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months straight, excluding shift turnover time;

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months in any 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48 hour5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period, all excluding shift turnover time;

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months should be allowed between work periods, including shift turnover time;

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized in advance by the [Plant Superintendent] or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation.

(continued)

ABWR TS 5.0-3 Design Control Document/Tier 2

25A5675AU Revision 7 Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)

Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the [Plant Superintendent] or his designee to ensure that excessive hours have not been assigned. Routine deviation from the above guidelines is not authorized.

OR The amount of overtime worked by unit staff members performing safety related functions shall be limited and controlled in accordance with the NRC Policy Statement on working hours (Generic Letter 82-12).

e. The [Operations Manager or Assistant Operations Manager] shall hold an active SRO license.

f. The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Supervisor (SS) in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.

ABWR TS 5.0-4 Design Control Document/Tier 2

25A5675AU Revision 7 Unit Staff Qualifications 5.3 5.0 ADMINISTRATIVE CONTROLS 5.3 Unit Staff Qualifications Reviewers Note: Minimum qualifications for members of the unit staff shall be specified by use of an overall qualification statement referencing an ANSI Standard acceptable to the NRC staff or by specifying individual position qualifications. Generally, the first method is preferable; however, the second method is adaptable to those unit staffs requiring special qualification statements because of unique organizational structures.

5.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of

[Regulatory Guide 1.8, Revision 2, 1987, or more recent revisions, or ANSI Standard acceptable to the NRC staff]. The staff not covered by [Regulatory Guide 1.8] shall meet or exceed the minimum qualifications of [Regulations, Regulatory Guides, or ANSI Standards acceptable to NRC staff].

ABWR TS 5.0-5 Design Control Document/Tier 2

25A5675AU Revision 7 TS Bases Control 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Technical Specifications (TS) Bases Control 5.4.1 Changes to the Bases of the TS shall be made under appropriate administrative controls and reviews.

5.4.2 Licensees may make changes to Bases without prior NRC approval provided the changes do not involve either of the following:

a. A change in the plant-specific TS, or plant-specific DCD Tier 1 or Tier 2 information; or

b. A change to the site-specific portion of the FSAR that involves an unreviewed safety question as defined in 10 CFR 50.59, or a change to Tier 2 of the plant-specific DCD that involves an unreviewed safety question as defined in the design certification rule for the ABWR (Appendix A to 10 CFR 52).

Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71.

5.4.3 The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the FSAR, which consists of the plant-specific DCD and the site-specific portion of the FSAR.

5.4.4 Proposed changes that meet the criteria of Specification 5.4.2.a or Specification 5.4.2.b above shall be reviewed and approved by the NRC prior to implementation.

ABWR TS 5.0-6 Design Control Document/Tier 2

25A5675AU Revision 7 Procedures, Programs, and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Procedures, Programs, and Manuals 5.5.1 Procedures 5.5.1.1 Scope Written procedures shall be established, implemented, and maintained covering the following activities:

a. The applicable procedures recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978;

b. The emergency operating procedures required to implement the requirements of NUREG-0737 and NUREG-0737, Supplement 1, as stated in [Generic Letter 82-33];

c. Quality assurance for effluent and environmental monitoring;

d. Fire Protection Program implementation; and

e. All programs specified in Specification 5.5.2.

5.5.2 Programs and Manuals The following programs shall be established, implemented, and maintained:

5.5.2.1 Offsite Dose Calculation Manual (ODCM)

a. The ODCM shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alarm and trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program; and

b. The ODCM shall also contain the Radioactive Effluent Controls program required by Specification 5.5.2.4, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radioactive Effluent Release, reports required by Specification 5.7.1.2 and Specification 5.7.1.3.

Licensee initiated changes to the ODCM:

a. Shall be documented and records of reviews performed shall be retained.

This documentation shall contain:

(continued)

ABWR TS 5.0-7 Design Control Document/Tier 2

25A5675AU Revision 7 Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.1 Offsite Dose Calculation Manual (ODCM) (continued)

1. sufficient information to support the change(s) together with the appropriate analyses or evaluations justifying the change(s), and

2. a determination that the change(s) maintain the levels of radioactive effluent control required pursuant to 10 CFR 20.1302, 40 CFR 190, 10 CFR 50.36a, and 10 CFR 50, Appendix I, and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations;

b. Shall become effective after review and acceptance by plant reviews and the approval of the [Plant Superintendent]; and

c. Shall be submitted to the NRC in the form of a complete, legible copy of the entire ODCM as a part of, or concurrent with, the Radioactive Effluent Release Report for the period of the report in which any change in the ODCM was made. Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (i.e., month and year) the change was implemented.

5.5.2.2 Primary Coolant Sources Outside Containment This program provides controls to minimize leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to levels as low as practicable. The systems include the Low Pressure Core Flooder, High Pressure Core Flooder, Residual Heat Removal, Reactor Core Isolation Cooling, Hydrogen Recombiner, Post Accident Sampling, Standby Gas Treatment, Suppression Pool Cleanup, Reactor Water Cleanup, Fuel Pool Cooling and Cleanup, Process Sampling, Containment Atmospheric Monitoring, and Fission Product Monitor. The program shall include the following:

a. Preventive maintenance and periodic visual inspection requirements; and

b. Integrated leak test requirements for each system at refueling cycle intervals or less.

5.5.2.3 Post Accident Sampling This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shall include the following:

a. Training of personnel; (continued)

ABWR TS 5.0-8 Design Control Document/Tier 2

25A5675AU Revision 7 Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.3 Post Accident Sampling (continued)

b. Procedures for sampling and analysis; and

c. Provisions for maintenance of sampling and analysis equipment.

5.5.2.4 Radioactive Effluent Controls Program This program conforms to 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to members of the public from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the ODCM, (2) shall be implemented by procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

a. Limitations on the functional capability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM;

b. Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentration values in Appendix B, Table 2, Column 2 to 10 CFR 20.1001-20.2401;

c. Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents pursuant to 10 CFR 20.1302 and with the methodology and parameters in the ODCM;

d. Limitations on the annual and quarterly doses or dose commitment to a member of the public from radioactive materials in liquid effluents released from each unit to unrestricted areas, conforming to 10 CFR 50, Appendix I;

e. Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days;

f. Limitations on the functional capability and use of the liquid and gaseous effluent treatment systems to ensure that appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a period of 31 days would exceed 2 percent of the guidelines for the annual dose or dose commitment, conforming to 10 CFR 50, Appendix I; (continued)

ABWR TS 5.0-9 Design Control Document/Tier 2

25A5675AU Revision 7 Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.4 Radioactive Effluent Controls Program (continued)

g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the dose associated with 10 CFR 20, Appendix B, Table II, Column 1;

h. Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I;

i. Limitations on the annual and quarterly doses to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and

j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.

5.5.2.5 Component Cyclic or Transient Limit This program provides controls to track the cyclic and transient occurrences in DCD Tier 2, Section 3.9.1.1 to ensure that components are maintained within the design limits.

5.5.2.6 Inservice Testing Program This program shall include the following:

a. Testing frequencies specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:

ASME Boiler and Pressure Vessel Code and applicable Required Frequencies Addenda terminology for for performing inservice inservice testing activities testing activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days Biennially or every 2 years At least once per 731 days (continued)

ABWR TS 5.0-10 Design Control Document/Tier 2

25A5675AU Revision 7 Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.6 Inservice Testing Program (continued)

b. The provisions of SR 3.0.2 are applicable to the above required Frequencies for performing inservice testing activities;

c. The provisions of SR 3.0.3 are applicable to inservice testing activities; and

d. Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any TS.

5.5.2.7 Ventilation Filter Testing Program (VFTP)

A program shall be established to implement the following required testing of Engineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in [Regulatory Guide ], and in accordance with Regulatory Guide 1.52, Revision 2; ASME N510-1989; and AG-1-1991.

a. Demonstrate for each of the ESF systems that an inplace test of the high efficiency particulate air (HEPA) filters shows a penetration and system bypass < [0.05]% when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989 at the system flowrate specified below

[+/- 10%]:

ESF Ventilation System Flowrate Control Room Habitability System Standby Gas Treatment System

b. Demonstrate for each of the ESF systems that an inplace test of the charcoal adsorber shows a penetration and system bypass < [0.05]%

when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989 at the system flowrate specified below [+/- 10%]:

ESF Ventilation System Flowrate Control Room Habitability System Standby Gas Treatment System

c. Demonstrate for each of the ESF systems that a laboratory test of a sample of the charcoal adsorber, when obtained as described in Regulatory Guide 1.52, Revision 2, shows the methyl iodide penetration less than the value specified below when tested in accordance with

[ASTM D3803-1989] at a temperature of [30°C] and greater than or equal to the relative humidity specified below:

(continued)

ABWR TS 5.0-11 Design Control Document/Tier 2

25A5675AU Revision 7 Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.7 Ventilation Filter Testing Program (VFTP) (continued)

ESF Ventilation System Penetration RH Control Room Habitability System Standby Gas Treatment System Reviewers Note: Allowable penetration = [100% - methyl iodide efficiency for charcoal credited in staff safety evaluation]/(safety factor).

Safety factor = [5] for systems with heaters.

d. Demonstrate for each of the ESF systems that the pressure drop across the combined HEPA filters, the prefilters, and the charcoal adsorbers is less than the value specified below when tested in accordance with Regulatory Guide 1.52, Revision 2, and ASME N510-1989 at the system flowrate specified below [+/- 10%]:

ESF Ventilation System Delta P Flowrate Control Room Habitability System Standby Gas Treatment System

e. Demonstrate that the heaters for each of the ESF systems dissipate the value specified below [+/- 10%] when tested in accordance with ASME N510-1989:

ESF Ventilation System Wattage Control Room Habitability System Standby Gas Treatment System The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the VFTP test frequencies.

5.5.2.8 Explosive Gas Radioactivity Monitoring Program This program provides controls for potentially explosive gas mixtures contained in the Offgas System. The gaseous radioactivity quantities shall be determined following the methodology in Branch Technical Position (BTP) ETSB 11-5, Postulated Radioactive Release due to Waste Gas System Leak or Failure.

(continued)

ABWR TS 5.0-12 Design Control Document/Tier 2

25A5675AU Revision 7 Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2.8 Explosive Gas Radioactivity Monitoring Program (continued)

The program shall include:

a. The limits for concentrations of hydrogen and oxygen in the Offgas System and a surveillance program to ensure the limits are maintained.

Such limits shall be appropriate to the systems design criteria (i.e.,

whether or not the system is designed to withstand a hydrogen explosion);

b. A surveillance program to ensure that the quantity of radioactivity in the Offgas System is less than the amount that would result in a whole body exposure of 25 mSv to any individual in an unrestricted area, in the event of inadvertent bypass of the Offgas Systems charcoal beds as analyzed in DCD Tier 2, Section 15.7.1.

The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas Radioactivity Monitoring Program surveillance frequencies.

5.5.2.9 Diesel Fuel Oil Testing Program A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established. The program shall include sampling and testing requirements, and acceptance criteria, all in accordance with applicable ASTM Standards. The purpose of the program is to establish the following:

a. Acceptability of new fuel oil for use prior to addition to storage tanks by determining that the fuel oil has:

1. an API gravity or an absolute specific gravity within limits,

2. a flash point and kinematic viscosity within limits for ASTM 2D fuel oil, and

3. a clear and bright appearance with proper color;

b. Other properties for ASTM 2D fuel oil are within limits within 31 days following sampling and addition to storage tanks; and

c. Total particulate concentration of the fuel oil is 10 mg/l when tested every 31 days in accordance with ASTM D-2276, Method A-2 or A-3.

(continued)

ABWR TS 5.0-13 Design Control Document/Tier 2

25A5675AU Revision 7 Procedures, Programs, and Manuals 5.5 5.5 Procedures, Programs, and Manuals 5.5.2 Programs and Manuals (continued) 5.5.2.10 Software Error Evaluation Program This program provides controls to ensure that appropriate software error evaluation procedures, to protect the plant from common mode software errors, are established to ensure that redundant system capability is not adversely affected. This program shall evaluate the cause of the inoperability, the affected components, and the plans and schedule for completing proposed remedial actions. If a determination is made that a common mode software error exists, then a Special Report shall be submitted in accordance with Specification 5.7.2.b.

ABWR TS 5.0-14 Design Control Document/Tier 2

25A5675AU Revision 7 SFDP 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Safety Function Determination Program (SFDP) 5.6.1 This program ensures loss of safety function is detected and appropriate actions taken. Upon failure to meet two or more LCOs at the same time, an evaluation shall be made to determine if loss of safety function exists. Additionally, other appropriate limitations and remedial or compensatory actions may be identified to be taken as a result of the support system inoperability and corresponding exception to entering supported system Condition and Required Actions. This program implements the requirements of LCO 3.0.6.

5.6.2 The SFDP shall contain the following:

a. Provisions for cross division checks to ensure a loss of the capability to perform the safety function assumed in the accident analysis does not go undetected;

b. Provisions for ensuring the plant is maintained in a safe condition if a loss of function condition exists;

c. Provisions to ensure that an inoperable supported systems Completion Time is not inappropriately extended as a result of multiple support system inoperabilities; and

d. Other appropriate limitations and remedial or compensatory actions.

5.6.3 A loss of safety function exists when, assuming no concurrent single failure, a safety function assumed in the accident analysis cannot be performed. For the purpose of this program, a loss of safety function may exist when a support system is inoperable, and:

a. A required system redundant to system(s) supported by the inoperable support system is also inoperable (Case A); or

b. A required system redundant to system(s) in turn supported by the inoperable supported system is also inoperable (Case B); or

c. A required system redundant to support system(s) for the supported systems (a) and (b) above is also inoperable (Case C).

(continued)

ABWR TS 5.0-15 Design Control Document/Tier 2

25A5675AU Revision 7 SFDP 5.6 5.6 SFDP 5.6.3 (continued)

Generic Example:

Division A Division B System i System i Case C System ii (Support System System ii Inoperable)

System iii System iii Case A System iv System iv Case B 5.6.4 The SFDP identifies where a loss of safety function exists. If a loss of safety function is determined to exist by this program, the appropriate Conditions and Required Actions of the LCO in which the loss of safety function exists are required to be entered.

ABWR TS 5.0-16 Design Control Document/Tier 2

25A5675AU Revision 7 Reporting Requirements 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 Reporting Requirements 5.7.1 Routine Reports The following reports shall be submitted in accordance with 10 CFR 50.4.

5.7.1.1 Annual Reports

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

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

Annual Reports covering the activities of the unit as described below for the previous calendar year shall be submitted by March 31 of each year. [The initial report shall be submitted by March 31 of the year following initial criticality.]

Reports required on an annual basis include:

a. Occupational Radiation Exposure Report A tabulation on an annual basis of the number of station, utility, and other personnel (including contractors) for whom monitoring was required, receiving an annual deep dose equivalent > 1 mSv and the associated collective deep dose equivalent (reported in person-rem) according to work and job functions (e.g.,

reactor operations and surveillance, inservice inspection, routine maintenance, special maintenance [describe maintenance], waste processing, and refueling).

This tabulation supplements the requirements of 10 CFR 20.2206. The dose assignments to various duty functions may be estimated based on pocket dosimeter, thermoluminescent dosimeter (TLD), or film badge measurements.

Small exposures totalling < 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total deep dose equivalent received from external sources should be assigned to specific major work functions; and

[b. Any other unit unique reports required on an annual basis.]

5.7.1.2 Annual Radiological Environmental Operating Report

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

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

(continued)

ABWR TS 5.0-17 Design Control Document/Tier 2

25A5675AU Revision 7 Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1.2 Annual Radiological Environmental Operating Report (continued)

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements [in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979]. [The report shall identify the TLD results that represent collocated dosimeters in relation to the NRC TLD program and the exposure period associated with each result.] In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.7.1.3 Radioactive Effluent Release Report

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

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit during the previous year shall be submitted prior to May 1 of each year in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.7.1.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience [, including documentation of all challenges to the safety/relief valves,] shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

(continued)

ABWR TS 5.0-18 Design Control Document/Tier 2

25A5675AU Revision 7 Reporting Requirements 5.7 5.7 Reporting Requirements 5.7.1 Routine Reports (continued) 5.7.1.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

The individual specifications that address core operating limits must be referenced here.

b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

Identify the Topical Report(s) by number, title, date, and NRC staff approval document, or identify the staff Safety Evaluation Report for a plant specific methodology by NRC letter and date.

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.7.1.6 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

The RCS pressure and temperature limits, including heatup and cooldown rates, criticality, and hydrostatic and leak test limits, shall be established and documented in the PTLR. [ The individual Specifications that address the reactor vessel pressure and temperature limits and the heatup and cooldown rates may be referenced. ] The analytical methods used to determine the pressure and temperature limits including the heatup and cooldown rates shall be those previously reviewed and approved by the NRC in [Topical Report(s), number, title, date, and NRC staff approval document, or staff safety evaluation report for a plant specific methodology by NRC letter and date]. The reactor vessel pressure and temperature limits, including those for heatup and cooldown rates, shall be determined so that all applicable limits (e.g., heatup limits, cooldown limits, and inservice leak and hydrostatic testing limits) of the analysis are met.

The PTLR, including revisions or supplements thereto, shall be provided upon issuance for each reactor vessel fluency period.

(continued)

ABWR TS 5.0-19 Design Control Document/Tier 2

25A5675AU Revision 7 Reporting Requirements 5.7 5.7 Reporting Requirements (continued) 5.7.2 Special Reports Special Reports may be required covering inspection, test, and maintenance activities. These special reports are determined on an individual basis for each unit, and their preparation and submittal are designated in the Technical Specifications.

Special Reports shall be submitted in accordance with 10 CFR 50.4 within the time period specified for each report.

The following Special Reports shall be submitted:

a. When a Special Report is required by Condition C of LCO 3.3.3.1, Essential Multiplexer System, a report shall be submitted within the following 14 days. The report shall outline the cause of the inoperability, consideration of common mode failures, and the plans and schedule for restoring the EMS transmission segments to OPERABLE status.

b. When a Special Report is required by Specification 5.5.2.10, Software Error Evaluation Program, a report shall be submitted within the following 7 days. The report shall outline the cause of the inoperability, the affected components, and the plans and schedule for completing proposed remedial actions.

ABWR TS 5.0-20 Design Control Document/Tier 2

ML20007E349

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