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| - UNITS 1 & 2 i Amendment 110
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| TABLE OF CONTENTS
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| - TECHNICAL SPECIFICATIONS
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| 1.0 USE AND APPLICATION
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| ===1.1 Definitions===
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| ..........................................1.1-1 1.2 Logical Connectors
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| ...................................1.2-1 1.3 Completion Times
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| .....................................1.3-1 1.4 Frequency ............................................1.4-1
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| ===2.0 SAFETY===
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| LIMITS (SLs) 2.1 SLs .................................................2.0-1 2.2 SL Violations
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| ........................................2.0-1
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| ===3.0 LIMITING===
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| CONDITION FOR OPERATION (LCO) AND SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
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| .......................3.0-1
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| ===3.1 REACTIVITY===
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| CONTROL SYSTEMS
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| ====3.1.1 SHUTDOWN====
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| MARGIN (SDM)
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| ................................3.1.1-1 3.1.2 Core Reactivity
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| ......................................3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC)
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| ..............3.1.3-1 3.1.4 Rod Group Alignment Limits
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| ...........................3.1.4-1 3.1.5 Shutdown Bank Insertion Limits
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| .......................3.1.5-1 3.1.6 Control Bank Insertion Limits
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| ........................3.1.6-1 3.1.7 Rod Position Indication
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| ..............................3.1.7-1 3.1.8 PHYSICS TESTS Exceptions
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| -MODE 2 ......................3.1.8-1
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| ===3.2 POWER===
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| DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (F Q(Z)) .................3.2.1-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor
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| )F (N H ........3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
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| .........................3.2.3-1 3.2.4 QUADRANT POWER TILT RATIO (QPTR)
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| .....................3.2.4-1 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
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| .........3.2.5-1
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| ===3.3 INSTRUMENTATION===
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| ====3.3.1 Reactor====
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| Trip System (RTS) Instrumentation
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| ............3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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| ..........................3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation
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| .......3.3.3-1 3.3.4 Remote Shutdown System ...............................3.3.4-1 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation
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| ..................................3.3.5-1 3.3.6 Containment Ventilation Isolation Instrumentation
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| ....3.3.6-1 3.3.7 Control Room Ventilation (VC) Filtration System Actuation Instrumentation
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| ........................3.3.7-1 3.3.8 Fuel Handling Building Exhaust Filter Plenum (FHB)
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| Ventilation System Actuation Instrumentation
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| ....3.3.8-1 3.3.9 Boron Dilution Protection System (BDPS)
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| ..............3.3.9-1 TABLE OF CONTENTS -TECHNICAL SPECIFICATIONS
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| ===3.4 REACTOR===
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| COOLANT SYSTEM (RCS)3.4.1 RCS Pressure, Temperature, and Flow Departure.from Nucleate Boiling (DNB) Limits ...............
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| 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality
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| ..............
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| 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits ............
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| 3.4.3-1 3.4.4 RCS Loops-MODES 1 and 2 ..............................
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| 3.4.4-1 3.4.5 RCS Loops-MODE 3... ... ............................
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| 3.4.5-1 3.4.6 RCS Loops-MODE 4 ..............
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| ........................
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| 3.4.6-1 3.4.7 RCS Loops-MODE 5, Loops Filled .......................
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| 3.4.7-1 3.4.8 RCS Loops-MODE 5, Loops Not Filled ...................
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| 3.4.8-1 3.4.9 Pressurizer
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| ..............................
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| 3.4.9-1 3.4.10 Pressurizer Safety Valves ............................
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| 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ..... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP)System ..............
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| 3.4.12-1 3.4.13 RCS Operational LEAKAGE ..............................
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| 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ...........
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| 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation
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| ...............
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| 3.4.15-1 3.4.16 RCS Specific Activity ........ ................
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| 3.4.16-1 3.4.17 RCS Loop Isolation Valves ............................
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| 3.4.17-1 3.4.18 RCS Loops-Isolated
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| ...................
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| ...........
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| 3.4.18-1 3.4.19 Steam Generator (SG) Tube Integrity
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| .................
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| 3.4.19-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.1 Accumulators
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| .........................................
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| 3.5.1-1 3.5.2 ECCS-Operating
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| .......................................
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| 3.5.2-1 3.5.3 ECCS-Shutdown
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| .................
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| .3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST).............
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| 3.5.5 Seal Injection Flow ..................................
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| 3.5.5-1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment
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| ..........................................
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| 3.6.1-1 3.6.2 Containment Air Locks....
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| ...... 3.6.2-1 3.6.3 Containment Isolation Valves....
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| ........ ....... 3.6.3-1 3.6.4 Containment Pressure .................................
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| 3.6.4-1 3.6.5 Containment Air Temperature
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| ..........................
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| 3.6.5-1 3.6.6 Containment Spray and Cooling Systems ................
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| 3.6.6-1 3.6.7 Spray Additive System ................................
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| 3.6.7-1 3.6.8 (Deleted)
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| ............................................
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| 3.6.8-1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) .....................
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| 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ..................
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| 3.7.2-1 3.7.3 Secondary Specific Activity ..........................
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| 3.7.3-1 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs) ..............
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| .3.7.4-1 3.7.5 Auxiliary Feedwater (AF) System ......................
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| 3.7.5-1 3.7.6 Condensate Storage Tank (CST) ........................
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| 3.7.6-1 BRAIDWOOD
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| -UNITS 1 & 2 ii Amendment 144 BRAIDWOOD
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| - UNITS 1 & 2 iii Amendment 124
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| TABLE OF CONTENTS
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| - TECHNICAL SPECIFICATIONS
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| ===3.7 PLANT===
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| SYSTEMS (continued)
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| ====3.7.7 Component====
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| Cooling Water (CC) System
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| ..................3.7.7-1 3.7.8 Essential Service Water (SX) System
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| ..................3.7.8-1 3.7.9 Ultimate Heat Sink (UHS)
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| .............................3.7.9-1 3.7.10 Control Room Ventilation (VC) Filtration System
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| ......3.7.10-1 3.7.11 Control Room Ventilation (VC) Temperature Control System
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| ...................................3.7.11-1 3.7.12 Nonaccessible Area Exhaust Filter Plenum Ventilation System
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| ...............................3.7.12-1 3.7.13 Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System
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| .........................3.7.13-1 3.7.14 Spent Fuel Pool Water Level
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| ..........................3.7.14-1 3.7.15 Spent Fuel Pool Boron Concentration
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| ..................3.7.15-1 3.7.16 Spent Fuel Assembly Storage
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| ..........................3.7.16-1
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| ===3.8 ELECTRICAL===
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| POWER SYSTEMS 3.8.1 AC Sources
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| -Operating ................................
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| .3.8.1-1 3.8.2 AC Sources
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| -Shutdown ..................................3.8.2-1 3.8.3 Diesel Fuel Oil
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| ......................................3.8.3-1 3.8.4 DC Sources
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| -Operating ................................
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| .3.8.4-1 3.8.5 DC Sources
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| -Shutdown ..................................3.8.5-1 3.8.6 Battery Cell Parameters
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| ..............................3.8.6-1 3.8.7 Inverters-Operating ..................................3.8.7-1 3.8.8 Inverters-Shutdown ...................................3.8.8-1 3.8.9 Distribution Systems
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| -Operating .......................3.8.9-1 3.8.10 Distribution Systems
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| -Shutdown ........................3.8.10-1
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| ===3.9 REFUELING===
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| OPERATIONS
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| ====3.9.1 Boron====
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| Concentration
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| ..................................3.9.1-1 3.9.2 Unborated Water Source Isolation Valves
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| ..............3.9.2-1 3.9.3 Nuclear Instrumentation
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| ..............................3.9.3-1 3.9.4 Containment Penetrations .............................3.9.4-1 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation
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| -High Water Level
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| .....................3.9.5-1 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation
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| -Low Water Level
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| ......................3.9.6-1 3.9.7 Refueling Cavity Water Level
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| .........................3.9.7-1
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| ===4.0 DESIGN===
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| FEATURES 4.1 Site .................................................4.0-1 4.2 Reactor Core
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| .........................................4.0-1 4.3 Fuel Storage
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| .........................................4.0-2 BRAIDWOOD
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| - UNITS 1 & 2 iv Amendment 110
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| TABLE OF CONTENTS
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| - TECHNICAL SPECIFICATIONS
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| ===5.0 ADMINISTRATIVE===
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| CONTROLS
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| ===5.1 Responsibility===
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| .......................................5.1-1 5.2 Organization
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| .........................................5.2-1 5.3 Facility Staff Qualifications
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| ........................5.3-1 5.4 Procedures
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| ...........................................5.4-1 5.5 Programs and Manuals
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| ................................
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| .5.5-1 5.6 Reporting Requirements
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| ...............................5.6-1 5.7 High Radiation Area
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| ..................................5.7-1 Definitions 1.1 1.0 USE AND APPLICATION
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| ===1.1 Definitions===
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| The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.Term ACTIONS ACTUATION LOGIC TEST AXIAL FLUX DIFFERENCE (AFD)CHANNEL CALIBRATION Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum.shall include a continuity check of output devices.AFD shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.A CHANNEL CALIBRATION shall be the adjustment.
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| as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass the entire channel. including the required sensor.alarm. -interlock.
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| display. and trip functions.
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| 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.
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| overlapping calibrations or total channel steps so that the entire channel is calibrated.
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| BRAIDWOOD
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| -UNITS 1 & 2 1.1-1 Amendment 98 Definitions 1.1 1.1 Definitions CHANNEL CHECK CHANNEL OPERATIONAL TEST (COT)CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation.
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| 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.
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| A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions.
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| The COT shall include adjustments, as necessary, of the required alarm, interlock.
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| and trip setpoints so that the setpoints are within the required range and accuracy.CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Unit operation within these limits is addressed in individual Specifications.
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| BRAIDWOOD
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| -UNITS 1 & 2 1.1 -2 Amendment 98 Definitions 1.1 1.1 Definitions DOSE EQUIVALENT 1-131 DOSE EQUIVALENT XE-133 ENGINEERED SAFETY FEATURE (ESF) RESPONSE TIME DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The determination of DOSE EQUIVALENT 1-131 shall be performed using the Committed Effective Dose Equivalent (CEDE) dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. II, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion." DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity.
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| The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soi 1. " The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF 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.
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| 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.
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| In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. BRAIDWOOD
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| -UNITS 1 &2 1.1-3 Amendment 162 Definitions
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| * " 1.1 1.1 Definitions LEAKAGE LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE, such as that from pump seals or valve packing (except Reactor Coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;2. LEAKAGE into the containment 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; or 3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE);b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE;c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE)through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing each master relay and verifying the OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.BRAIDWOOD
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| -UNITS 1 & 2 1.1- 4 Amendment 144 Definitions
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| : 1. 1 1.1 Definitions MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature.
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| and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.OPERABLE -OPERABILITY PHYSICS TESTS A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train.component, or device to perform its specified safety function(s) are a so capable of performing their related support function(s).
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| PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation.
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| These tests are: a. Described in Chapter 14, Initial Test Program.of the UFSAR: b. Authorized under the provisions of'10 CFR 50.59: or c. Otherwise approved by the Nuclear Commission.
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| Regulatory BRAIDWOOD
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| -UNITS 1 & 2 1.1 -5 Amendment 98
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| ===1.1 Definitions===
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| PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) QUADRANT POWER TILT RATIO (QPTR) RATED THERMAL POWER CRTP) REACTOR TRIP SYSTEM CRTS) RESPONSE TIME RECENTLY IRRADIATED FUEL BRAIDWOOD
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| -UNITS 1 & 2 Definitions 1.1 The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits including heatup and cooldown rates, and the pressurizer Power Operated Relief Valve (PORV) lift settings for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6. QPTR shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3645 MWt. The RTS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage. 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.
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| In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. Fuel that has occupied part of a critical reactor core within the previous 48 hours. Note that all fuel that has been in a critical reactor core is referred to as irradiated fuel. 1.1-6 Amendment No. 174 Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN (SDM)SDM shall be-the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming: a. All Rod Cluster Control Assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn.
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| With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM: and b. In MODES 1 and 2. the fuel and moderator temperatures are changed to the hot zero power temperature.
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| SLAVE RELAY TEST STAGGERED TEST BASIS THERMAL POWER A SLAVE RELAY TEST shall consist of energizing each slave relay and verifying the OPERABILITY of each slave relay. The SLAVE-RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems.
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| channels, or other designated components during the interval specified by the Surveillance Frequency.
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| so.that all systems, subsystems.
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| 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 shall be the-total reactor core heat transfer rate to the reactor coolant.BRAIDWOOD
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| -UNITS 1 & 2 1.1 -7 Amendment 98 Definitions 1.1 1.1 Definitions TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)A TADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of required alarm, interlock, display. and trip functions.
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| The TADOT shall include adjustment, as necessary.
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| of the trip actuating device so that it actuates at the required setpoint within the required accuracy.BRAIDWOOD
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| -UNITS 1 & 2 1.1 -8 Amendment 98 MODE TITLE 1 Power Operation 2 Startup 3 Hot Standby 4 Hot Shutdown(b) 5 Co 1 d Shutdown(b) 6 Refue 1 i ngrcJ (a) Exe 1 udi ng decay heat. Table 1.1-1 (page 1 of 1) MODES % RATED REACTIVITY THERMAL CONDITION POWER( a) ( ko++) 2 0.99 > 5 2 0.99 5 < 0.99 NA < 0.99 NA < 0.99 NA NA NA Definitions
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| ===1.1 AVERAGE===
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| REACTOR COOLANT TEMPERATURE (oF) NA NA 2 350 350 > TilVO > 200 200 NA (b) All required reactor vessel head closure bolts fully tensioned. (c) One or more required reactor vessel head closure bolts less than fully tensioned.
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| BRAIDWOOD
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| -UNITS 1 & 2 1.1 -9 Amendment 186 Logical Connectors 1.2 1.0 USE AND APPLICATION
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| ===1.2 Logical===
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| Connectors PURPOSE The purpose of this section is to explain the meaning of logical connectors.
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| Logical connectors are used in Technical Specifications (TS)to discriminate between. and yet connect, discrete Conditions, Required Actions. Completion Times, Surveillances, and Frequencies.
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| 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 indentations of the logical connectors.
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| When, logical connectors are used to state a Condition.
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| 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.
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| Completion Time. Surveillance.
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| or Frequency.
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| EXAMPLES The following examples illustrate connectors.
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| the use of logical BRAIDWOOD
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| -UNITS 1 & 2 1.2- 1 Amendment 98 Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)
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| EXAMPLE 1.2-1 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.
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| BRAIDWOOD
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| -UNITS 1 & 2 1.2 -2 Amendment 98 Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)
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| EXAMPLE 1.2-2 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.
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| 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.
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| 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 theological 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.
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| BRAIDWOOD
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| -UNITS 1 & 2 1.2 -3 Amendment 98 Completion Times 1.3 1.0 USE AND APPLICATION
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| ===1.3 Completion===
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| 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.
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| If situations are discovered that require entry into more than one Condition at a time within a single LCO (multiple Conditions).
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| 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.
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| Once a Condition has been entered, subsequent trains.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.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 1.3- 1 Amendment 98 Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)
| |
| However, when a subsequent train, 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:
| |
| : 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 hours: or b. The stated Completion Time as measured from discovery of the subsequent inoperability.
| |
| The.above Completion Time extension does not apply to those Specifications that have exceptions that allow completely separate-re-entry into the Condition (for each train.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 hours," 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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -2 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
| |
| EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours met.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 6 hours AND in MODE 5 within 36 hours. A total of 6 hours is allowed for reaching MODE 3 and a total of 36 hours (not 42 hours) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours. the time allowed for reaching MODE 5 is the next 33 hours because the total time allowed for reaching MODE 5 is 36 hours.If Condition B is entered while for reaching MODE 5 is the next in MODE 3. the time allowed 36 hours.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -3 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-2 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. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours met.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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -4 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| 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.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 OPERAB[E status was the first inoperable pump. A.24 hour extension to the stated 7 days is allowed. provided this does not result in the second pump being inoperable for> 7 days.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -5 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X train train to OPERABLE AND inoperable.
| |
| status.10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours Function Y Function Y train train to OPERABLE AND inoperable.
| |
| status.10 days from discovery of failure to meet the LCO C. One C.1 Restore 72 hours Function X Function X train train to OPERABLE inoperable.
| |
| status.AND OR One C.2 Restore 72 hours Function Y Function Y train train to OPERABLE inoperable.
| |
| status.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -6 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| When one Function X train and one Function Y train are inoperable.
| |
| Condition A and Condition B are concurrently applicable.
| |
| The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train 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 train 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 aMlows 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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -7 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) 4 hours valves to OPERABLE inoperable.
| |
| status.B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours met.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 hours provided this does not result in any subsequent valve being inoperable for > 4 hours.If the Completion Time of 4 hours (plus the extension) expires while one or more valves are still inoperable.
| |
| Condition B is entered.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -8 Amendment
| |
| : 98.
| |
| Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-5 ACTIONS Separate Condition valv.-n-t-y -NOTE --a f entry is allowed for each inoperable CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours valves OPERABLE status.inoperable.
| |
| B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours met.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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -9 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| 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.EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per inoperable.
| |
| SR 3.x.x.x. 8 hours OR A.2 Reduce THERMAL 8 hours POWER to< 50% RTP.B. Required B.1 Be in MODE 3. 6 hours Action and associated Completion Time not met.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -10 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| 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 hour interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour 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 hours 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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -11 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour subsystem subsystem inoperable.
| |
| isolated.
| |
| AND Once per 8 hours thereafter AND A.2 Restore subsystem 72 hours to OPERABLE status.B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2. Be in MODE 5. 36 hours met.Required Action A.1 has two Completion Completion Time begins at the time the and each "Once per 8 hours thereafter" performance of Required Action A.1.Times. The 1 hour Condition is entered interval begins upon BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -12 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour or any subsequent 8 hour 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.IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -13 Amendment 98 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 Limiting Condition for Operation CLCO). -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.
| |
| 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.
| |
| Sometimes special situations dictate when the requirements of a.Survei11ance 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 1.4-5 discusses these special situations.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -I1 Amendment 98 Frequency 1.4 1.4 Frequency DESCRIPTION (continued)
| |
| The use of "met" or "performed" in these instances conveys specific meaning. 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.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. The examples do not reflect the potential application of LCO 3.0.4.b.BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -2 Amendment 134 Frequency 1.4 1.4 Frequency EXAMPLES (continued)
| |
| EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours) 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 hours, an extension of the time interval to 1.25 times the stated 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 Example 1.4-3). 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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -3 Amendment 98 Frequency 1.4 1.4 Frequency EXAMPLES (continued)
| |
| EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours after 2 25% RTP AND 24 hours 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 2 25% RTP. the Surveillance must be performed within 12 hours.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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -4 Amendment 98
| |
| --.Frequency 1.4 1.4 Frequency EXAMPLES (continued)
| |
| EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY----NOTED Not required to be performed until 12 hours after 2 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 hours after power reaches 2 25% RTP to perform the Surveillance.
| |
| The Surveillance is still considered to be performed within the"specified Frequency." Therefore.
| |
| if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval.
| |
| 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 hours with power a 25% RTP.Once the unit reaches 25% RTP. 12 hours would be allowed for completing the Surveillance.
| |
| If the Surveillance were not performed within this 12 hour 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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -5 Amendment 98 Frequency 1.4 1.4 Frequency EXAMPLES (continued)
| |
| EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-NO4TE----Only required to be performed in MODE 1.Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1. 2, or 3 (the assumed Applicability of the associated LCO) between performances.
| |
| As the Note modifies the required performance of the Surveillance, the note is construed to be part of the"specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1. this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance.
| |
| The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to MODE 1. Therefore.
| |
| if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1. 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 result in entry into MODE 1.Once the unit reaches MODE 1. the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Survei11ance had been performed.
| |
| If the Surveillance were not performed prior to MODE 1. there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -6 Amendment 98 Frequency 1.4 1.4 Frequency EXAMPLES (continued)
| |
| EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY--NOTE--Only required to be met in MODE 1.Verify leakage rates are within limits. 24 hours Example 1.4-5 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 hour interval (plus the extension allowed by SR 3.0.2).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 hour Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour Frequency were not met), SR 3.0.4 would require satisfying the SR.BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -7 Amendment 98 SLs 2.0 2.0 SAFETY LIMITS CSLs) 2.1 Sls 2.1.1 Reactor Core Sls In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System CRCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following Sls shall not be exceeded.
| |
| 2.1.1.1 In MODE 1, the Departure from Nucleate Boiling Ratio CDNBR) shall be 1.24 for the WRB-2 DNB correlation for a thimble cell, 1.25 for the WRB-2 DNB correlation for a typical cell 1.19 for the ABB-NV DNB correlation for a thimble cell and a typical cell. 2.1.1.2 In MODE 2, the DNBR shall be 1.17 for the WRB-2 DNB correlation, 1.13 for the ABB-NV DNB correlation 1.18 for the WLOP DNB correlation.
| |
| 2.1.1.3 In MODES 1 and 2, the peak fuel centerline temperature shall be maintained as follows: a. < 5080°F decreasing by 58°F per 10,000 MWD/MTU burnup for Westinghouse fuel, b. < 5173°F decreasing by 65°F per 10,000 MWD/MTU burnup for AREVA NP fuel (Unit 1 only), and c. < 5189°F decreasing by 65°F per 10,000 MWD/MTU burnup for AREVA NP fuel containing Gadolinia (Unit 1 only). 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained
| |
| :-::; 2735 psig. 2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour. 2.2.2 If SL 2.1.2 is violated:
| |
| 2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour. 2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes. BRAIDWOOD
| |
| -UNITS 1 & 2 2.0 -1 Amendment No. 174 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 hour to place the unit, as applicable, in: a. MODE 3 within 7 hours: b. MODE 4 within 13 hours: and c. MODE 5 within 37 hours.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. 3. and 4.BRAIDWOOD
| |
| -UNITS 1 & 2 3.0 -1 Amendment 98 LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made: a. 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;b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or c. When an allowance is stated in the individual value, parameter, or other Specification.
| |
| This Specification shall not prevent changes in MODES or other specified conditions in the Ap licability that are required to comply with ACTIONS or that are part of a shutdown of the unit.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 required testing to demonstrate OPERABILITY.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.0 -2 Amendment 134 LCO Applicability 3.0 3.0 LCO Applicability 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, an evaluation shall be performed in accordance with Specification 5.5.15, "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 system's 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.BRAIDWOOD
| |
| -UNITS 1 & 2 3.0 -3 Amendment 98 LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.7 Exception LCOs allow specified Technical Specification (TS)requirements to be changed to permit performance of special tests and operations.
| |
| Unless otherwise specified, all other TS requirements remain unchanged.
| |
| Compliance with Exception LCOs is optional.
| |
| When an Exception LCO is desired to be met but is not met, the ACTIONS of the Exception LCO shall be met. When an Exception LCO is not desired to be met.entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.
| |
| LCO 3.0.8 LCOs. including associated ACTIONs, shall apply to each unit individually, unless otherwise indicated.
| |
| Whenever the LCO refers to a system or component that is.shared by both units, the ACTIONs will apply to both units simultaneously.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.0- 4 Amendment 98 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 erform 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.
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| Exceptions to this Specification are stated in the individual Specifications.
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| BRAIDWOOD
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| -'UNITS 1 & 2 3.0- 5 Amendment 98 SR Applicability 3.0 3.0 SR APPLICABILITY 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 hours or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance.
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| A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed.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.SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4 This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.SR 3.0.5 SRs shall apply to each unit individually, unless otherwise indicated.
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| BRAIDWOOD
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| -UNITS 1 & 2 3.0 -6 Amendment 134 SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN LCO 3.1.1 SDM shall be within the limits specified in the APPLICABILITY:
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| MODE 2 with < 1.0, kffif MODES 3, 4, and 5. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore SDM to within 1 imit. 15 minutes SURVEILLANCE SR 3.1.1.1 Verify SDM is with-in the limits specified in the COLR.
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| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.1.1 1 Amendment Core Reactivity 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity LCO 3.1.2 The measured core predicted values.reactivity shall be within +/- 1% Ak/k of APPLICABILITY:
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| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core A.1 Re-evaluate core 7 days reactivity not within design and safety limit. analysis.
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| and determine that the reactor core is acceptable for continued operation.
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| AND A.2 Establish appropriate 7 days operating restrictions and SRs.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met.BRAIDWOOD
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| -UNITS 1 & 2 3.1.2 -1 Amendment 98 Core Reactivity
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| | |
| ====3.1.2 SURVEILLANCE====
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| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify measured core reactivity is within Prior to +/- 1%
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| of predicted values. entering MODE 1 after each refueling SR 3.1.2.2 -----------
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| : 1. Only required to be performed after 60 Effective Full Power Days (EFPD). 2. The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 EFPD after each fuel loading. Verify measured core reactivity is within In accordance
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| +/- 1%
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| of predicted values. with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 & 2 3.1.2 2 Amendment MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)LCO 3.1.3 APPLICABILITY:
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| The MTC shall be maintained within the limits specified in the COLR. The maximum upper limit shall be that specified in Figure 3.1.3-1.MODE 1 and MODE 2 with keff 2 -1.0 for the upper MTC limit.MODES 1. 2. and 3 for the lower MTC limit.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper A.1 Establish 24 hours limit. administrative withdrawal limits for control banks to maintain MTC within limit.B. Required Action and B.1 Be in MODE 2 with 6 hours associated Completion keff < 1.0.Time of Condition A not met.C. MTC not within lower C.1 Be in MODE 4. 12 hours limit.BRAIDWOOD
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| -UNITS 1 & 2 3.1.3 -1 Amendment 98 MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within upper limit. Prior to entering MODE 1 after each refueling SR 3.1.3.2 -NOTES- --1. Not required to be performed until 7 Effective Full Power Days (EFPD)after reaching the equivalent of an equilibrium RTP All Rods Out (ARO)boron concentration of 300 ppm.2. If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR.SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.3. SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of < 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR.Verify MTC is within lower limit. Once each cycle BRAIDWOOD
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| -UNITS 1 & 2 3.1.3 -2 Amendment 98 MTC 3.1.3 0 C.)E.0 P-4 Ed Q 0 H-4.A:D Ed 04-4¢-a E-C4 9 8 7 6 5 4 3 UNACCEPTABLE OPERATI ON ACCEPTj OPERAI ABLE'ION 50 60 70 80 90 100 21 I 0'1 0 10 20 30 40 PERCENT RTP Figure 3.1.3-1 (page 1 of 1)Moderator Temperature Coefficient vs. Power Level BRAIDWOOD
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| -UNITS 1 & 2 3.1.3 -3 Amendment 98 Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and control rods shall be OPERABLE.AND Individual indicated rod positions shall be within 12 steps of their group step counter demand position.APPLICABILITY:
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| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod(s) A.1.1 Verify SDM is within 1 hour inoperable.
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| the limits specified in the COLR.OR A.1.2 Initiate boration to 1 hour restore SDM to within limit.AND A.2 Be in MODE 3. 6 hours (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.1.4 -1 Amendment 98 Rod Group Alignment Limits 3.1.4 ACTIONS (continued)
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| CONDITION REQUIRED ACTION ICOMPLETION TIME B. One rod not within I alignment limit.B.1.1 Verify 5DM is within the limits specified in the COLR.OR B.1.2 Initiate boration to restore SDM to within limit.AND B.2 B.3 AND B.4 Reduce THERMAL POWER to 5 75% RTP.Verify SDM is within the limits specified in the COLR.Determine Heat Flux Hot Channel Factor (Fa(Z)) and Nuclear Enthalpy Rise Hot Channel Factor (FNH)-1 hour 1 hour 2 hours from discovery of Condition B concurrent with inoperability of Power Distribution Monitoring System (PDMS)Once per 12 hours 72 hours (continued)
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| AND A. A.BRAIDWOOD
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| -UNITS 1 & 2 3.1.4 Amendment 110 Fe, ^ .-11.
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| Rod Group Alignment Limits 3.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
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| B.5 Re-evaluate safety 5 days analyses and confirm results remain valid for duration of operation under these conditions.
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| C. More than one rod not C.1.1 Verify SDM is within 1 hour within alignment the limits specified limit. in the COLR.OR C.1.2 Initiate boration to 1 hour restore required SDM to within limit.AND C.2 Be in MODE 3. 6 hours from discovery of Condition C concurrent with inoperability of PDMS AND C.3 -NOTE Only required to be performed when PDMS is OPERABLE.Restore rod(s) to 72 hours within alignment limit.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.1.4 -3 Amendment 110 FEB 1 Zr 2J:?
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| Rod Group Alignment Limits 3.1.4 ACTIONS (continued)
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| CONDITION REOU I RED ACTI ON COMPLETION TIME D. Required Action and associated Completion Time of Condition B or Required Action C.3 not met. D.1 Be in MODE 3. 6 hours SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.1.4.1 Verify individual alignment limit. rod positions within In accordance with the Surveillance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.
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| In accordance with the Surveillance Frequency Control Program SR 3.1.4.3 Verify rod drop time of each rod, from the fully withdrawn position, is 2.7 seconds from the beginning of decay of stationary gr-j pper coil voltage to dashpot entry, with: a. Tavg 550°F; and b. All reactor coolant pumps operating.
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| Prior to cri t i ca 1 ity after each removal of the reactor head BRAIDWOOD
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| -UNITS 1 & 2 3.1.4 -4 Amendment Shutdown Bank Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be within the insertion limits specified in the COLR.-NOTE- -w p o-- g not applicable while performing This LCO is SR 3.1.4.2.APPLICABILITY:
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| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown A.1.1 Verify SDM is within 1 hour banks not within the limits specified limits. in the COLR.OR A.1.2 Initiate boration to 1 hour restore SDM to within limit.AND A.2 Restore shutdown 2 hours bank(s) to within limits.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met.BRAIDWOOD
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| -UNITS 1 & 2 3.1.5 -1 Amendment 98 Shutdown Bank Insertion SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1. 5.1 Verify each shutdown bank is within the insertion limits specified in the COLR. 3.1.
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| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 & 2 3.1.5 -2 Amendment Control Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO 3.1.6 Each control bank shall be within the insertion, sequence.and overlap limits specified in the COLR.This LCO is t ap--i --NOTE--- i --not applicable while performing SR 3.1.4.2.APPLICABILITY:
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| MODE 1.MODE 2 with keff 2 1.0.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank insertion A.1.1 Verify SDM is within 1 hour limits not met. the limits specified in the COLR.OR A.1.2 Initiate boration to 1 hour-restore SDM to within limit.AND A.2 Restore control 2 hours bank(s) to within .limits.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.1.6 -1 Amendment 98 Control Bank Insertion Limits 3.1.6 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank sequence or overlap limits not met. B.1.1 OR Verify SDM is within the limits specified in the COLR. 1 hour B.1.2 AND Initiate boration to restore SDM to within 1 imit. 1 hour C. Required Action and associated Completion Time not met. B.2 C.1 Restore control bank sequence and overlap to within limits. Be in MODE 2 with keff < 1. O. 2 hours 6 hours SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.1.6.1 Verify estimated critical control bank position is within the limits specified in the COLR. Within 4 hours prior to criticality SR 3.1.6.2 Verify each control bank is within the insertion limits specified in the COLR. In accordance with the Surveillance Frequency Control Program (continued)
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| BRAIDWOOD
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| -UNITS 1 &2 3.1.6 -2 Amendment 165/165 Control Bank Insertion SURVEILLANCE REQUIREMENTS (continued)
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| SURVEILLANCE SR 3.1. 6.3 Verify each control bank not fully withdrawn from the core is within the sequence and overlap limits specified in the COLR.
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| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.1.6 3 Amendment I Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 APPLICABILITY:
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| The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System-shall be OPERABLE.MODES 1 and 2.ACTIONS t InTr-__-_-Fu-"I ll I-Separate position_II." I _Condition entry is allowed for each inoperable DRPI indicator.
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| and each demand CONDITION REQUIRED ACTION COMPLETION TIME A. One DRPI per group A.1 Verify the position Once per 8 hours inoperable for one or of the rods with more groups. inoperable DRPIs.OR A.2 Reduce THERMAL POWER 8 hours to s 50% RTP.B. One or more rods with B.1 Initiate action to Immediately inoperable DRPIs have verify the position been moved in excess of the rods with of 24 steps in one inoperable DRPIs.direction since the last determination of OR the rod's position.B.2 Reduce THERMAL POWER 8 hours to s 50% RTP.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.1.7-1 Amendment 110 FEB 'L SO 201 Rod Position Indication
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| ====3.1.7 ACTIONS====
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| (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME C. One demand position C.1.1 Verify by Once per 8 hours indicator per bank administrative means inoperable for one or all DRPIs for the more banks. affected bank(s) are OPERABLE.C;1.2 Verify the most Once per 8 hours withdrawn rod and the least withdrawn rod of the affected bank(s) are S 12 steps apart.OR C.2 Reduce THERMAL POWER 8 hours to < 50X RTP.D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time not met.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each DRPI agrees within 12 steps of Prior to the group demand position for the full criticality indicated range of rod travel. after each removal of the reactor head.BRAIDWOOD
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| -UNITS 1 & 2 3.1.7-2 Amendment 98 PHYSICS TESTS Exceptions -MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions -MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS. the requirements of LCO LCO LCO LCO LCO 3.1.3.3.1.4.3.1.5.3.1.6.3.4.2."Moderator Temperature Coefficient (MTC)": "Rod Group Alignment Limits": "Shutdown Bank Insertion Limits": "Control Bank Insertion Limits": and"RCS Minimum Temperature for Criticality" may be suspended, provided: a. Reactor Coolant System (RCS) lowest loop average temperature is 2 530 0 F: b. SDM is within the limits specified in the COLR: and c. THERMAL POWER is s 5% RTP.APPLICABILITY:
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| MODE 2 during PHYSICS TESTS.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.. SDM not within limit. A.1 Initiate boration to 15 minutes restore SDM to within limit.AND.A.2 Suspend PHYSICS TESTS 1 hour exceptions.
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| B. THERMAL POWER not B.1 Open reactor trip Immediately within limit. breakers.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.1.8 -1 Amendment 98 PHYSICS TESTS Exceptions-MODE 2 3.1.8 ACTIONS (continued)
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| CONDITION REQU I RED ACTI ON COMPLETION TIME C. RCS lowest loop average not within imit. C.1 Restore RCS lowest loop average temperature to within 1 imit. 15 minutes D. Required Action and associated Completion Time of Condition C not met. 0.1 Be in MODE 3. 15 minutes SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.1.8.1 Perform CHANNEL OPERATIONAL TEST on power range and -j ntermedi ate range channel s per SR 3.3.1.7, SR 3.3.1.8, and Table 3.3.1.1-1.
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| Prior to initiation of PHYSICS TESTS SR 3.1.8.2 Verify the RCS lowest loop average temperature is 530°F. In accordance with the Surveillance Frequency Control Program SR 3.1.8.3 Verify THERMAL POWER is 5% RTP. In accordance with the Surveillance Frequency Control Program SR 3.1.8.4 Ve rify SDM is wi th-j n the 1-j mits speci fi ed in the COLR. In accordance with the Su rvei 11 ance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.1.8-2 Amendment I Fo(Z)3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))LCO 3.2.1 Fo(Z). as approximated by Fo(Z) and Fo(Z). shall be within the limit specified in the COLR.I APPLICABILITY:
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| MODE 1.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fo(Z) not within A.1 Reduce THERMAL POWER 15 minutes limit. k 1% RTP for each 1% Fo(Z) exceeds limit.AND A.2 Reduce Power Range 72 hours Neutron Flux- High trip setpoints 2 1%for each 1% Fo(Z)exceeds limit.AND A.3 Reduce Overpower AT 72 hours trip setpoints 2 1%for each 1% Fo(Z)exceeds limit.B. Fo(Z) not within B.1 Reduce THERMAL POWER 4 hours limit. k 1% RTP for each 1% Fo(Z) exceeds limit.AND (conti nued)BRAIDWOOD
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| -UNITS 1 & 2 3.2.1 -1 Amendment 110 FEB I 3 2 0o I F 0 (Z)3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
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| B.2 Reduce Power Range 72 hours Neutron Flux-High trip setpoints
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| ; 1%for each 1% Fow(Z)exceeds limit.AND B.3 Reduce Overpower AT 72 hours trip setpoints 2 1X for each 1% Fw(Z)exceeds limit.C. Required Action and C.1 Be in MODE 2. 6 hours associated Completion Time not met.I BRAIDWOOD
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| -UNITS 1 & 2 3.2.1 -2 Amendment 110 FED I :3 2aIl SURVEILLANCE SURVEI SR -------NOTES -----During power escalation at the beginning of each cycle, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained. Not required to be performed until 12 hours after declaring Power Distribution Monitoring System (PDMS)inoperable.
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| Performance of SR 3.2.1.3 satisfies the initial performance of this SR after declaring PDMS inoperable.
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| Verify is within limit specified in the COLR.
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| Prior to exceeding 75% RTP after each refueling AND Once within 12 hours after achieving equil i bri um conditions after exceeding, by 2 10% RTP, the THERMAL POWER at whi ch F5 (D was last verified In accordance with the Surveillance Frequency Control Program (continued)
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| BRAIDWOOD
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| -UNITS 1 &2 3.2.1 -3 Amendment 165/165 F 0 (Z)3.2.1 SURVEILLANCE REQUIREMENTS (continued)
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| SURVEILLANCE FREQUENCY SR 3.2.1.2 NOTES 1. During power escalation at the beginning of each cycle. THERMAL POWER may be increased until an equilibrium power level has been achieved.
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| at which a power distribution map is obtained.2. If Fo(Z) measurements indicate that the[ Fo(Z) 1 maximum over z K(Z) j has increased since the previous evaluation of Fo(Z): a. Increase Fo"(Z) by the greater of a factor of 1.02 or by an appropriate factor specified in the COLR and reverify Fo(Z) is within limits specified in the COLR; or b. Repeat SR 3.2.1.2 once per 7 EFPD until either a. above is met or two successive flux maps indicate that the[ F. (Z)1 maximum over z K(Z)has not increased.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.2.1- 4 Amendment 110.FE13 1 3 -a2l SURVEILLANCE REQUIREt"IENTS SR 3.2.1.2 (continued) Not required to be performed until 12 hours after declaring PDMS inoperable.
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| Performance of SR 3.2.1.4 satisfies the initial performance of this SR after declaring PDMS inoperable.
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| Verify (Z) is wi thi n 1 i mi t specifi ed in the COLR.
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| Prior to exceeding 75% RTP after each refueling Once within 12 hours after achieving equi l-j br-j um conditions after exceeding, by 10% RTP, the THERMAL POWER at whi ch was last verified In accordance with the Surveillance Frequency Control Program (cont -j n ued ) BRAIDWOOD
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| -UNITS 1 &2 3.2.1 -Amendment 165/165 Fo(l) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)
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| SURVEILLANCE FREQUENCY SR 3.2.1.3 Only required to be performed when PDMS is OPERABLE.
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| Verify Fg(n the COLR. is within limit specified in In accordance with the Surveillance Frequency Control Program SR 3.2.1.4 --NOTE --Only required to be performed when PDMS is OPERABLE.
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| Verify F;(Z) the COLR. is within limit specified in In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.2.1 6 Amendment FNH 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F&H)I LCO 3.2.2 APPLICABILITY:
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| F&H shall be within the limit specified in the COLR.MODE 1.I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----NOTE -A.1 Reduce THERMAL POWER 4 hours Required Actions A.2 to < 50% RTP.and A.4 must be completed whenever AND Condition A is entered. A.2 Determine F&H. 24 hours AND F^H not within limit.A.3 Reduce Power Range 72 hours Neutron Flux- High trip setpoints to< 55% RTP.AND (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.2.2 -1 Amendment 110 FEB 1 3 2O31 3NAH 3.2.2 I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
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| A.4 NOTE THERMAL POWER does not have to be reduced to comply with this Required Action.Determine F&H* Prior to exceeding 50% RTP AND Prior to exceeding 75% RTP AND 24 hours after reaching 2 95% RTP B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time not met.BRAIDWOOD
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| -UNITS 1 & 2 3.2.2 -2 Amendment 110.E3 D I 2-31 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 -------------NOTE-
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| --------Not requi red to be performed untn 12 hours after declaring POMS inoperable.
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| Performance of SR 3.2.2.2 satisfies the initial performance of this SR after declaring POMS Verify is within limits specified in COLR. SR 3.2.2.2 --------------NOTE----Only required to be performed when POMS is OPERABLE.
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| Verify F: H is with-j n 1 imit specifi ed in the COLR. Prior to exceeding 75% RTP after each refueling In accordance with the Surveillance Frequency i Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.2.2 3 Amendment AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE LCD 3.2.3 The AFD shall be maintained within the limits specified the COLR. ------------
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| ---NOTE The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits. APPLICABILITY:
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| MODE 1 with THERMAL POWER 50% RTP when Power Distribution Monitoring System (PDMS) is inoperable.
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| ACTIONS CONDITION REQU I RED ACTI ON COMPLETION TIME A. AFD not within limits. A.l Reduce THERMAL POWER 30 mi nutes to < 50% RTP. SURVEILLANCE SURVEI SR ---------NOTE-------
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| -------Not required to be performed until 12 hours after declaring PDMS inoperable.
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| Verify AFD is within limits for each OPERABLE excore channel.
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| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.2.3 1 Amendment I QPTR 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)LCO 3.2.4 APPLICABILITY:
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| The QPTR shall be s 1.02.MODE 1 with THERMAL POWER > 50% RTP when Power Distribution Monitoring System (PDMS) is inoperable.
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| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit. A.1 Reduce THERMAL POWER 2 hours after 2 3% from RTP for each QPTR each 1% of QPTR determination
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| > 1.00.AND A.2 Determine QPTR and Once per reduce THERMAL POWER 12 hours 2 3% from RTP for each 1% of QPTR> 1.00.AND A.3 Perform SR 3.2.1.1. 24 hours after SR 3.2.1.2. and achieving SR 3.2.2.1. equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter AND (continued)
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| I BRAIDWOOD
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| -UNITS 1 & 2 3.2.4 -1 Amendment 110 FEB 13 2aO1.
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| QPTR 3.2.4 ACTIONS CONDITION I REQUIRED ACTION I COMPLETION TIME A. (continued)
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| A.4 Re-evaluate safety analyses and confirm results remain valid for duration of operation under this condition.
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| AND A. 5-----NOTES------
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| : 1. Perform Required Action A.5 only after Required Action A.4 is completed.
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| : 2. Required Action A.6 shall be completed whenever Required Action A.5 is performed.
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| Prior to exceeding the THERMAL POWER limit of Required Action A.1 Prior to exceeding the THERMAL POWER limits of Required Action A.1.(continued)
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| Normalize excore detectors to restore QPTR to within limits.AND BRAIDWOOD
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| -UNITS 1 & 2 3.2.4 -2 Amendment 98 I QPTR 3.2.4 I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
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| A.6 NOTE Perform Required Action A.6 only after Required Action A.5 is completed.
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| Perform SR 3.2.1.1. 24 hours after SR 3.2.1.2. and achieving SR 3.2.2.1. equilibrium conditions at RTP not to exceed 48 hours after exceeding the THERMAL POWER limit of Required Action A.1 B. Required Action and B.1 Reduce THERMAL POWER 4 hours associated Completion to 5 50% RTP.Time not met.BRAIDWOOD
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| -UNITS 1 & 2 3.2.4 -3 Amendment 110 FEB 13 2001 QPTR 3.2.4 SLiRVEI LLANCE REQLI I REMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 -------------
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| NOTES --------------
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| : 1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER $ 75% RTP, the remaining three power range channel inputs can be used for calculating QPTR. 2. SR 3.2.4.2 may be performed in lieu of this Surveillance.
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| : 3. Not required to be performed until 12 hours after declaring PDMS i noperab 1 e. Verify QPTR is $ 1.02 by calculation.
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| In accordance with the Surveillance Frequency Control Program SR 3.2.4.2 ----------------
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| NOTES ------------------
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| : 1. Not required to be performed until 12 hours after input from one Power Range Neutron Flux channel is inoperable with THERMAL POWER > 75% RTP. 2. Not required to be performed until 12 hours after declaring PDMS i noperab 1 e. Verify QPTR is $ 1.02 using the movable In accordance incore detectors.
| |
| with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.2.4 4 Amendment DNBR 3.2.5 3.2 POWER DISTRIBUTION LIMITS 3.2.5 Departure from Nucleate Boning Ratio LCO 3.2.5 DNBR shall be within the limit specified in the APPLICABILITY:
| |
| MODE 1 with THERMAL POWER 50% RTP when Power Monitoring System (PDMS) is OPERABLE.
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DNBR not within limit. A.1 Restore ONBR to within limit. 2 hours B. Required Action and associated Completion Time not met. B.1 Reduce THERMAL POWER to < 50% RTP. 4 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.5.1 Verify DNBR is within limit specified in the COLR.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.2.5 1 Amendment
| |
| | |
| 3.3.1 RTS Instrumentation ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. One channel inoperable.
| |
| or train While this LCO is not met for Function 18, 19, or 20 in MODE 5, making the Rod Control System capable of rod withdrawal is not permitted.
| |
| C.1 Restore channel or train to OPERABLE status. 48 hours OR C.2.1 Initiate action to fully insert all rods. 48 hours AND C.2.2 Place the Rod Control System in a condition incapable of rod withdrawal.
| |
| 49 hours BRAIDWOOD UNITS 1 &2 3.3.1-2 Amendment ACTIONS (continued)
| |
| CONDITION D. One Power Range Neutron Flux-High channel inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 REQUIRED ACTION -------------NOTE------------
| |
| One channel may be bypassed for up to 12 hours for surveillance testing and setpoint adjustment.
| |
| D.l OR D.2 Place channel in trip. Be in MODE 3. RTS Instrumentation
| |
| | |
| ====3.3.1 COMPLETION====
| |
| | |
| TIME 72 hours 78 hours (continued) . ' 3.3.1-3 Amendment No. 180 ACTIONS (continued)
| |
| CONDITION E. One channel inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 REQUIRED ACTION -------------NOTE------------
| |
| One channel may be bypassed for up to 12 hours for surveillance testing. E.1 OR E.2 Place channel in trip. Be in MODE 3. RTS Instrumentation
| |
| | |
| ====3.3.1 COMPLETION====
| |
| | |
| TIME 72 hours 78 hours (continued) 3.3.1-4 Amendment No. 180 3.3.1 RTS Instrumentation ACTI ONS (conti n ued ) CONDITION REQUI RED ACTI ON COMPLETION TIME F. One Intermediate Range Neutron Flux channel inoperable.
| |
| F.l Reduce THERMAL POWER to < P-6. OR 2 hours F.2 Increase THERMAL POWER to > P-I0. 2 hours G. Two Intermediate Range Neutron Flux channels inoperable.
| |
| G.l Suspend operations involving positive reactivity additions.
| |
| AND G.2 Reduce THERMAL POWER to < P-6. Imnediately 2 hours H. One Source Range Neutron Flux channel inoperable.
| |
| H.l Suspend operations involving positive reactivity additions.
| |
| Imnediately
| |
| : 1. Two Source Range Neutron Flux channels inoperable.
| |
| 1.1 Open Reactor Trip Breakers (RTBs). Imnediately J. One Source Range Neutron Flux channel inoperable.
| |
| J.l Restore channel to OPERABLE status. OR 48 hours J.2.1 Initiate action to fully insert all rods. AND 48 hours J.2.2 Place the Rod Control System in a condition incapable of rod withdrawal.
| |
| 49 hours (contlnued)
| |
| BRAIDWOOD UNITS 1 &2 3.3.1 5 Amendment 169 ACTIONS (continued)
| |
| CONDITION K. One channel inoperable.
| |
| L. One Turbine Trip channel inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 REQUIRED ACTION ------------NOTES------------
| |
| : 1. For Functions with installed bypass test capability (Functions 8a, 9, 10), one channel may be bypassed for up to 12 hours for surveillance testing. 2. For Functions with no installed bypass test capability (Functions 12 and 13), the inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels.
| |
| -----------------------------
| |
| K.1 Place channel in trip. OR K.2 Reduce THERMAL POWER to< P-7. ------------NOTE-------------
| |
| The inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels.
| |
| -----------------------------
| |
| L.1 Place channel in trip. OR L.2 Reduce THERMAL POWER to < P-8. RTS Instrumentation
| |
| | |
| ====3.3.1 COMPLETION====
| |
| | |
| TIME 72 hours 78 hours 72 hours 78 hours (contlnued) 3.3.1-6 Amendment No. 180 RTS Instrumentation
| |
| | |
| ====3.3.1 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME M. One train inoperable. One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE.
| |
| M.1 OR Restore train to OPERABLE status. M.2 Be in MODE 3. 24 hours 30 hours N. One RTB trai n inoperable.
| |
| One train may be bypassed for up to 4 hours for surveillance testing, provided the other train is OPERABLE. ---N.1 Restore train to OPERABLE status. OR 24 hours N.2 Be in MODE 3. 30 hours O. One or more channels 0.1 Verify interlock is in 1 hour i noperab 1required state for existing unit conditions.
| |
| OR Be in MODE 3. 7 hours (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 -Amendment 169 3.3.1 RTS Instrumentation ACTIONS (continued)
| |
| CONDITION REOUI RED ACTI ON P. One or more channels inoperable.
| |
| P.1 Verify interlock is in required state for existing unit conditions.
| |
| OR 1 hour P.2 Be in MODE 2. 7 hours O. One trip mechanism inoperable for one RTB. 0.1 Restore inoperable trip mechanism to OPERABLE status. OR 48 hours 0.2 Be in MODE 3. 54 hours R. One Reactor Coolant Pump (RCP) Breaker Pos it ion cha nne 1 (per train) inoperable. --
| |
| The inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels.
| |
| --R.1 Place channel in trip. OR 6 hours R.2 Reduce THERMAL POWER to < P-7. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.1 -8 Amendment 169 3.3.1 RTS Instrumentation SURVEILLANCE REQUIREMENTS
| |
| -------------------
| |
| --------NOTE-
| |
| ------------
| |
| Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. In accordance the Surveillance Frequency Control Program SR 3.3.1.2 --------Adjust NIS channel if absolute difference is > 2%. Not required to be performed until 12 hours after THERMAL POWER is 15% RTP. Compare results of calorimetric heat In accordance the balance calculation to Nuclear Instrumentation System (NIS) channel Surveillance output. Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.3.1 -Amendment RTS Instrumentation
| |
| | |
| ====3.3.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.3.1.3
| |
| : 1. Adjust NIS channel if absolute difference is 3%. 2. Only required to be performed with THERMAL POWER> 15% RTP. Compare results of the incore measurements to NIS AFD. Prior to exceeding 75% RTP after each refueling In accordance with the Surveillance Frequency Control Program SR 3.3.1.4 This Surveillance must be performed on the RTBB prior to placing the bypass breaker in service. Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.5 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UN 1 &2 3.3.1 -10 Amendment 3.3.1 RTS Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE QUENCY SR 3.3.1.6 Not required to be performed until 24 hours after THERMAL POWER is 75% RTP. Calibrate excore channels to agree with In accordance incore measurements.
| |
| with the Surveillance Frequency Control Program SR 3.3.1. 7 -----
| |
| : 1. Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours after entry into MODE 3. 2. The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capabi 1 i ty Perform In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.3.1 -11 Amendment 3.3.1 RTS SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.3.1.8
| |
| : 1. This Surveillance shall include verification that interlocks P 6 and P-I0 are in their required state for existing unit conditions.
| |
| : 2. The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capabi 1 ity. Perform COT.
| |
| Only required when not performed within the Frequency specified in the Survei II ance Frequency Control Program Prior to reactor sta rtup Four hours after reducing power below P 10 for power and intermediate instrumentation Four hours after reducing power below P 6 for source range instrumentation (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 -12 Amendment 3.3.1 RTS Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.8 (continued)
| |
| In accordance with the Surve-i 11 ance Frequency Control Program SR 3.3.1.9 -
| |
| Verification of setpoint is not required.
| |
| Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.10 This Surveillance shall include verification that the time constants are adjusted to the prescribed values. Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.3.1.11 Neutron detectors CALIBRATION. are excluded from CHANNEL Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.1 l3 Amendment 171 3.3.1 RTS Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.3.1.12 ----NOTE --------The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
| |
| Perform COT.
| |
| In accordance with the . Survei 11 ance Frequency I Control Program SR 3.3.1.13 ----NOTE --Verification of setpoint is not required.
| |
| Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.14 Verification of setpoint is not required.
| |
| Perform TADOT. Only required when not performed within previous 31 days Prior to reactor startup continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 -14 Amendment 171 3.3.1 RTS SURVEI LLANCE REQU I REMENTS (continued)
| |
| SURVEI LLANCE SR 3.3.1.15 -------------------NOTE---
| |
| -
| |
| Neutron detectors are excluded from response time Verify RTS RESPONSE TIME is within In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.3.1 15 Amendment RTS Instrumentation
| |
| | |
| ====3.3.1 Table====
| |
| 3.3.1-1 (page 1 of 6) Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVE I LLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 1. Manual Reactor Tri p 1,2 2 B SR 3.3.1.13 NA 2 C SR 3.3.1.13 NA 2. Power Range Neutron Flux a. High 1,2 4 0 SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15 s; 110.8% RTP b. Low lib) ,2 4 E SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.15 s; 27.0% RTP 3. Power Range Neutron Flux-High Positive Rate 1,2 4 E SR 3.3.1.7 SR 3.3.1.11 S; 6.2% RTP with time constant 2 sec 4. Intermeciate Range Neutron Fl ux lib), 21cl 2 F,G SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 s; 30.0% RTP 5. Source Range Neutron Flux 2'dl 2 H, I SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.15 s; 1.42 E5 cps 31al, 41al, 5 1a ) 2 I,J SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15 S; 1.42 E5 cps (continued) (al With Rod Control System capable of rod withdrawal or one or more rods not fully inserted. (b) Below the P-I0 (Power Range Neutron Flux) interlock. (c) Above the P-6 (Source Range Block Permissive) interlock. (d) Below the P-6 (Source Range Block Permissive) interlock.
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 -16 Amendment 1 RTS Instrumentation
| |
| | |
| ====3.3.1 Table====
| |
| 3.3.1-1 (page 2 of 6) Reactor Trip System Instrumentation APpLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CONDlTlONS CHANNELS CONDITIONS REQU I REMENTS VALUE Overtemperature 1,2 4 E SR 3.3.1.1 to SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 Overpower 1.2 4 E SR SR SR SR
| |
| : 8. Pressurizer Pressure Low 1 ,,: 4 K SR 3.3.1.1 1875 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 High 1,2 4 E SR 3.3.1.1 2393 psig SR3.3.1.7 SR3.3.1.10 SR 3.3.1.15 1 (c)Water 3 SR 3.3.1.1 93.5% of SR 3.3.1.7 instrument SR 3.3.1.10 span 10. Reactor 1 (El 3 K SR 3.3.1.1 (per loop) SR SR SR 1 (ei (RCP) (per 11. Reactor Cool ant R SR 3.3.1.13 NA (continued) (el Above the P-7 (Low Power Reactor Trips Block) interlock.
| |
| BRAIDWOOD UNITS 1 & 2 3.3.1 Amendment RTS Instrumentation
| |
| | |
| ====3.3.1 Table====
| |
| 3.3.1-1 (page 3 of 6) Reactor Trip System Instrumentation FUNCTION APpLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQU I REMENTS ALLOWABLE VALUE 12. Undervol tage RCPs (per train) 4 K SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.15 :?: 4920 V 13. Underfrequency RCPs (per train) 4 K SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.15 :?: 56.08 Hz 14. (SG) a. Unit 1 1,2 4 E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 :?: 16.1% of narrow range instrument D. Unit 2 1,2 4 E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 2: 34.8% of na rrow range instrument span 15. Turbine Trip a. Emergency Trip Header PressClre (per train) 1 (f) 3 L SR3.3.1.10 SR 3.3.1.14 2: 910 psig b. I(f) 4 L SR 3.3.1.10 SR 3.3.1.14 2: 1% open 16. Safety Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS) 1,2 Z trai ns SR 3.3.1.13 NA (continued) (e) Above the P*7 (Low Power Reactor Trips Block) interlock. (f) Above the P*8 (Power Range Neutron Flux) interlock.
| |
| BRAIDWOOD UNITS 1 & 2 3.3.1 18 Amendment 171 RTS Instrumentation
| |
| | |
| ====3.3.1 Table====
| |
| 3.3.1-1 (page 4 of 6)Reactor Trip System Instrumentation APpLICABLE MODES OR OTHEr< SPECIFIED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE Reactor Trip System Source Range Block 2 0 SR 1.11 ?: 6£*11 amp Penni 5si ve. SR 1.12 Power Block. (1) P*lO 3 P SR 3.3.1.11 NA SR 3.3.1.12 P-13 Input 2 P SR 3.3.1.10 NA SR 3.3.1.12 Power Range 3 P SR 3.3.1.11 ::; 32.1% RTP Neutron Flux. P*8 Sr< 3.3.1.12 1.2 3 0 SR 3.3.1.11 ?: 7.9% RTP and SR 3.3.1.12 ::; 12.1% RTP Turbine l1iu15e 2 P SR 1.10 ::; 12.1% Pressure.
| |
| -13 SR 1.12 turbi ne power Reactor Tri¥ 1.2 2 trains N SR 3.3.1.4 NA Breakers (R Bs) I,) 3(d) I 4: 0) I 5 id) 2 trains C SR 3.3.1.4 NA Reactor Trip Breaker 1.2 1 each per RTB Q SR 3.3.1.4 NA Undervo 1 tage and Shunt ('Trip Mechanisms 3 (3). 4 1 ,). 5(a) 1 each per RTB \., SR 3.3.1.4 NA Automatic Trip Logic 1.2 2 trains M SR 3.3.1.5 NA ('4(3). 5 1a) 2 trains \., SR 3.3.1.5 NA (al With Rod Control System capable of rod witharawal or one or rrore rods not fully inserted. (d) Below the P-6 (Source Range B'ock Pennissive) lnterlock. (g) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB. BRAIDWOOD UNITS 1 & 2 3.3.1 Amendment 3.3.1 AT( 5) [_1_]5 A ( 1+T 2 5) 1+T3 5 RTS Instrumentation Table 3.3.1-1 (page 5 of Reactor Trip System Note 1: Overtemperature 6T The Overtemperature 6T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.04% of 6T span. 6T is measured Reactor Coolant System (RCS) 6T, 6T o is the indicated 6T at RTP, of. sis the Lapl ace transform operator, sec l , T is the measured RCS average temperature, OF. T/ is the nomi na 1 at RTP, :5 *. P is the measured pressurizer pressure, pi is the nominal RCS operating pressure, =K 1 --* K, ,: =
| |
| * K3 T1 =
| |
| * T2
| |
| * T 3 <-T 4 --* T, 5 --* T, 6 <-f l (6I) = *{* + (qt -qb)} when qt -qb <
| |
| * RTP 0% of RTP when
| |
| * RTP :5 qt -qb :5
| |
| * RTP *{ (qt -qb) *} when qt qb >
| |
| * RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP. As specified in the COLR.* BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 Amendment 3.3.1 RTS Instrumentation Table 3.3.1-1 (page 6 of Reactor Trip System Note 2: Overpower The Overpower Function Allowable Value shall not exceed the following Trip Setpoint by more than 3.60% of span. T (l+TI s) [_1_] :::; To {K4 -K5 [_l_J T-K6 [T _1_ -TII]-f2 I)}(1+T2 s) 1+T7 s 1+T6 s 1+T6 s is measured RCS of. is the indicated at RTP, OF. sis the Lapl ace transform operator, sec-I. T is the measured RCS average temperature, OF. Til is the nominal Tav9 at RTP, 5 *. I<s =
| |
| * for -increas-jng Tav9 I\; =
| |
| * when T > Til
| |
| * for decreas-j ng
| |
| * when T 5 1" TI --* T2 --T6 5
| |
| * T 7 --As specified in the COLR.* BRAIDWOOD
| |
| -LIN ITS 1 & 2 3.3.1 -Amendment 171 ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.2 Engineered====
| |
| | |
| Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 APPLICABILITY:
| |
| The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.According to Table 3.3.2-1.ACTIONS Separate Condition entry is allowed--------------
| |
| _ _ _ ___ _ ____ _ ________INU I _for each Function.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in required channels or Table 3.3.2-1 for the trains inoperable.
| |
| channel(s) or train(s).B. One channel B.1 Restore channel to 48 hours inoperable.
| |
| OPERABLE status.OR B.2.1 Be in MODE 3. 54 hours AND B.2.2 Be in MODE 5. 84 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.2 -1 Amendment 98
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION C.1 -------NOTE-
| |
| -----C. One train inoperable.
| |
| One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE.
| |
| Restore train to 24 hours OPERABLE status. OR C.2.1 Be in MODE 3. 30 hours AND C.2.2 Be in MODE 5. 60 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.2 2 Amendment 169 ACTIONS (continued)
| |
| CONDITION D. One channel inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 D.1 OR ESFAS Instrumentation
| |
| | |
| ====3.3.2 REQUIRED====
| |
| ACTION One channel may be bypassed for up to 12 hours for surveillance testing. Place channel in trip. COMPLETION TIME 72 hours D.2.1 Be in MODE 3. 78 hours AND D.2.2 Be in MODE 4. 84 hours (continued) 3.3.2 -3 Amendment No. 180
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation ACTIONS (continued)
| |
| CONDITION REQU I RED ACTI COMPLETION TIlvlE E. One Containment Pressure channel -inoperable.
| |
| E.1 OR E.2.1 AND E.2.2 One additional channel may be bypassed for up to 12 hours for surveillance testing.
| |
| Place channel in bypass. Be in MODE 3. Be in MODE 4. 72 hours 78 hours 84 hours F. One channel inoperable.
| |
| or trai n F.1 OR F.2.1 AND F.2.2 Restore channel or train to OPERABLE status. Be i n
| |
| : 3. Be in MODE 4. 48 hours 54 hours 60 hours (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -4 Amendment 169
| |
| | |
| ====3.3.2 Instrumentation====
| |
| | |
| ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME G. One train inoperable.
| |
| G.I NOTE One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE.
| |
| Restore train to OPERABLE status. OR 24 hours G.2.I Be in MODE 3. AND 30 hours G.2.2 Be in MODE 4. 36 hours H. One channel i noperab 1 e. H.I One channel may be bypassed for up to 2 hours for surveillance testing provided the other channel is OPERABLE.
| |
| Place channel in tr-j p. OR 1 hour H.2.1 Be in MODE 3. AND 7 hours H.2.2 Be in MODE 4. 13 hours (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -5 Amendment 169
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION TIME 1. One channel inoperable.
| |
| 1.1 The inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels.
| |
| OR Place channel in tr-ip. 72 hours 1.2 in MODE 3. 78 hours J. One or more trains inoperable.
| |
| J.1 Declare associated auxiliary feedwater pump inoperable.
| |
| Irrrnediately (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -6 Amendment 169 ACTIONS (continued)
| |
| CONDITION K. One channel i noperab 1 e. BRAIDWOOD
| |
| -UNITS 1 & 2 K.1 OR ESFAS Instrumentation
| |
| | |
| ====3.3.2 REQUIRED====
| |
| ACTION One channel may be bypassed for up to 12 hours for surveillance testing. Place channel in trip. COMPLETION TIME 72 hours K.2.1 Be in MODE 3. 78 hours AND K.2.2 Be in MODE 5. 108 hours (continued) 3.3.2 -7 ArnendmenLNo.
| |
| 180
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation ACTIONS (continued)
| |
| REQU I RED ACTI ON TIlvlE L. One or more channels inoperable.
| |
| L.1 OR Verify "interlock is in required state for existing unit condition.
| |
| L.2.1 Be in MODE 3. AND L.2.2 Be "in
| |
| : 4. 1 hour 7 hours 13 hours SURVEILLANCE REQUIREMENTS Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.
| |
| SR 3.3.2.1 SURVEILLANCE Perform CHANNEL CHECK. FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.3.2.2 Perform COT. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UN ITS 1 & 2 3.3.2 -8 Amendment 169
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.2.3
| |
| -
| |
| Verification of relay setpoints not requ-j red. Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.4 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.5 Perform MASTER RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.6 The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
| |
| Perform COT. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.3.2 -9 Amendment
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.3.2.7 SURVEI LLANCE Verification of relay setpoints not required.
| |
| FREQUENCY Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.8 Perform SLAVE RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.9 Verification of setpoint not required.
| |
| Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.10 This Surveillance shall include verification that the time constants are adjusted to the prescribed values. Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program (cont -j nued) BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -10 Amendment 171
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.3.2.11 Verify ESFAS RESPONSE are with-in l imi t. In accordance with the Surveillance Frequency Contro l Program SR 3.3.2.12 Verify ESFAS RESPONSE TIMES are within limit . In accordance with the Surveillance Frequency Contra l Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.2 11 Amendment ESFAS Instrumentation 3.3.2 1 of 6) Engineered Safety System Instrwentati on APPLICABLE MODES OR FUNCTION OTHER SPECjI'I ED CONDITIONS REQUIRED CHI\NNELS CONDITIONS SURVEI LLANCE REQUI REMENTS ALLOWABLE VALUE 1. Safety Injection
| |
| : a. Manua 1 Ini ti aU on 1,2,3,4 2 B SR 3.3.2.9 NA b. Automatic Actuat ion Logi c Actuation ays 1.2,3,4 2 trains C SR SR SR 3.3.2.4 3.3.2.5 3.3,2,8 NA c. Containrrent Pressure-High 1 1,2,3 3 D SR SR SR SR 3,3.2.1 3.3,2,6 3.3,2.10 3.3,2.12 4,6 psig d. Pressurizer Pressure-Low 1,2,3(') 4 D SR Sf!. Sil. S.il. 3.3.2.1 3.3,2,6 3,3,2,10 3,3,2,12 ;?: 1817 psig e. Steam .ine Pressure-Low 1,2,J" 3 steam ine D Sf!. Sf!. SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 ;?: 614 psi g:O) 2. Containment Spray a, Manual Initi ati on 1,2,3,4 2 B SR 3,3.2.9 NA b. Automatic Actuation Logi c and Actuation Relays 1,2,3,4 2 trai ns C SR SR SR 3,3,2.4 3.3.2.5 3.3.2.8 NA c. Containment Pressure High-3 1,2,3 4 E SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 21.2 psig (cont i nued ) (a) Above the poll (Pressurizer Pressure) interlock, (b) Time constants used in the lead/lag controller are tJ;?: 50 seconds and t2 5 seconds. BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 Amendment ESFAS Instrumentation
| |
| | |
| ====3.3.2 Table====
| |
| 3.3.2*} (page 2 of 6)Engineered Safety Feature Actuation Instrurrentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREJ.IENTS VALUE 3. Contairr.El1t Isolation Phase A Isolation Mmual 1.2.3,4 2 B SR 3.3.2.9 NA Initiation Autaretic 1.2.3,4 2 trains C SR 3.3.2.4 NA Actuation SR 3.3.2.5 Logic and SR 3.3.2.8 Act-.ation Relays Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirEllllnts.
| |
| Injection Phase B Iso 1 ati on t'anual 1.2,3,4 2 B SR 3.3.2.9 NA Initiation Autaretic 1,2,3,4 2 trains C SR NA Actuation SR Logic and SR Actuation Relays ContaimEnt 1,2,3 4 E SR s 21.2 psig Pressure SR High-3 SR SR (contmuea)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 Amendment 171 ESFAS Instrumentation
| |
| | |
| ====3.3.2 Table====
| |
| 3.3.2-1 (page 3 of 6)Engi neered Safety Feature Actuati on System Instrurrentati on FUNCTION APPLICABLE MODES OR OTHER SPECI FI ED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEI LLANCE REQUIREMENTS ALLOWABLE VALUE 4. Steam Line Isolation
| |
| : a. Manual Initiation 1 ,2 Ic ) ,3 Ic ) 2 F SR 3.3.2.9 NA b. Automatic Actuation Logic and Actuation Rel ays 1 ,2 Ig ) ,3 Ig ) 2 trai ns G SR SR SR 3.3.2.4 3.3.2.5 3.3.2.8 NA c. Contai nment Pressure-High 2 1 ,2 Ig ) ,3 Ig ) 3 o SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 9.4 pSig d. Steam Line Pressure (1) Low 1,2 Ig ),Jla)lfJlg) 3 per steam line o SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 614 psig lb) (2) Negative Rate-High 3 ldll g) 3 per steam 1 ine o SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 165.3 psi Ie) (contl nUed) (a) Above the P-11 (Pressurizer Pressure) interlock. (b) Time constants used in the lead/lag controller are tl 50 seconds and t2 5 seconds. (c) Except when all Main Steam Isolation Valves (MSIVs) are closed. (d) Below the P-11 (Pressurizer Pressure) interlock with Function 4.d.1 blocked. (e) Time constant utilized in the rate/lag controller is 50 seconds. (f) Below the P-11 (Pressurizer Pressure) interlock with Function 4.d.2 not enabled. (g) Except when all Main Steam Isolation Valves (MSIVs) and MSIV bypass valves are closed. BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -14 Amendment 171 ESFAS Instrumentation 3.3.2 4 of 6)Engineered Safety System InstrlJJlentation APPLICABLE MODES OR FUNCTION OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEI LLANCE REQUI REMENTS ALLOWABLE VALUE Turbine Trip and Feedwater Isolation Automatic Actuation Logic and Actuation Relays Steam Generator (SG) Water Level-High High (P-14l Unit 1 Unit 2 Safety Injection 1,2 Ih),3!hl 2 trains SR 3.3.2.4 NA SR 3.3.2.5 SR 3.3.2.8 1 ,2 Ih) ,3"') 4 per SG SR 3.3.2.1 S; 89,9% of SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2,6 span SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12 1 ,2,h) .3 1hl 4 per SG SR 3.3.2.1 s; 81.5% of SR 3.3.2.4 narrow range SR 3.3.2.5 instrtFent SR 3.3.2.6 span SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12 Refer to Function 1 (Safety I'ljection) for all initiation functions and requirements. ( conti nuec!l Except when all Feedwater Isolation Valves are closed or isolated by a closed manua: valve. BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 Amendment ESFAS Instrumentation
| |
| | |
| ====3.3.2 Table====
| |
| 3.3.2-1 (page 5 of 6)Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPEC! FI ED REQUIRED SURVE I L LANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 6. Auxi 1 i ary Feedwater
| |
| : a. Automatic Actuation Logic and Acbation Relays 1.2,3 2 trains G SR SR SR NA b. SG Water Level-Low LOW 1) Unit 1 1.2,3 4 per SG D SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 16.1% of narrow range instrwent span 2) Unit 2 1,2,3 4 per SG D SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 34.8% of narrow range instrument span c. Safety Injection Refer to Functi on 1 (Safety Injection) for ali i ni ti ati on functions and requi rements. d. Loss of Offsite Power \Undervo ltage on Bus 141( 241)) 1,2.3 2 H SR SR SR " 2730 V e. Undervo 1 tage Reactor Coo 1 ant Purrp (per train) 1,2 4 SR SR SR 4920 V f. Auxiliary Feedwater Purrp Suction Transfer on Suction Pressure-Low 1,2,3 1 per train J SR SR SR " 17.4 psia 7. Switchover to Containment Sump a. Automatic Actuation Logic and Actuation R,elays 1,2,3,4 2 trains C SR SR SR 3.3.2.4 3.3.2.5 3.3.2.8 NA b. Refueling Water Storage Tank (RWSTl Level-Low Low 1,2,3.4 4 K SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 44.7% of instrument span Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 16 Amendment ESFAS Instrumentation
| |
| | |
| ====3.3.2 Table====
| |
| 3.3.2-1 (page 6 of 6) Engineered Safety Feature Actuation System lnstrumentation REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CHANNELS CONDITIONS REQU I REMENTS VALUE ESFAS Interlocks a, Reactor Trip, P-4 1,2,3 2 per train SR 3.3.2.9 NA Pressuri zer Pr'essure, 1,2,3 2 SR 3.3.2.6 <; 1936 psig P-l1 SR 3.3.2.10 T'.!J-LO<i LO<i. P-12 1,2,3 3 L Sf{ 3.3.2.6 548.O'F Sil. 3.3.2.10 BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -Amendment PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 APPLICABILITY:
| |
| The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.According to Table 3.3.3-1.ACTIONS-------------------NOTE-------------------------------------I Separate Condition entry is allowed for each Function.
| |
| I CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in required channels Table 3.3.3-1 for the inoperable.
| |
| channel.B. As required by B.1 Restore required 30 days Required Action A.1 channel to OPERABLE and referenced in status.Table 3.3.3-1.C. Required Action and C.1 Initiate action in Imrmediately associated Completion accordance with Time of Condition B Specification 5.6.7.not met.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.3 -1 Amendment 134 PAM Instrumentation
| |
| | |
| ====3.3.3 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 Restore one required 7 days Required Action A.1 channel. to OPERABLE and referenced in status.Table 3.3.3-1.E. One or more Functions E.1 Restore all but one 7 days with two or more required channel to required channels OPERABLE status.inoperable.
| |
| F. ---------NOTE---------
| |
| F.1 Be in MODE 3. 6 hours Not applicable to Functions 11, 12, and AND 14.F.2 Be in MODE 4. 12 hours Required Action and associated Completion Time of Condition D or E not met.(continued)
| |
| I I I BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.3 -2 Amendment 137 PAM Instrumentation
| |
| | |
| ====3.3.3 ACTIONS====
| |
| (continued)
| |
| CONDITION REQU I RED ACT I ON COMPLETION TIME G. ---------NOTE -------Only applicable to Functions 11, 12, and 14. Required Action and associated Completion Time of Condition D or E not met. G. 1 Initiate action in accordance with Specification
| |
| | |
| ====5.6.7. IrTTTlediately====
| |
| | |
| SURVEILLANCE REQUIREMENTS SR 3.3.3.1 SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1. SURVEI LLANCE FREQUENCY In accordance instrumentation channel that is normally SR Perform CHANNEL CHECK for each required with the energized.
| |
| Surveillance Frequency Control Program SR -------------------
| |
| NOT E-------------------
| |
| Radiation detectors for Function 11, Containment Area Radiation, are excluded.
| |
| In accordance with the Perform CHANNEL CALIBRATION.
| |
| Surveillance Frequency Control Program BRAIDWOOD
| |
| -UN ITS 1 & 2 3.3.3 -Amendment 165/165 PAM Instrumentation
| |
| | |
| ====3.3.3 Table====
| |
| 3.3.3-1 (page 1 of 1)Post Accident Ionitoring Instrurentation
| |
| -nU UIc 1. Reactor Coolant System (RCS) Pressure (Wide Range)2. RES Hot Leg Temperature (Wide Range)3. RCS Cold Leg Teaperature (Wide Range)4. Steam Generator (SG) Water Level (Wide Range)(per SG)5. SG Water Level (Narrow Range)(per SG)6. Pressurizer Water Level (Narrow Range)7. Containment Pressure (Wide Rangej 8. Steam Line Pressure (per SG)9. Refueling Water Storage Tank Water Level 10. Contairment Floor Water Level (Wide Range)11. Containment Area Radiation (High Range)12. Main Steam Line Radiation (per steam line)13. Core Exit Teaperature (per core quadrant)14. Reactor Vessel Water Level APFLIULMLt rPULt OR UOHER SPECIFIED COITIOtS _1,2,3 1.2,3 1,2.3 1,2.3 1,2.3 1,2,3 1,2.3 1,2,3 1.2.3 1,2,3 1,2,3 1,2,3 1.2,3 1,2.3 REWIRED 0'AGMELS 2 2 2 1 1 2 2 2 2 2 1 1 4 2 MIDITIRY6 B B B D D B B B B B D D B B BRAIDWOOD
| |
| -UNITS 1 & 2 3;3.3 -4 Amendment 137 Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.4 Remote====
| |
| Shutdown System LCO 3.3.4 APPLICABILITY:
| |
| The Remote Shutdown System Functions in Table 3.3.4-1 shall be OPERABLE.MODES 1, 2, and 3.ACTIONS--- ------------------
| |
| NOTE------------------------------------
| |
| Separate Condition entry is allowed for each Function.
| |
| I CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable.
| |
| Function to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.4 -1 Amendment 134 Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR SR 3.3.4.1 Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.
| |
| In accordance with the Surveillance Frequency Control Program 3.3.4.2 ---Neutron detectors are excluded from CHANNEL CALIBRATION.
| |
| Perform CHANNEL CALIBRATION for each required instrumentation channel. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.3.4 2 Amendment Remote Shutdown System 3.3.4 Table 3.3.4-1 (Page 1 of 1)Remote Shutdown Monitoring Instrumentation l REQUIRED FUNCTION/INSTRUMENT PARAMETER i NUMBER OF CHANNELS 1. Intermediate Range Neutron Flux 1 2. Source Range Neutron Flux 1 3. Reactor Coolant Temperature
| |
| -Wide Range a. Hot Leg (per loop) 1 b. Cold Leg (per loop) 1 4. Pressurizer Pressure 1 5. Pressurizer Level 1 6. Steam Generator Pressure (per SG) 1 7. Steam Generator Level (per SG) 1 8. Residual Heat Removal Temperature 1 9. Auxiliary Feedwater Flow Rate (per SG) 1 BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.4 -3 Amendment 98
| |
| | |
| ===3.3 INSTRUMENTATION===
| |
| | |
| LOP DG Start Instrumentation 3.3.5 3.3.5 Loss of Power CLOP) Diesel Generator COG) Start Instrumentation LCO 3.3.5 Two channels per bus of the loss of voltage Function, two channels per bus of the degraded voltage Function and two channels per bus of the low degraded voltage Function shall be OPERABLE.
| |
| APPLICABILITY:
| |
| MODES 1, 2, 3, and 4; When associated DG is required to be OPERABLE by LCO 3.8.2, "AC Sources-Shutdown." ACTIONS -------------------------------------NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each Function.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A. l --------NOTE---------
| |
| with one channel on For loss of voltage one or more buses Function, the inoperable.
| |
| inoperable channel may be bypassed for up to 2 hours for surveillance testing of the other channel. ---------------------
| |
| Pl ace channel in 1 hour trip. B. One or more Functions B.l Restore one channel 1 hour with two channels on for the Function on one or more buses the affected bus to inoperable.
| |
| OPERABLE status. (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.5 -1 Amendment 188 LOP DG Start Instrumentation
| |
| | |
| ====3.3.5 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.l Enter applicable Immediately associated Completion Condition(s) and Ti me not met. Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.
| |
| SURVEILLANCE REQUIREMENTS SR 3.3.5.1 SR 3.3.5.2 SURVEILLANCE
| |
| -------------------NOTE--------------------
| |
| Verification of relay setpoints not required.
| |
| Perform TADOT. Perform CHANNEL CALIBRATION with setpoint Allowable Value as follows: a. Loss of voltage Allowable Value 2730 V with a time delay of ::::; 1.9 seconds. b. Degraded voltage Allowable Value 3930 V with a time delay of 310 +/- 30 seconds. c. Low degraded voltage Allowable Value 3196.4 V with a time delay of ::::; 3.5 seconds. FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.5 -2 Amendment 188 Containment Ventilation Isolation Instrumentation 3 3 f 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.6 Containment====
| |
| | |
| Ventilation Isolation Instrumentation LCO 3.3.6 The Containment Ventilation Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.
| |
| APPLICABILITY:
| |
| According to Table 3.3.6-1. ACTIONS -------------------------------------NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each Function.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation A.1 Restore the affected 4 hours monitoring channel channel to OPERABLE inoperable.
| |
| status. B. One or more automatic B.1 Enter applicable Immediately actuation trains Conditions and inoperable.
| |
| Required Actions of LCD 3.6.3, OR "Containment Isolation Valves," Two radiation for containment purge monitoring channels valves made inoperable.
| |
| inoperable by isolation OR instrumentation.
| |
| Required Action and associated Completion Time of Condition A not met. BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.6-1 Amendment 1 7 8 Containment Ventilation Isolation Instrumentation
| |
| -3.3.6 SURVEILLANCE REQUIREMENTS
| |
| -------------------------------------NOTE-------------------------------------
| |
| Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Ventilation Isolation Function.
| |
| SR 3.3.6.1 SR 3.3.6.2 SR 3.3.6.3 SURVEILLANCE Perform CHANNEL CHECK. --------------NOTE-------------------------
| |
| This Surveillance is only applicable to the actuation logic of the ESFAS Instrumentation.
| |
| Perform ACTUATION LOGIC TEST.
| |
| This Surveillance is only applicable to the master relays of the ESFAS Instrumentation.
| |
| Perform MASTER RELAY TEST. BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.6 -2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
| |
| Amendment 1 7 8 Containment Ventilation Isolation Instrumentation
| |
| | |
| ====3.3.6 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.3.6.4 Perform COT. SR 3.3.6.5 Perform SLAVE RELAY TEST. SR 3.3.6.6 Perform CHANNEL CALIBRATION.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.6-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 1 7 8 FUNCTION 1. Manual Initiation
| |
| -Phase A 2. Manual Initiation
| |
| -Phase B 3. Automatic Actuation Logic and Actuation Relays 4. Containment Radiation-High
| |
| : 5. Safety Injection Containment Ventilation Isolation Instrumentation 3.3.6 Table 3.3.6*1 (page 1 of 1) Containrrent Ventilation Isolation Instrurrentation APPLI 1\BLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS TRIP SETPOINT Refer to LCD 3.3.2, "ESFAS Instrumentation," Function 3.a.1, for all initiation functions and requirerrents.
| |
| Refer to LCD 3.3.2, "ESFAS Instrurrentation," Function 3.b.1, for all i niti ati on functions and requi rerrents.
| |
| 1,2,3,4 2 trains SR 3.3.6.2 SR 3.3.6.3 SR 3.3.6.5 1,2,3,4 2 SR 3.3.6.1 SR 3.3.6.4 SR 3.3.6.6 NA (a) Refer to LCD 3.3.2, "ESFAS Instrurrentation," Function 1, for all initiation functions and requi rements. (a) Trip setpoint shall be established 2 x background in the Containment Building at RTP. BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.6-4 Amendment 1 7 8 VC Filtration System Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.7 Control====
| |
| Room Ventilation (VC) Filtration System Actuation Instrumentation LCO 3.3.7 APPLICABILITY:
| |
| The VC Filtration System actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.According to Table 3.3.7-1.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place the redundant 1 hour on one train VC Filtration System inoperable.
| |
| train in normal mode.OR A.2 Place one VC 1 hour Filtration System train in emergency mode.B. One or more channels B.1 Place one VC 1 hour on both trains Filtration System inoperable.
| |
| train in emergency mode.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND or B not met in MODE 1, 2. 3. or 4. C.2 Be in MODE 5. 36 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.7 Amendment 98 VC Filtration System Actuation Instrumentation
| |
| | |
| ====3.3.7 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of irradiated fuel assemblies.
| |
| | |
| ===0.1 Suspend===
| |
| movement of i rradi ated fuel assemblies.
| |
| Immediately E. Required Action and associated Completion Time of Condition A or B not met in MODE 5 or 6. E.1 Initiate action to restore one VC Filtration System train to OPERABLE status. Immediately SURVEILLANCE REQUIREMENTS
| |
| ------------
| |
| -----------NOTE----
| |
| Refer to Table 3.3.7 1 to determine which SRs apply for each VC Filtration System Actuation Function.
| |
| SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.2 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.7.3 Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 & 2 3.3.7 -2 Amendment ViC Fi L tr,;;ti r-n Sysztent Acatct iWIn Strumm-Ytta t-Icen Table 3.3.7-1 (page I of I*-11C Fil1tration S/staT Actuation lnsAt~rn'aticii APPLICABLE 14Ubt.FUICTION I. Control Rccm Padi ation-C-aseons
| |
| : 2. Sifety Injection OR OTHER SU)RVEI LLANCE T SPECIFIED REOUIRED CHSIMELS REGUIRiErrrS TRIP -EFF CONlDITIONS 1.2,3.4,5,6,(a) 2 per train SR 3.3.7-4l 2 riaI-SR 3.3.7.2 SR 3.3.7.3" Pefer to LCO 3.3.2, "ESFAS lnstrtentaticn," Function 1, for all iniftatioil functions and require-ents.
| |
| 'IT (a) During noverrant of irradiated fuel asseTblies.
| |
| BRAIDWOOD
| |
| -UNITS I & 2 3, 3. 7-3 AT1=nrlm=nf-1 1. t-%1-11ý Lýtv FHB Ventilation System Actuation Instrumentation 3.3.8 3.3 INSTRUMENTATION 3.3.8 Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System Actuation Instrumentation LCO 3.3.8 The FHB Ventilation System actuation each Function in Table 3.3.8-1 shall instrumentation for be OPERABLE.APPLICABILITY:
| |
| According to Table 3.3.8-1.ACTIONS s enYr-- ---nil[ ii I- -----
| |
| II %J I L-LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Restore channel to 7 days inoperable.
| |
| OPERABLE status.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.8 -.1 Amendment 98 FHI V'entilat-ion System A"t- i- "iru 3.3,.ACTIONS (cnrlL I e CONDITION REQUIRED ACTION COMPLETION TIME.B, Required Action and B.1 Place in emergency Ihninediately associated Completion mode one FHB Time not met. Ventilation System train capable of OR being powered by an OPERABLE emergency Two channels power source.inoperabl e.OR B.2.1 Suspend movement of IrmTediately RECENTLY IRRADIATED FUEL assemblies in the fuel handling building.AND B.2.2 ---------
| |
| NOTE-----Only required with equipment hatch not intact.Suspend movement of Irnemdiately RECENTLY IRRADIATED FUEL assemblies in the containment.
| |
| B1\n1.nOD
| |
| -UNITS I & 2 31).3.8 -2 Amendment 14 0 FHB Vent"ilation System Actuation Instrumentation
| |
| | |
| ====3.3.8 SURVEILLANCE====
| |
| | |
| REQUIREMENTS
| |
| ----------
| |
| ------------
| |
| -------NOTE-----------
| |
| ------
| |
| Refer to Table 3.3.8-1 to determine which SRs apply for each FHB Ventilation System Actuation Function.
| |
| SURVEI LLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.8.2 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.8.3 Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.3.8 3 Amendment FHE 'V Fti 11 -a t '--, % t -em ý ctL18ti on I i r utImic-rl-at!
| |
| Ixn 3.3.8 Table 3.35.81 (page i of 1)FI-EVenti l5ticn Sy:tarn Actuaticn.
| |
| tnstrutentatic-n AP P-E 1-8LL I'IDDCTlr~i NOES OR OTHER fELD rIip STSURVEILLPIICE SPECIFIED P2JIREM REQUIRIEMT5 TRIP SETPOINT CONDITIONS
| |
| : 1. Fuel Handling Building (a),(b) 2 SR 3.3.8.1 _ 5 nP~ir Radiation SR 3.3.8.2 SR 3.3.8.3 2. Safety Injection Refer to LCO 3.3.2, "ESFAS InmtruTmntation," Funmtion I, fcr all initiation functicns and requirements.(a) During mnverrznt of RECENTLY IRRADIATED FUEL assemlies in the fuel handling building.(b) During friveircnt of RECENTLY IRPADIATED FUEL asseffblies in the containmEnt with the cquiprmnt hatch not intact.I I I BPAIDWOOD
| |
| -UNITS 1 0 .. iAedrn 4 3. 3.-8 -4 A -AillEnd-ment T.40 BDPS 3.3.9 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.9 Boron====
| |
| Dilution Protection System (BDPS)LCO 3.3.9 BDPS shall be OPERABLE with: a. One or more reactor coolant pump(s) in operation;
| |
| : b. Each Reactor Coolant System (RCS) loop isolation valve open: and c. The BDPS instrumentation in Table 3.3.9-1 OPERABLE.
| |
| -----------------------
| |
| NOTE --------------------
| |
| The Boron Dilution Alert Alarm may be bypassed in MODE 3 during reactor startup.
| |
| ------------------------------------------
| |
| APPLICABILITY:
| |
| MODES 3, 4, and 5.ACTIONS Unborated water source isolation administrative controls.-----NOTE------
| |
| valves may be unisolated intermittently under CONDITION REQUIRED ACTION COMPLETION TIME A. One Boron Dilution A.1 Restore channel to 72 hours Alert channel OPERABLE status. inoperable. (continued)
| |
| BPRAIDWOOD
| |
| -UNITS I & 2 I 3.3.9-1 Amnendment 111 BDPS 3.3.9 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Close unborated water 1 hour associated Completion source isolation Time of Condition A valves. not met. AND B.2 Verify unborated Once per 31 days water source isolation valves closed. C. Two Boron Dilution C.1 Close unborated water 1 hour Alert channels source isolation inoperable, valves. OR AND No reactor coolant C.2 Perform SR 3.1.1.1. 1 hour pump in operation.
| |
| AND OR Once per One or more RCS loop 12 hours isolation valve(s) not thereafter open. AND C.3 Verify unborated Once per water source 12 hours isolation valves closed.BRAIDWOOD
| |
| -UNITS 1 & 2 I 3.3.9-2 Amendment 111 BOPS 3.3.9 SURVEILLANCE REQUIREMENTS SR 3.3.9.1 SURVEI LLANCE Verify one or more reactor coolant pump(s) -j n operat ion. FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.3.9.2 Verify each RCS loop isolation valve is open. In accordance with the Surveillance Frequency Control Program SR 3.3.9.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.9.4 Verify each Boron Dilution Alert channel selector switch is in the Normal position.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.3.9.5 Verify each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
| |
| In accordance with the Surveillance Frequency Control Program (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.9 -3 Amendment 165/165 BOPS 3.3.9 SURVEILLANCE (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.3.9.6 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.9.7 The CHANNEL CALIBRATION is only required to include that portion of the channel associated with the Boron Dilution Alert function.
| |
| Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 & 2 3.3.9 -4 Amendment BOPS 3.3.9 FUNCTION Table 3.3.9-1 Boron Dilution Protection 1 of 1)lnstrurrentation REQUIRED CHANNELS SURVElLLANCE REQUIREMENTS ALLOWABLE VALUE Dilution Alert Channels Volurre Control Tank Level High 2 SR 3.3.9.3 s; 71.15% SR 3.3.9.6 SR 3.3.9.7 BRAIDWOOD UNITS 1 & 2 3.3.9 -Amendment RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM CRCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling CDNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature CTavg_) , and RCS total flow rate shall be within the limits spec1fied below: a. Pressurizer pressure within the limit specified in the COLR; b. RCS average temperature within the limit specified in the COLR; and c. RCS total flow 386,000 gpm and within the limit specified in the COLR. ----------------------------NOTE----------------------------
| |
| Pressurizer pressure limit does not apply during: a. THERMAL POWER ramp> 5% RTP per minute; or b. THERMAL POWER step> 10% RTP. APPLICABILITY:
| |
| MODE 1. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours not within imits. parameter(s) to within limit. B. Required Action and associated Completion B.1 Be in MODE 2. 6 hours Time not met. BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.1-1 Amendment No. 17 4 RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SR 3.4.1.1 SR 3.4.1.2 SR 3.4.1.3 SR 3.4.1.4 SURVEILLANCE Verify pressurizer pressure is within the limit specified in the COLR. Verify RCS average temperature is within the limit specified in the LOLR. Verify RCS total flow rate 386,000 gpm and within the limit specified in the COLR. -------------------NOTE--------------------
| |
| Not required to be performed until 7 days after 90% RTP. Verify by precision heat balance that RCS total flow rate is 386,000 gpm and within the limit specified in the COLR. BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.1-2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 174 RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Min-imum Temperature for LCO 3.4.2 Each RCS loop average temperature shall be MODE 1, MODE 2 with keff 1. 0 . ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more loops not within 1 i mi t. ReS A.l Be in MODE 2 with keff < 1.0. 30 minutes SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.4.2.1 Veri fy RCS in each 1 oop 550°F. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.4.2 Amendment RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 APPLICABILITY:
| |
| RCS pressure.
| |
| RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR.At all times.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----NOTE--- A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.shall be completed whenever this AND Condition is entered._ A.2 Determine RCS is 72 hours acceptable for Requirements of LCO continued operation.
| |
| not met in MODE 1. 2.3, or 4.B.. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 5. 36 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.3 -.1 Amendment 98 RCS PIT Limits 3.4.3 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. -----NOTE --Required Action C.2 shall be completed whenever this Condition is entered. C. 1 AND Initiate action to restore parameter(s) to within limits. Immediately Requirements of LCO not met any time other than in MODE 1, 2, 3, or 4. C.2 Determine RCS is acceptable for continued operation.
| |
| Prior to entering MODE 4 SURVEILLANCE SR 3.4.3.1 -----------------NOTE---
| |
| ---
| |
| Only requ"i red to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing. Verify RCS pressure, RCS temperature, and RCS heatup and cool down rates are within the limits specified in the PTLR.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.4.3 -2 Amendment RCS Loops-MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops-MODES 1 and LCO 3.4.4 Four RCS loops shall be OPERABLE and in APPLICABILITY:
| |
| MODES 1 and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCD not met. A.1 Be in MODE 3. 6 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.4 1 Amendment RCS Loops- MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.5 RCS Loops- MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE, and either: a. Two OPERABLE RCS loops shall be in operation when the Rod Control System is capable of rod withdrawal; or b. One OPERABLE RCS loop shall be in operation when the Rod Control System is not capable of rod withdrawal.
| |
| ~~- ---NOTE----
| |
| --------------
| |
| All reactor coolant pumps may be removed from operation for< 1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration:
| |
| and b. Core outlet temperature is maintained 2 10 0 F below saturation temperature.
| |
| APPLICABILITY:
| |
| MODE 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Place the Rod Control 1 hour not in operation with System in a condition Rod Control System incapable of rod capable of rod withdrawal.
| |
| withdrawal.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.5 -.1 Amendment 98 RCS Loops -MODE 3 3.4.5 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. No required RCS loop B.1 Suspend all Immediately in operation with Rod operations involving Control System not a reduction of RCS capable of rod boron concentration.
| |
| withdrawal.
| |
| AND B.2 Initiate action to Immediately restore one RCS loop to operation.
| |
| C. Two required RCS loops C.1 Initiate action to Immediately not in operation with place the Rod Control Rod Control System System in a condition capable of rod incapable of rod withdrawal.
| |
| withdrawal.
| |
| OR AND Required Action and C.2 Suspend all Immediately associated Completion operations involving Time of Condition A a reduction of RCS not met. boron concentration.
| |
| AND C.3 Initiate action to Immediately restore RCS loop(s)to operation.
| |
| D. One required RCS loop D.1 Restore required RCS 72 hours inoperable.
| |
| loop to OPERABLE status.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.5 -2 Amendment
| |
| : 98.
| |
| RCS Loops-MODE 3 3.4.5 ACTIONS (continued)
| |
| CONDITION REQU I RED ACT ION COMPLETION TIME E. Required Action and associated Completion Time of Condition D not met. E.1 Be in MODE 4. 12 hours F. Two required RCS loops inoperable.
| |
| F.1 AND F.2 AND F.3 Initiate action to place the Rod Control System in a condition incapable of rod withdrawal.
| |
| Suspend all operations involving a reduction of RCS boron concentration.
| |
| Initiate action to restore one RCS loop to OPERABLE status. Imnediately Imnediately Imnediately SURVEILLANCE SR 3.4.5.1 Verify each required RCS loop is in operation.
| |
| In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.5 -3 Amendment RCS Loops-MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.4.5.2 Verify steam generator secondary side narrow range water level is 18% for each required ReS loop. In accordance with the Surveillance Frequency Control Program SR 3.4.5.3 Verify correct breaker alignment and indicated power are available to each required pump that is not in operation.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.5-4 Amendment RCS Loops- MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.6 RCS Loops -MODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and Residual Heat Removal (RHR) loops shall be OPERABLE, and one OPERABLE loop shall be in operation.
| |
| --- -NOTES- --- --------1. All Reactor Coolant Pumps (RCPs) and RHR pumps may be removed from operation for s 1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration; and b. Core outlet temperature is maintained
| |
| ; 10OF below saturation temperature.
| |
| : 2. No RCP shall be started with any RCS cold leg temperature
| |
| < 350 0 F unless the secondary side water temperature of each Steam Generator (SG) is < 50 0 F above each of the RCS cold leg temperatures.
| |
| APPLICABILITY:
| |
| MODE 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No required loop in A.1 Suspend all Immediately operation.
| |
| operations involving a reduction in RCS boron concentration.
| |
| AND A.2 Initiate action to Immediately restore one loop to operation.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.6-.1 Amendment
| |
| : 98.
| |
| RCS Loops MODE 4 3.4.6 ACTIONS (continued)
| |
| CONDITION REQUI RED ACTI ON COMPLETION TIME B. One required loop inoperable.
| |
| B.1 AND B.2 Initiate action to restore a second loop to OPERABLE status.
| |
| Only required if RHR loop is OPERABLE.
| |
| ---Be in MODE 5. Irrmediately 24 hours C. Two required loops inoperable.
| |
| C.1 AND C.2 Suspend all operations involving a reduction of RCS boron concentration.
| |
| Initiate action to restore one loop to OPERABLE status. Irrmediately Ilmedi ately SURVEI LLANCE SR 3.4.6.1 SURVEILLANCE Verify required RHR or operation.
| |
| RCS loop is in FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.4.6.2 Verify SG secondary side narrow range water level is 18% for each required RCS loop. In accordance with the Survei 11 ance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.4.6 -2 Amendment SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.4.6.3 SR 3.4.6.4 SURVEILLANCE Verify correct breaker alignment and indicated power are available to each required pump that is not in operation.
| |
| -------------------NOTE--------------------
| |
| Not required to be performed until 12 hours after entering MODE 4. Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water. RCS Loops-MODE 4 3.4.6 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.6 -3 Amendment No. 183 RCS Loops- MODE 5. Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.7 RCS Loops -MODE 5, Loops Filled LCO 3.4.7 One Residual Heat Removal (RHR) loop shall be OPERABLE and in operation, and either: a. One additional RHR loop shall be OPERABLE:
| |
| or b. The secondary side water level of at least two Steam Generators MSGs) shall be > 18%.-- --NOTES-- -------------
| |
| : 1. The RHR pump may be removed from operation for 5 1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration:
| |
| and b. Core outlet temperature is maintained 2 10 0 F below saturation temperature.
| |
| : 2. One required RHR loop may be inoperable for s 2 hours for surveillance testing provided that the other RHR loop is OPERABLE and in operation.
| |
| : 3. No reactor coolant pump shall be started with any RCS cold leg temperature s 350 0 F unless the secondary side water temperature of each SG is < 50 0 F above each of the RCS cold leg temperatures.
| |
| : 4. All RHR loops may be removed from operation during.planned heatup to MODE 4 when at least one RCS loop is in operation.
| |
| APPLICABILITY:
| |
| MODE 5 with RCS loops filled.BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.7 -1 Amendment 98 RCS Loops -MODE 5. Loops Filled 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No required RHR loop A.1 Suspend all Immediately in operation.
| |
| operations involving a reduction in RCS boron concentration.
| |
| AND A.2 Initiate action to Immediately restore one RHR loop to operation.
| |
| B. One required RHR loop B.1 Initiate action to Immediately inoperable.
| |
| restore required RHR loop to OPERABLE status.C. One or both required C.1 Initiate action to Immediately SG secondary side restore required SG water level(s) not secondary side water within limits. level(s) to within limits.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.7 -2 Amendment 98 RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION D. Two required RHR loops D.1 Suspend all inoperable.
| |
| operations involving a reduction of RCS OR boron concentration.
| |
| Required RHR loop AND inoperable and one or both required SG D.2.1 Initiate action to secondary side water restore one RHR loop level Cs) not within to OPERABLE status. limits. OR D.2.2 Initiate action to restore required SG secondary side water level Cs) to within limits. SURVEILLANCE REQUIREMENTS SR 3.4.7.1 SR 3.4. 7 .2 SR 3.4.7.3 SURVEILLANCE Verify required RHR loop is in operation.
| |
| Verify SG secondary side narrow range water level is 18% in required SGs. Verify correct breaker alignment and indicated power are available to each required RHR pump that is not in operation.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.7 -3 COMPLETION TIME Immediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
| |
| Amendment No. 183 RCS Loops-MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.4.7.4 SURVEILLANCE Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water. BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.7 -4 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 183 RCS Loops- MODE 5. Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.8 RCS Loops -MODE 5. Loops Not Filled LCO 3.4.8 Two Residual Heat Removal one OPERABLE RHR loop shal (RHR) loops shall be OPERABLE and 1 be in operation.
| |
| l I^T=tv_slrl l_- * .n -.----_ _ _ _ _ _ _ _ _-1. All RHR pumps may be removed from operation for < 1 provided: hour a. No operations are permitted that would cause a reduction of the RCS boron concentration:
| |
| : b. The core outlet temperature is maintained 2 10OF below saturation temperature:
| |
| and c. No draining operations are permitted that would further reduce the RCS water volume.2. One RHR loop surveillance OPERABLE and may be inoperable for 5 2 hours for testing provided that the other RHR loop is in operation.
| |
| APPLICABILITY:
| |
| MODE 5 with RCS loops not filled.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No required RHR loop A.1 Suspend all Immediately in operation.
| |
| operations involving a reduction in RCS boron concentration.
| |
| AND A.2 Initiate action to Immediately restore one RHR loop to operation.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.8- 1 Amendment 98 RCS Loops-MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. One required RHR loop inoperable.
| |
| C. Two required RHR loops inoperable.
| |
| B.1 C.1 AND C.2 Initiate action to RHR loop to OPERABLE status. Suspend all operations involving reduction in RCS boron concentration.
| |
| Initiate action to restore one RHR loop to OPERABLE status. IfllTlediately IfllTlediately IfllTlediately SURVET LLANCE REQUI SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required RHR loop is in operation.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.4.8.2 Verify correct breaker alignillent and indicated power are available to each required RHR pump that is not in operation.
| |
| In accordance with the Survei 11 ance Frequency Control Program BRAIDWOOD 1 & 2 3.4.8 -2 Amendment 165/165 Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with: a. Pressurizer water level < 92%: and b. Two groups of pressurizer heaters OPERABLE with the capacity of each group 2 150 kW and capable of being powered from redundant Engineered Safety Features (ESF)power supplied buses.APPLICABILITY:
| |
| MODES 1, 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water A.1 Be in MODE 3. 6 hours level not within limit. AND A.2 Fully insert all 6 hours rods.AND A.3 Place Rod Control 6 hours System in a condition incapable of rod withdrawal.
| |
| AND A.4 Be in MODE 4. 12 hours B. One or more required B.1 Restore required 72 hours groups of pressurizer groups of pressurizer heaters inoperable.
| |
| heaters to OPERABLE status.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.9 -1 Amendment 98 Pressurizer
| |
| | |
| ====3.4.9 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition B not met. C.1 AND C.2 Be in MODE 3. Be in MODE 4. 6 hours 12 hours SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is 92%. In accordance*
| |
| with the Surveillance Frequency Control Program SR 3.4.9.2 Verify capacity of each required group of pressurizer heaters is 2 150 kW. In accordance with the Surveillance Frequency Control Program SR 3.4.9.3 Veri fy requ"j red pressuri zer heaters are capable of being powered from an ESF power supply. In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.9 2 Amendment Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings 2 2411 psig and < 2509 psig.I----------------------
| |
| NOTE----------------------
| |
| The lift settings are not required to be within the LCO limits during MODE 3 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions.
| |
| This exception is allowed for 54 hours following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.APPLICABILITY:
| |
| MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable.
| |
| OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND OR B.2 Be in MODE 4. 12 hours Two or more pressurizer safety valves inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.10 -I Amendment 131 Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is In accordance OPERABLE in accordance with the Inservice with the Testing Program. Following testing. lift Inservice settings shall be within +/- 1%. Testing Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.10 -2 Amendment 98 Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.11 Pressurizer Power Operated Relief Valves (PORVs)LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.APPLICABILITY:
| |
| MODES 1, 2, and 3.ACTIONS-------------------------------------
| |
| NOTE------------------------------------
| |
| Separate Condition entry is allowed for each PORV and each block valve.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain 1 hour inoperable and capable. Power to associated of being manually block valve.cycled.B. One PORV inoperable B.1 Close associated 1 hour and not capable of block valve.being manually cycled. AND B.2 Remove power from 1 hour associated block valve.AND B.3 Restore PORV to 72 hours OPERABLE status.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.11 -1 Amendment 134 Pressurizer PORVs 3.4.11 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve C.1 Place associated PORV 1 hour inoperable.
| |
| in manual control.AND C.2 Restore block valve 72 hours to OPERABLE status.D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time of Condition A. AND B. or C not met.D.2 Be in MODE 4. 12 hours E. Two PORVs inoperable E.1 Be in MODE 3. 6 hours and not capable of being manually cycled. AND E.2 Be in MODE 4. 12 hours F. Two block valves F.1 Restore one block 2 hours inoperable.
| |
| valve to OPERABLE status.G. Required Action and G.1 Be in MODE 3. 6 hours associated Completion Time of Condition F AND not met.G.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.11 -2 Amendment 98 Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SLiRVEI LLANCE FREQUENCY SR 3.4.11.1 Not required to be met with block valve closed in accordance with the Required Action of Condition B or E. Perform a complete cycle of each block valve. In accordance with the Surveillance Frequency Control Program SR 3.4.11.2 Only required to be performed in MODES 1 and 2. Perform a complete cycle of each PORV. In accordance with the Surveillance Frequency Control Program SR 3.4.11.3 Perform a complete cycle of each solenoid air control valve and check valve on the air accumulators in PORV control systems. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.4.11 3 Amendment LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with: a. A maximum of one charging pump (centrifugal) capable of injecting into the RCS; b. No Safety Injection (S1) pumps capable of inject-ing into the RCS; c. Each SI accumulator isolated, whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the PIT limit curves provided in the PTLR; and d. One of the following pressure relief capabilities:
| |
| : 1. Two Power Operated Relief Valves (PORVs) with lift settings within the limits specified in the PTLR, 2. Two Residual Heat Removal (RHR) suction relief valves with setpoints 450 psig, 3. One PORV with a lift setting within the limits specified in the PTLR and one RHR suction relief valve with a setpoint 450 psig, or 4. The RCS depressurized and an RCS vent of 2.0 square inches. ----------------------------NOTES------------------1. Operation in MODE 4 with all SI pumps and charging pumps capable of injecting into the RCS is allowed when all RCS cold legs exceed 330°F. 2. For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is 5 percent. APPLICABILITY:
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| MODES 4 and 5, MODE 6 when the reactor vessel head is on. BRAIDWOOD
| |
| -UNITS 1 &2 3.4.12 -1 Amendment 167 LTOP System 3.4.12 ACTIONS LCO 3.0.4.b is not applicable when entering MODE 4.I CONDITION REQUIRED ACTION COMPLETION TIME A. Two charging pumps A.1 ---------NOTE--------(centrifugal) capable Two charging pumps of injecting into the may be capable of RCS. injecting into the RCS during pump swap OR operation for< 15 minutes.One charging pump (positive displacement) capable Initiate action to Immediately of injecting into the verify a maximum of RCS. one charging pump (centrifugal) is capable of injecting into the RCS.B. One or more SI pumps B.1 Initiate action to Immediately capable of injecting verify no SI pumps into the RCS. are capable of injecting into the RCS.C. An accumulator not C.1 Isolate affected 1 hour isolated when the accumulator.
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| accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.(continued)
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| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.12 -2 Amendment 134 LTOP System 3.4.12 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Depressurize affected 12 hours associated Completion accumulator to less Time of Condition C than the maximum RCS not met. pressure for existing cold leg temperature allowed in the PTLR.E. One required RCS E.1 Restore required RCS 7 days relief valve relief valve to inoperable in MODE 4. OPERABLE status.F. One required RCS F.1 Restore required RCS 24 hours relief valve relief valve to inoperable in MODE 5 OPERABLE status.or MODE 6 when the reactor vessel head is on.G. Two required RCS G.1 Depressurize RCS and 8 hours relief valves establish RCS vent of inoperable.
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| 2 2.0 square inches.OR Required Action and associated Completion Time of Condition D.E, or F not met.OR LTOP System inoperable for any reason other than Condition A. B.C. D, E. or F.BRAIDWOOD
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| -UNITS 1 & 2 3.4.12 -3 Amendment 98 LTOP System 3.4 .12 SURVEI LLANCE REQUI REMENTS SR 3.4.12.1 SURVEILLANCE Verify no SI pump is capable of injecting into the RCS. FREQUENCY In accordance with the Surveil 1 ance Frequency Control Program SR 3.4.12.2 Verify a maximum of one charging pump (centrifugal) is capable of injecting into the RCS. In accordance with the Surveillance Frequency Control Program SR 3.4.12.3 Only required to be met for accumulator whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the PIT limit curves provided in the PTLR. Verify each accumulator is isolated.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.4.12.4 Verify required RCS vent? 2.0 square inches open. In accordance with the Surveillance Frequency Control Program (continued)
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| BRAIDWOOD
| |
| -UNITS 1 &2 3.4.12-4 Amendment LTOP System 3.4.12 SURVEI LLANC E REOU IREMENTS (continued)
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| SURVEILLANCE FREQUENCY SR 3.4.12.5 Verify RHR suction valves are open for each In accordance required RHR suction relief valve. with the Surveillance Frequency Control Program SR 3.4.12.6 Verify PORV block valve is open for each In accordance requi red PORV. with the Survei 11 ance Frequency Control Program SR 3.4.12.7 ---------------NOTE--------------Not required to be performed until 12 hours after decreasing RCS cold leg temperature to 350°F. Perform a COT on each required PORV, In accordance excluding actuation.
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| with the Surveillance Frequency Control Program SR 3.4.12.8 Perform CHANNEL CALIBRATION for each In accordance required PORV actuation channel. with the Survei 11 ance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.12-5 Amendment RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to: a. No pressure boundary LEAKAGE;b. 1 gpm unidentified LEAKAGE;c. 10 gpm identified LEAKAGE; and d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).I APPLICABILITY:
| |
| MODES 1, 2, 3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A.1 Reduce LEAKAGE to 4 hours LEAKAGE not within within limits.limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 5. 36 hours OR Pressure boundary LEAKAGE exists.OR Primary to secondary LEAKAGE not within limit.BRAIDWOOD
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| -UNITS 1 & 2 3.4.13 -1 Amendment144 RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 ----------------
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| : 1. Not requi red to be performed Lint i 1 12 hours after establishment of steady state operation.
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| : 2. Not applicable to primary to secondary LEAKAGE. Verify RCS operational LEAKAGE is within In accordance limits by performance of RCS water with the inventory balance. Surveillance Frequency Control Program SR 3.4.13.2 -------------NOTE----------Not required to be performed until 12 hours after establishment of steady state Verify primary to secondary LEAKAGE In accordance 150 gallons per day through anyone SG. with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.13 -2 Amendment RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 APPLICABILITY:
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| Leakage from each RCS PIV shall be within limits.MODES 1. 2. 3. and 4.ACTIONS-- NOTES--- ------ ----------
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| -1. Separate Condition entry is allowed for each flow path.2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths --NOTE with leakage from one Each valve used to satisfy or more RCS PIVs not Required Action A.1 and within limit. Required Action A.2 must have been verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary or the high pressure portion of the system.A.1 Isolate the high 4 hours pressure portion of the affected system from the low pressure portion by use of one closed manual.de-energized power operated.de-activated automatic.
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| or check valve.AND (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.4.14- 1 Amendment 98 RCS PIV Leakage 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
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| A.2 Isolate the high 72 hours pressure portion of the affected system from the low pressure portion by use of a second closed manual.de-energized power operated.de-activated automatic, or check valve.B. Residual Heat Removal B.1 Isolate the affected 4 hours (RHR) System suction flow path by use of isolation valve one de-energized interlock function power operated valve.inoperable.
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| C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours BRAIDWOOD
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| -UNITS 1 & 2 3.4.14 -2 Amendment 98 SURVEILLANCE SR 3.4.14.1
| |
| : 1. Only required to be performed in MODES 1 and 2. 2. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided. 3. Not required to be performed for RH8701A and Band RH8702A and B on the Frequency required following valve actuation or flow through the valve. Verify leakage from each RCS PIV is equivalent to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure 2215 psig and 2255 psig. RCS PIV Leakage 3.4.14 In accordance with the Inservice Testing Program, and in accordance with the Surveillance Frequency Control Program AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days, if leakage testing has not been performed once within the previous 9 months (continued)
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| BRAIDWOOD UNITS 1 &2 3.4.14 -3 Amendment RCS PIV Leakage 3.4 .14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 (continued)
| |
| Within 24 hours following valve actuation due to automatic or manual action or flow through the valve SR 3.4.14.2 Verify RHR System suction isolation valve interlock prevents the valves from being opened with a simulated or actual RCS pressure signal 360 psig. In accordance with the Surveil 1 ance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.14-4 Amendment RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:
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| : a. One containment sump monitor; and b. One containment atmosphere radioactivity monitor (gaseous or particulate).
| |
| APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION A. Required containment sump monitor inoperable.
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| BRAIDWOOD
| |
| -UNITS 1 & 2 A.1 AND A.2 REQU I RED ACTION Not required to be performed until 12 hours after establishment of steady state operation.
| |
| Perform SR 3.4.13.1.
| |
| Restore required containment sump monitor to OPERABLE status. 3.4.15-1 COMPLETION TIME Once per 24 hours 30 days (continued)
| |
| Amendment No. 179 ACTIONS (continued)
| |
| CONDITION B. Required containment atmosphere radioactivity monitor inoperable.
| |
| C. ---------NOTE--------
| |
| Only applicable when the containment atmosphere gaseous radioactivity monitor is the only OPERABLE monitor. ---------------------
| |
| Required containment sump monitor inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 B.l.1 OR B.l.2 AND B.2 C.1 AND C.2 RCS Leakage Detection Instrumentation 3.4.15 REQUIRED ACTION COMPLETION TIME Analyze grab samples Once per 24 of the containment hours atmosphere.
| |
| ---------NOTE--------
| |
| Not required to be performed until 12 hours after establishment of steady state operation.
| |
| ---------------------
| |
| Perform SR 3.4.13.1.
| |
| Once per 24 hours Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status. Analyze grab samples Once per 12 of the containment hours atmosphere.
| |
| Restore required 7 days containment sump monitor to OPERABLE status. (contlnued) 3.4.15-2 Amendment No. 179 RCS Leakage Detection Instrumentation 3.4 .15 ACTIONS (continued)
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| D. Required Action and D.1 Be in MODE 3. associated Completion Time not met. AND D.2 Be in MODE 5. E. All required monitors E.1 Enter LCD 3.0.3. inoperable.
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| SURVEILLANCE REQUIREMENTS SR 3.4.15.1 SR 3.4.15.2 SR 3.4.15.3 SR 3.4.15.4 SURVEILLANCE Perform CHANNEL CHECK of the required containment atmosphere radioactivity monitor. Perform COT of the required containment atmosphere radioactivity monitor. Perform CHANNEL CALIBRATION of the required containment sump monitor. Perform CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor. BRAIDWOOD
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| -UNITS 1 & 2 3.4.15-3 6 hours 36 hours Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 179 RCS Specific Activity 3.4 .16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits. APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. CONDITION REQU I RED ACTI ON COMPLETION TIME A. DOSE EQUIVALENT 1-131 not within limit.
| |
| LCO 3.0.4.c is applicable.
| |
| A.1 Verify DOSE EQUIVALENT 1-131 60 J.tCi/gm.
| |
| AND A.2 Restore DOSE EQUIVALENT 1-131 specific activity to withi n 1 imit. Once per 4 hours 48 hours B. DOSE EQUIVALENT XE-133 not within limit.
| |
| LCO 3.0.4.c is applicable.
| |
| | |
| ===8.1 Restore===
| |
| DOSE EQUIVALENT XE-133 to within 1 imit. 48 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.16 -1 Amendment RCS Specific Activity 3.4.16 ACTI ONS (cont i nued ) CONDITION REQUI RED ACTION COMPLETIDN TIME C. Required Action and associated Completion Time of Condition A or B not met. OR DOSE EQUIVALENT I 131 > 60 ),tCi/gm.
| |
| C.1 AND C.2 Be in MODE 3. Be in MODE 5. 6 hours 36 hours SURVEILLANCE SR SR 3.4.16.1 3.4.16.2 SURVEILLANCE Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity 603 ).tCi/gm.
| |
| Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity 1.0 ),tCi/gm.
| |
| FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Between 2 and 6 hours after a THERMAL POWER change of 15% RTP withi n a 1 hour period BRAIDWOOD UNITS 1 &2 3.4.16 -2 Amendment RCS Loop Isolation Valves 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.17 RCS Loop Isolation Valves LCO 3.4.17 APPLICABILITY:
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| Each RCS hot and cold leg loop isolation valve shall be open with power removed from each isolation valve operator.MODES 1. 2. 3. and 4.ACTIONS Separate Condition entry is allowed-NOTE- --for each RCS loop isolation valve.CONDITION REQUIRED ACTION COMPLETION TIME A. Power available to one A.1 Remove power from 30 minutes or more loop isolation loop isolation valve valve operators.
| |
| operators.
| |
| B. ---NOTE B.1 Maintain valve(s) Immediately All Required Actions closed.shall be completed whenever this AND Condition is entered.B.2 Be in MODE 3. 6 hours One or more RCS loop AND isolation valves closed. B.3 Be in MODE 5. 36 hours BRAIDWOOD
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| -UNITS 1 & 2 3.4.17 -1 Amendment 98 RCS Loop Isolation Valves 3,4,17 SURVEI LLANCE SURVEI SR 3.4,17.1 Verify each RCS loop isolation valve is open and power is removed from each loop isolation valve operator.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3,4,17 -2 Amendment RCS Loops-Isolated 3.4.18 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.18 RCS Loops-Isolated LCO 3.4.18 Each RCS isolated loop shall remain isolated with: a. The hot and cold leg loop stop isolation valves closed if boron concentration of the isolated loop is less than the required SDM boron concentration of the unisolated portion of the RCS: and b. The cold leg loop stop isolation valve closed if the cold leg temperature of the isolated loop is > 20 0 F below the highest cold leg temperature of the unisolated portion of the RCS.APPLICABILITY:
| |
| MODES 5 and 6.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Isolated loop hot or A.1 Close hot and cold Immediately cold leg isolation leg isolation valves.valve open with boron concentration requirement not met.B. Isolated loop cold leg B.1 Close cold leg Immediately isolation valve open isolation valve.with temperature requirement not met.BRAIDWOOD
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| -UNITS 1 & 2 3.4.18 -1 Amendment 98 RCS Loops-Isolated 3.4.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.18.1 Verify cold leg temperature of isolated Within loop is.s 20 0 F below the highest cold leg 30 minutes temperature of the unisolated portion of prior to the RCS. opening the cold leg isolation valve in the isolated loop SR 3.4.18.2 Verify boron concentration of isolated loop Within 4 hours is greater than or equal to the required prior to SDM boron concentration of the unisolated opening the hot portion of the RCS. or cold leg isolation valve in the isolated loop BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.18 -2 Amendment 98 SG Tube Integrity 3.4 .19 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.19 Steam Generator (SG) Tube Integrity LCO SG tube integrity shall be maintained.
| |
| AND All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with the Steam Generator Program.
| |
| MODES 1, 2, 3, and 4. ACTIONS ----------------
| |
| ---------------NOTE---------------------------------Separate Condition entry is allowed for each SG tube. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes satisfying the tube plugging criteria and not plugged in accordance with the Steam Generator Program. A.1 AND Verify tube integrity of the affected tube(s) is maintained until the next refueling outage or SG tube inspection.
| |
| 7 days A.2 Plug the affected tube(s) in accordance with the Steam Generator Program. Prior to entering MODE 4 following the next refueling outage or SG tube inspection B. Required Action and associated Completion Time of Condition A not met. B.1 AND Be in MODE 3. 6 hours OR B.2 Be in MODE 5. 36 hours SG tube integrity not maintained.
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| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.19 Amendment 172/172 SG Tube Integrity 3.4.19 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.19.1 Verify SG tube integrity in accordance with the Steam Generator Program. In accordance with the Steam Generator Program SR 3.4.19.2 Verify that each inspected SG tube that satisfies the tube plugging criteria is plugged in accordance with the Steam Generator Program. Prior to entering MODE 4 following a SG tube inspection BRAIDWOOD
| |
| -UNITS 1 &2 3.4.19 -2 Amendment 172/172 Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.1 Accumulators LCO 3.5.1 Four ECCS accumulators shall be OPERABLE.APPLICABILITY:
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| MODES 1 and MODE 3 with> 1000 2., Reactor Coolant System (RCS) pressure psig.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours inoperable due to concentration to boron concentration within limits.not within limits.B. One accumulator B.1 Restore accumulator 1 hour inoperable for reasons to OPERABLE status.other than Condition A.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND or B not met.C.2 Reduce RCS pressure 12 hours to 5 1000 psig.D. Two or more D.1 Enter LCO 3.0:.3. Immediately accumulators inoperable.
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| BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.1 -1 Amendment 98 Accumulators
| |
| | |
| ====3.5.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. In accordance with the Surveillance Frequency Contro 1 Program SR 3.5.1.2 Verify borated water level in each accumulator is 31% and 63%. In accordance with the Surveillance Frequency Control Program SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is 602 psig and 647 psig. In accordance with the Surveillance Frequency Control Program SR 3.5.1.4 Verify boron concentration -i n each accumulator is 2200 ppm and 2400 ppm. In accordance with the Surveillance Frequency Contro 1 Program SR 3.5.1.5 -Only required to be performed for affected accumulators after each solution volume increase of 10% of indicated level that is not the result of addition from the refueling water storage tank containing a boron concentration 2200 ppm and 2400 ppm. -----Verify boron concentration in each accumulator is 2200 ppm and 2400 ppm. Once within 6 hours SR 3.5.1.6 Verify power is removed from each accumulator isolation valve operator.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.5.1-2 Amendment ECCS- Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.2 ECCS -Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.-- NOTES -------- ----1. In MODE 3. both Safety Injection (SI) pump flow paths and a portion of both Residual Heat Removal (RHR) pump flow paths may be isolated by closing the isolation valves for up to 2 hours to perform pressure isolation valve testing per SR 3.4.14.1.2. In MODE 3. a portion of both Residual Heat Removal (RHR)pump flow paths may be isolated by closing the isolation valves for up to 2 hours to perform pressure isolation valve testing per SR 3.4.14.1.
| |
| provided an alternate means of cold leg injection is available for each isolated flow path.APPLICABILITY:
| |
| MODES 1. 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One train inoperable.
| |
| A.1 Restore train to 7 days OPERABLE status.B. Two trains inoperable.
| |
| B.1 Restore one train to 72 hours OPERABLE status.AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2.3.5.2 -1 Amendment 98 ECCS -Operating
| |
| | |
| ====3.5.2 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.2 -2 Amendment 98 SURVEILLANCE REQUIREMENTS SR 3.5.2.1 SR 3.5.2.2 SURVEILLANCE Verify the following valves are in the listed position with power to the valve operator removed: Number Position Function MDV SI8806 Open Suction to SI Pumps MOV SI8835 Open SI Pump Discharge to Reactor Coolant System CRCS) Cold Legs MDV SI8813 Open SI Pump Recirculation to the Refueling Water Storage Tank MDV SI8809A Open RHR Pump Discharge to RCS Cold Legs MDV SI8809B Open RHR Pump Discharge to RCS Cold Legs MDV SI8840 Closed RHR Pump Discharge to RCS Hot Legs MDV SI8802A Closed SI Pump Discharge to RCS Hot Legs MDV SI8802B Closed SI Pump Discharge to RCS Hot Legs --------------------NOTE-------------------
| |
| Not required to be met for system vent flow paths opened under administrative control. Verify each ECCS 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.
| |
| ECCS-Operating
| |
| | |
| ====3.5.2 FREQUENCY====
| |
| | |
| In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.2 -3 Amendment No. 183 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.5.2.3 Verify ECCS locations susceptible to gas accumulation are sufficiently filled with water. < SR 3.5.2.4 Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head. SR 3.5.2.5 Verify each ECCS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. SR 3.5.2.6 Verify each ECCS pump starts automatically on an actual or simulated actuation signal. SR 3.5.2.7 Verify, for each ECCS throttle valve listed below, each position stop is in the correct position:
| |
| Valve Number Valve Function SI8810 A,B,C,D Centrifugal Charging System SI8816 A,B,C,D SI System CHot Leg) SI8822 A,B,C,D SI System (Cold Leg) SR 3.5.2.8 Verify, by visual inspection, each ECCS train containment sump suction inlet is not restricted by debris and the suction inlet screens show no evidence of structural distress or abnormal corrosion.
| |
| ECCS-Operating
| |
| | |
| ====3.5.2 FREQUENCY====
| |
| | |
| In accordance with the Surveillance Frequency Control Program In accordance with the Inservice Testing Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.2 -4 Amendment No. 183
| |
| | |
| ===3.5 EMERGENCY===
| |
| | |
| CORE COOLING SYSTEMS CECCS) 3.5.3 ECCS-Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.
| |
| APPLICABILITY:
| |
| MODE 4. ACTIONS ECCS-Shutdown 3.5.3 ----------------------------------NOTE---------------------------------
| |
| LCO 3.0.4.b is not applicable to ECCS high head subsystem.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS RHR A.1 Initiate action to Immediately subsystem inoperable.
| |
| restore required ECCS RHR subsystem to OPERABLE status. B. Required ECCS B.1 Restore required ECCS 1 hour centrifugal charging centrifugal charging subsystem inoperable.
| |
| subsystem to OPERABLE status. c. Required Action and C.1 Be in MODE 5. 24 hours associated Completion Time of Condition B not met. BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.3-1 Amendment . 1 7 6 ECCS -Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all In accordance equipment required to be OPERABLE:
| |
| with applicable SRs SR 3.5.2.1 SR 3.5.2.7 SR 3.5.2.3 SR 3.5.2.8.SR 3.5.2.4 BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.3 -2 Amendment 98 RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.4 Refueling Water Storage Tank (RWST)LCO 3.5.4 APPLICABILITY:
| |
| The RWST shall be OPERABLE.MODES 1. 2. 3. and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron A.1 Restore RWST to 8 hours concentration not OPERABLE status.within limits.OR RWST borated water temperature not within limits.B. RWST inoperable for B.1 Restore RWST to. 1 hour reasons other than OPERABLE status.Condition A.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.4 -1 Amendment 98 RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Only required to be performed when ambient air temperature is < 35°F or > 100°F. Verify RWST borated water temperature is ;::: 35°F and lOO°F. In accordance with the Surveillance Frequency Control Program SR 3.5.4.2 Only required to be performed when ambient air temperature is < 35°F. Verify RWST ;::: 35°F. vent path temperature is In accordance with the Surveillance Frequency Control Program SR 3.5.4.3 Verify RWST borated water level is 89%. In accordance with the Surveillance Frequency Control Program SR 3.5.4.4 Verify RWST boron concentration is ;::: 2300 ppm and 2500 ppm. In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.5.4 -2 Amendment Seal Injection Flow 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.5 Seal Injection Flow LCO 3.5.5 APPLICABILITY:
| |
| Reactor coolant pump seal injection flow shall be within the limits of Figure 3.5.5-1.MODES 1. 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Seal injection flow A.1 Adjust manual seal 4 hours not within limit. .injection throttle valves to give a flow within the limits of Figure 3.5.5-1.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours BRAIDWOOD
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| -UNITS 1 & 2 3.5.5 -1 Amendment 98 Seal Flow 3.5.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR -------------NOTE-----------Not requ-i red to be performed until 4 hours after the Reactor Coolant System pressure stabilizes at 2215 psig and s 2255 psig. Verify manual seal injection throttle valves are adjusted to give a flow within the limits of Figure 3.5.5 1. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.5.5 -Amendment 165/165 Seal Injection Flow 3.5.5 250 225 200 175 150 125 100 75 50 225).. .. ... .....ACCEPTABLE REGION....* (49.28, 150)(44, 1 .0)63.43) (32, 63.43) UNACCEPTAI-1 200)(24, LE REGION 25 70 0 20 30 40 50 60 SEAL INJECTION FLOW (GPM)Figure 3.5.5-1 (page 1 of 1)Seal Injection Flow Limits BRAIDWOOD
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| -UNITS 1 & 2 3.5.5 -3 Amendment 98 Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 APPLICABILITY:
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| Containment shall be OPERABLE.MODES 1, 2. 3. and 4.ACTIONS CONDITION REQUIRED ACTION' COMPLETION TIME A. Containment A.1 Restore containment 1 hour inoperable.
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| to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and In accordance leakage rate testing except for containment with the air lock testing, in accordance with the Containment Containment Leakage Rate Testing Program. Leakage Rate Testing Program (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.1 -1 Amendment 98 Containment
| |
| | |
| ====3.6.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
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| SURVEILLANCE FREQUENCY SR 3.6.1.2 Verify containment structural integrity in In accordance accordance with the Containment Tendon with the Surveillance Program. Containment Tendon Surveillance Program BRAIDWOOD
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| -UNITS 1 & 2 3.6.1 -2 Amendment 98 Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 APPLICABILITY:
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| Two containment air locks shall be OPERABLE.MODES 1, 2, 3. and 4.ACTIONS-- -NOTES- ---------------
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| ~1. Entry and exit is permissible to perform repairs on the affected air lock components.
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| : 2. Separate Condition entry is allowed for each air lock.3. Enter applicable Conditions and Required Actions of LCO 3.6.1."Containment." when air lock leakage results in exceeding the overall containment leakage rate.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more NOTES- ---containment air locks 1. Required Actions A.1.with one containment A.2. and A.3 are not air lock door applicable if both doors inoperable.
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| 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)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.2 -1 Amendment 98 Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
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| A.1 Verify the OPERABLE 1 hour door is closed in the affected air lock.AND A.2 Lock the OPERABLE 24 hours door closed in the affected air lock.AND A.3 ----NOTE-- --Air lock doors in high radiation areas may be verified locked closed by administrative means.Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.2 -2 Amendment 98 Containment Air Locks 3.6.2 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME B. One or more containment air locks with containment air lock interlock mechanism inoperable.
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| ----- -NOTES---------
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| : 1. Required Actions B.1.B.2. and B.3 are not applicable if both doors in the same air lock are inoperable and Condition C is entered.2. Entry and exit of containment is permissible under the control of a dedicated individual.
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| B.1 Verify an OPERABLE door is closed in the affected air lock.AND B.2 AND B.3 Lock an OPERABLE door closed in the affected air lock.----NOTE---Air lock doors in high radiation areas may be verified locked closed by administrative means.1 hour 24 hours Once per 31 days Verify an OPERABLE door is locked closed in the affected air lock.I &(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.2 -3 Amendment 98 Containment Air Locks 3.6.2 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME C. One or more C.1 Initiate action to Immediately containment air locks evaluate overall inoperable for reasons containment leakage other than Condition A rate per LCO 3.6.1.or B.AND C.2 Verify a door is 1 hour closed in the affected air lock.AND C.3 Restore air lock to 24 hours OPERABLE status..D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours BRAIDWOOD
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| -UNITS 1 & 2 3.6.2 -4 Amendment 98 Containment Air Locks 3.6.2 SURVEI LLANCE REQUI SURVEILLANCE FREQUENCY SR 3.6.2.1 --------------
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| ----NOTES----
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| -----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 applicable to SR 3.6.1.1. Perform required air lock leakage rate In accordance testing in accordance with the Containment with the Leakage Rate Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be In accordance with the opened at a time. Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.6.2 -5 Amendment Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 APPLICABILITY:
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| Each containment isolation valve shall be OPERABLE.MODES 1. 2. 3, and 4.ACTIONS____- --------NOTES-----------
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| : 1. Penetration flow path(s) except for 48 inch purge valve 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 containment isolation valves.4. Enter applicable Conditions and Required Actions of LCO 3.6.1."Containment." when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.CONDITION REQUIRED ACTION COMPLETION TIME A. -NOTE -A.1 Isolate the affected 4 hours Only applicable to penetration flow path penetration flow paths by use of at least with two containment one closed and isolation valves. de-activated
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| _ automatic or remote manual valve. closed One or more manual valve, blind penetration flow paths flange, or check with one containment valve with flow isolation valve through the valve inoperable except for secured.purge valve leak age not within limit. AND (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.3 -.1 Amendment 98 Containment Isolation Valves 3.6.3 ACTIONS CONDITION IREQUIRED ACTION [COMPLETION TIME A. (continued)
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| A.2----NOTES ------1. Isolation devices in high radiation areas may be verified by use of administrative means.2. Isolation devices that are locked, sealed. or otherwise secured may be verified by use of administrative means.Verify the affected penetration flow path is isolated.Once per 31 days for isolation devices outside containment AND Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days for isolation devices inside containment A. I (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.3 -2 Amendment 98 Containment Isolation Valves 3.6.3 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME B. -------NOTE-- ----- B.1 Isolate the affected 1 hour Only applicable to penetration flow path penetration flow paths by use of at least with two containment one closed and isolation valves. de-activated automatic or remote manual valve, closed One or more manual valve, or penetration flow paths blind flange.with two containment isolation valves inoperable except for purge valve lea kage not within limit.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.3 -3 Amendment 98 Containment Isolation Valves 3.6.3 ACTIONS (continued)
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| CONDITION I REQUIRED ACTION I COMPLETION TIME C. ------NOTE----Only applicable to penetration flow paths with only one containment isolation valve and a closed system.C. 1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic or remote manual valve, closed manual valve, or blind flange.72 hours One or more penetration flow paths with one containment isolation valve inoperable.
| |
| AND C.2-NOTES --1. Isolation devices in high radiation areas may be verified by use of administrative means.2. Isolation devices that are locked.sealed. or otherwise secured may be verified by use of administrative means.Verify the affected penetration flow path is isolated.Once per 31 days D. One or more D.1 Restore purge valve 24 hours penetration flow paths leakage to within with one or more limits.containment purge valves not within p urge valve leakage iMits.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.3 -.4 Amendment 98 Containment Isolation Valves 3.6.3 ACTIONS (continued)
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| CONDITION REQUIRED E. Required Action and E.1 Be in MODE 3. associated Completion Time not met. AND E.2 Be in MODE 5. SURVEILLANCE COMPLETION 6 36 SR 3.6.3.1 SURVEI LLANCE Verify each 48 inch purge valve is sealed closed. FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.6.3.2 Verify each 8 inch purge valve is closed, except when the 8 inch containment purge valves are open for purging or venting under administrative controls.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.6.3.3 Valves and blind flanges in high radiation areas may be verified by use of administrative controls.
| |
| Verify each containment isolation manual valve, remote manual valve, and blind flange that is located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for conta"j nment i so 1 at i on valves that a re open under administrative controls.
| |
| In accordance with the Survei 11 ance Frequency Control Program (continued)
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| BRAIDWOOD
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| -UNITS 1 &2 3.6.3 -5 Amendment Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)
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| SURVEI LLANCE FREQUENCY SR 3.6.3.4 ---------------
| |
| NOTE ----------------
| |
| Valves and blind flanges in high radiation areas may be verified by use of administrative means. Verify each containment isolation manual valve, remote manual valve, and blind ange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.
| |
| Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days SR 3.6.3.5 Verify the isolation time of each automatic containment isolation valve is within limits. In accordance with the Inservice Testing Program SR 3.6.3.6 Perform leakage rate testing for 8 inch containment purge valves with resilient seals. In accordance with the Survei 11 ance Frequency Control Program SR 3.6.3.7 Perform leakage rate testing for 48 inch containment purge valves with resilient seals. In accordance with the Surveillance Frequency Control Program SR 3.6.3.8 Verify each automatic containment isolation valve that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.6.3 -6 Amendment Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment LCD 3.6.4 Containment pressure shall be -0.1 psig and +1.0 APPLICABILITY:
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| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQU I RED ACTI ON COMPLETION TIME A. Containment pressure not within limits. A.1 Restore containment to within imits. 1 hour B. Required Action and associated Completion Time not met. B.1 AND B.2 Be in MODE 3. Be in MODE 5. 6 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limits. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.6.4 1 Amendment Containment Air Temperature 3.6.5 3.6 CONTAINMENT 3.6.5 Containment A-j r LCO 3.6.5 Containment average air temperature shall be APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average air temperature not within limit. A.l Restore containment average air temperature to within 1 imit. 8 hours B. Required Action and associated Completion Time not met. B.l AND B.2 Be in MODE 3. Be in MODE 5. 6 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEI LLANCE SR 3.6.5.1 Verify containment average air temperature is within limit.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.6.5 -1 Amendment 165/165 Containment Spray and Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS .3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 APPLICABILITY:
| |
| Two containment spray trains and two containment cooling trains shall be OPERABLE.MODES 1. 2. 3. and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment 7 days train inoperable.
| |
| spray train to OPERABLE status. AND 14 days from discovery of failure to meet the LCO B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 5. 84 hours C. One or more C.1 Restore containment 7 days containment cooling cooling train(s) to trains inoperable.
| |
| OPERABLE status. AND 14 days from discovery of failure to meet the LCO (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.6 -1 Amendment 98 Containment Spray and Cooling Systems 3.6.6 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION D. Required Action and D.l Be in MODE 3. associated Completion Time of Condition C AND not met. D.2 Be in MODE 5. E. Two containment spray E.l Enter LCD 3.0.3. trains inoperable.
| |
| OR Any combination of three or more trains inoperable.
| |
| SURVEILLANCE REQUIREMENTS SR 3.6.6.1 SR 3.6.6.2 SR 3.6.6.3 SU RV EI LLANCE --------------------NOTE-------------------
| |
| Not required to be met for system vent flow paths opened under administrative control. Verify each containment spray 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.
| |
| Operate each containment cooling train fan unit for 2 15 minutes. Verify each containment cooling train cooling water flow rate is 2 2660 gpm to each cooler. COMPLETION TIME 6 hours 36 hours Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.6 -2 (continued)
| |
| Amendment No. 183 Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.6.6.4 Verify each containment spray pump's In accordance developed head at the flow test point is with the greater than or equal to the required Inservice developed head. Testing Program SR 3.6.6.5 Verify each automatic containment spray In accordance valve in the flow path that is not locked, with the sealed, or otherwise secured in position, Surveillance actuates to the correct position on an Frequency actual or simulated actuation signal. Control Program SR 3.6.6.6 Verify each containment spray pump starts In accordance automatically on an actual or simulated with the actuation signal. Surveillance Frequency Control Program SR 3.6.6.7 Verify each containment cooling train In accordance starts automatically on an actual or with the simulated actuation signal. Surveillance Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed.
| |
| Foll owing maintenance that could result in nozzle blockage OR F o 11 owi ng fl u i d fl ow through the nozzles SR 3.6.6.9 Verify containment spray locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 & 2 3.6.6 -3 Amendment No. 183 Spray Additive System 3.6.7 3.6 CONTAINMENT 3.6.7 Spray Additive LCD 3.6.7 The Spray Additive System shall be APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQU I RED ACTI ON COMPLETION A. Spray Addi t i ve System 7 days A.1 Restore Spray i noperab 1 e. Additive System to OPERABLE status. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 84 hours SURVEILLANCE SR 3.6.7.1 SURVEI Verify each spray additive manual and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
| |
| FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.6.7.2 Verify spray additive tank solution level is 78.6% and 90.3%. In accordance with the Surveillance Frequency Control Program (continued)
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| BRAIDWOOD
| |
| -UNITS 1 &2 3.6.7 -1 Amendment Spray Additive System 3.6.7 SURVEI LLANCE REQUI (conti nued) SURVEILLANCE FREQUENCY SR 3.6.7.3 Verify spray additive tank sodium hydroxide solution concentration is 30% and 36% by weight. In accordance with the Surve"i 11 ance Frequency Control Program SR 3.6.7.4 Verify each spray additive automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.6.7.5 Verify spray additive flow rate from each solution's flow path. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.6.7 2 Amendment 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 (Deleted)BRAIDWOOD
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| -UNITS 1 & 2 3.6.8-1 Amendment 137
| |
| * MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)LCO 3.7.1 APPLICABILITY:
| |
| Five MSSVs per steam generator shall be OPERABLE.MODES 1, 2, and 3.I ACTIONS-------------------------------------
| |
| NOTE----------------
| |
| Separate Condition entry is allowed for each MSSV.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more steam A.1 Reduce THERMAL POWER 4 hours generators with one or to less than or equal more MSSVs inoperable.
| |
| to the Maximum Allowable
| |
| % RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.AND A.2 -------NOTE---Only required in Mode 1.Reduce the Power 36 hours Range Neutron Flux -High reactor trip setpoint to less than or equal to the Maximum Allowable% RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.BRAIDWOOD
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| -UNITS 1 & 2 3.7.1 -1 Amendment 128 MSSVs 3.7.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND OR B.2 Be in MODE 4. 12 hours One or more steam generators with > 4 MSSVs inoperable.
| |
| SURVEILLANCE REQUIREMENTS
| |
| __.SURVEILLANCE FREQUENCY SR 3.7.1.1 -------------------
| |
| NOTE--------------------
| |
| Only required to be performed in MODES 1 and 2.Verify each required MSSV lift setpoint per In accordance Table 3.7.1-2 in accordance with the with the Inservice Testing Program. Following Inservice testing, lift setting shall be within +/- 1%. Testing Program I BRAIDWOOD
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| -UNITS 1 & 2 3.7.1 -2 Amendment 128 MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)OPERABLE Main Steam Safety Valves versus Maximum Allowable Power I NUMBER OF OPERABLE MAXIMUM ALLOWABLE MSSVs PER STEAM POWER (% RTP)GENERATOR 4 56 3 < 39 2 < 23 I I I I BRAIDWOOD
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| -UNITS 1 & 2 3.7.1 -3 Amendment 128 MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)Main Steam Safety Valve Lift Settings VALVE NUMBER LIFT SETTING STEAM GENERATOR (psig +/- 3%)A B C D MS013A MS013B MS013C MS013D 1235 MS014A MS014B MS014C MS014D 1220 MS015A MS015B MS015C MS015D 1205 MS016A MS016B MS016C MS016D 1190 MS017A MS017B MS017C MS017D 1175 BRAIDWOOD
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| -UNITS 1 & 2 3.7.1 -4 Amendment 98
| |
| | |
| ===3.7 PLANT===
| |
| SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs) LCD 3.7.2 Four MSIVs and their associated actuator trains shall be OPERABLE.
| |
| APPLICABILITY:
| |
| MODE 1, MODES 2 and 3 except when all MSIVs are closed. ACTIONS MSIVs 3.7.2 CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV actuator A.1 Restore MSIV actuator 7 days train inoperable.
| |
| train to OPERABLE status. B. Two MSIVs each with B.1 Restore one MSIV 72 hours one actuator train actuator train to inoperable such that OPERABLE status. the inoperable actuator trains are in different ESF Divisions.
| |
| C. Two MSIVs each with C.1 Restore one MSIV 24 hours one actuator train actuator train to inoperable and both OPERABLE status. inoperable actuator trains are in the same ESF Division.
| |
| D. Two MSIV actuator D.1 Declare the affected Immediately trains inoperable on MSIV inoperable.
| |
| the same MSIV. (cont1nued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.2-1 Amendment No. 181 ACTIONS (continued)
| |
| CONDITION E. Three or more MSIV actuator trains inoperable.
| |
| OR Required Action and associated Completion Time of Condition A, B, or C not met. F. One MSIV inoperable in MODE 1. G. Required Action and associated Completion Time of Condition F not met. H. ---------NOTE---------
| |
| Separate Condition entry is allowed for each MSIV. ----------------------
| |
| One or more MSIV inoperable in MODE 2 or 3. I. Required Action and associated Completion Time of Condition H not met. BRAIDWOOD
| |
| -UNITS 1 & 2 E.1 F.1 G.1 H.1 AND H.2 I.1 AND I.2 REQUIRED ACTION Declare each affected MSIV inoperable.
| |
| Restore MSIV to OPERABLE status. Be in MODE 2. Close MSIV. Verify MSIV is closed. Be in MODE 3. Be in MODE 4. MSIVs 3.7.2 COMPLETION TIME Immediately 8 hours 6 hours 8 hours Once per 7 days 6 hours 12 hours 3.7.2-2 Amendment No. 181 I I I I I I I I I SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SR 3.7.2.2 SURVEILLANCE
| |
| -------------------NOTE--------------------
| |
| Only required to be performed in MODES 1 and 2. Verify closure time of each MSIV is s 5 seconds. -------------------NOTE--------------------
| |
| Only required to be performed in MODES 1 and 2. Verify each actuator train actuates the MSIV to the isolation position on an actual or simulated actuation signal. BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.2-3 MSIVs 3.7.2 FREQUENCY In accordance with the Inservice Testing Program In accordance with the Surveillance Frequency Control Program Amendment No. 181 Secondary Specific Activity 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Specific Activity 3.7.3 The specific activity of the secondary coolant shall be 0.1 DOSE EQUIVALENT 1-131. APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not within limit. A.l AND Be in MODE 3. 6 hours A.2 Be in MODE 5. 36 hours SURVEI LLANCE SR Verify the specific activity of the secondary coolant is 0.1 DOSE EQUIVALENT 1-131.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.3 -Amendment SG PORVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs)LCO 3.7.4 APPLICABILITY:
| |
| Four SG PORV lines shall be OPERABLE.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SG PORV line A.1 Restore SG PORV line 30 days inoperable.
| |
| to OPERABLE status.B. Two or more SG PORV B.1 Restore all but one 24 hours lines inoperable.
| |
| SG PORV line to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours I BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.4 -I Amendment 134 SG PORVs 3.7.4 SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each SG PORV. In accordance with the Surve-i 11 ance Frequency Control Program SR 3.7.4.2 Verify one complete cycle of each SG PORV block valve. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.4-2 Amendment 165/165 AF System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AF) System LCO 3.7.5 Two AF trains shall be OPERABLE.APPLICABILITY:
| |
| MODES 1, 2, and 3.ACTIONS----------------------------------
| |
| NOTE---------------------------------
| |
| LCO 3.0.4.b is not applicable when entering MODE 1.CONDITION REQUIRED ACTION COMPLETION TIME A. One AF train A.1 Restore AF train to 72 hours inoperable.
| |
| OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 4. 12 hours C. Two AF trains C.1 ---------NOTE--------
| |
| inoperable.
| |
| LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one AF train is restored to OPERABLE status.Initiate action to Immediately restore one AF train to OPERABLE status.BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.5 -1 Amendment 134 AF System 3.7.5 SURVEI LLANCE REQU TREMENTS SR 3.7.5.1 SURVEI LLANCE Verify each AF manual, power operated, and automatic valve in each water flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
| |
| FREQUENCY In accordance with the Survei 11 ance Frequency Control Program SR 3.7.5.2 Verify day tank contains?
| |
| 420 gal oi l. of fuel In accordance with the Surveillance Frequency Control Program SR 3.7.5.3 Operate the diesel driven AF pump for ? 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.5.4 Verify the developed head of each AF pump at the flow test point is greater than or equal to the required developed head. In accordance with the Inservice Testing Program SR 3.7.5.5 Verify each AF automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.7.5.6 Verify each AF pump starts automatically on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.7.5 -2 Amendment AF System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.7.5.7 Verify proper alignment of the required AF flow paths by verifying flow from the condensate storage tank to each steam generator.
| |
| Prior to entering MODE 2 whenever unit has been in MODE 5, MODE 6, or defueled for a cumulative period of > 30 days SR 3.7.5.8 Verify fuel oil properti es are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program. In accordance with the Diesel Fuel Oi 1 Testing Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.5 -3 Amendment CST 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST)LCO 3.7.6 APPLICABILITY:
| |
| The CST level shall be a 66%.MODES 1. 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CST level not within A.1 Verify by 4 hours limit. administrative means OPERABILITY of backup AND water supply.Once per 12 hours thereafter AND A.2 Restore CST level to 7 days within limit.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.6 -1 Amendment 98 CST 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST level is 66%. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.6 -2 Amendment CC System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CC) System LCO 3.7.7 APPLICABILITY:
| |
| The CC System shall be OPERABLE.MODES 1. 2. 3. and 4.ACTIONS~NOTE--- -----------
| |
| Enter applicable Conditions and Required Actions of LCO 3.4.6. "RCS Loops- MODE 4." for Residual Heat Removal loops made inoperable by CC.CONDITION REQUIRED ACTION COMPLETION TIME A. One CC flow path A.1 Restore CC flow path 7 days inoperable.
| |
| to OPERABLE status.B. One required CC pump B.1 Restore required CC 7 days inoperable.
| |
| pump to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition A or- AND B not met.C.2 Be in MODE 5. 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.7 -1 Amendment
| |
| : 98.
| |
| CC System 3.7.7 SURV E T L LANC E REQU I REMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Isolation of CC flow to individual components does not render the CC System inoperable.
| |
| Verify each CC manual and power operated valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.7.7.2 Verify each Essential Service Water System manual and power operated valve directly serving the CC heat exchangers that is not locked, sealed, or otherwise in the correct position, is in the correct position, or can be aligned to the correct position.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.7.7.3 Verify each required CC pump starts automatically on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.7 -2 Amendment SX System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Essential Service Water (SX) System LCD 3.7.8 The following SX trains shall be OPERABLE:
| |
| : a. Two unit-specific SX trains; and b. One opposite-unit SX train for unit-specific support. APPLICABILITY:
| |
| MODES I, 2, 3, and 4. ACTIONS CONDITION REQLI I RED ACTI ON COMPLETION TIME A. One unit-specific SX train inoperable.
| |
| A.l
| |
| : 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Operating," for Emergency Diesel Generator made inoperable by SX. 2. Enter applicable Conditions and Required Actions of LCO 3.4. 6 , "RCS Loops-MODE 4," for Residual Heat Remova 1 loops made inoperable by 5X. Restore unit-specific SX train to OPERABLE status. 72 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1& 2 3.7.8 -1 Amendment 160 SX System 3.7.8 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Opposite-unit SX train inoperable.
| |
| B.1 Restore opposite-unit SX train to OPERABLE status. 7 days C. Required Action and associated Completion Time of Condition A or B not met. C.1 Be in MODE 3. MID C.2 Be in MODE 5. 6 hours 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.8 -2 Amendment 1 60 SX System 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1
| |
| -
| |
| Isolation of SX flow to individual components does not render the SX System inoperable.
| |
| Verify each uni specific SX manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
| |
| In accordance with the Surveillance Frequency Cont ro1 P rog ram SR 3.7.8.2 --Not required when opposi unit is in MODE 1, 2, 3, or 4. Operate the opposite-unit SX 15 minutes. pump for In accordance with the Survei 11 ance Frequency Control Program SR 3.7.8.3 Cycle each opposite-unit SX crosstie valve that is not secured in the open position with power removed. In accordance with the Surveillance Frequency Control Program SR 3.7.8.4 Verify each unit specific SX automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.7.8.5 Verify each unit-specific SX pump starts automatically on an actual or simulated actuation signal. In accordance with the Survelllance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.7.8 -3 Amendment 165/165 UHS 3.7.9 3.7 PLANT 3.7.9 Ultimate Heat Sink LCD 3.7.9 The UHS shall be APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COtv'IPLETION TIME A. UHS inoperable.
| |
| A.l AND A.2 Be in MODE Be in MODE 3. 5. 6 hours 36 hours SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is 590 ft Mean Sea Level (MSL). In accordance with the Surveillance Frequency Control Program SR 3.7.9.2 Verify average water temperature of UHS is :::; lOO°F. In accordance with the Surveillance Frequency Control Program SR 3.7.9.3 Verify bottom level of UHS is :::; 584 ft MSL. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.9 1 Amendment V1 Filtraiý-or,.7.1 3. 7 PLANT SYSTEMS 3.7.10 Control Room Ventilation (VC) Filtration System LCO 3.7.10 Two VC Filtration System, tr~ainss sha11l be E,,RABLLE.
| |
| -----------------------
| |
| NOTE ------------------------
| |
| The control room envelope (CRE) boundary may be opened intermittently under administrative control.MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
| |
| APPLICABILITY:
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One VC Filtration A.1 Restore VC Filtration 7 days System train System train to inoperable for reasons OPERABLE status.other than Condition B.B. One or more VC B.1 Initiate action to Irrmnediately Filtration System implement mitigating trains inoperable due actions.to inoperable CRE boundary in MODE 1, 2, AND 3, or 4.B.2 Verify mitigating 24 hours actions ensure CRE occupant exrosures to radiologica
| |
| , chemical, and smoke hazards will not exceed limits.AND B.3 Restore CRE boundary 90 days to OPERABLE status.(continued)
| |
| : r. ~ ~ nUN l r .r._iI tTS -I C ')OF"I-i L)v~tuu UU)iC 7 .0 -Am e d Men 146 VC Filtration System 3.7.10 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION JCOMPLETION TIME.Required ction and C.I Be i, MODE 3. 6 hours associated Completion Time of Condition A or AND B not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours D. Required Action and D.i.1 Place OPERABLE VC Inmediately associated Completion Filtration System Time of Condition A train in emergency not met in MODE 5 mode.or 6, or during movement of irradiated AND fuel assemblies.
| |
| D.1.2 Verify OPERABLE VC Immediately Filtration System train is capable of being powered by an OPERABLE emergency power source.OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies.
| |
| AND D.2.2 Suspend positive Immediately reactivity additions.(continued)
| |
| BRAIDWOOD
| |
| -UNITS I & 2 3.7.10 --2 Amendment 146 1 VC Filtration System 3.7 .10 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION E. Two VC Filtration E.l Suspend movement of System trains irradiated fue 1 inoperable in MODE 5 assemblies.
| |
| or 6, or during movement of irradiated ANO fuel assemblies.
| |
| E.2 Suspend positive OR reactivity additions.
| |
| One or more VC Filtration System trains inoperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of irradiated fuel assemblies.
| |
| F. Two VC Filtration F.l Enter LCO 3.0.3. System trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B. SURVEILLANCE REQUIREMENTS SR 3.7.10.1 SURVEILLANCE Operate each VC Filtration System train with: a. Flow through the makeup system filters for 15 continuous minutes with the heaters operating; and b. Flow through the recirculation charcoal adsorber 15 minutes. BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.10-3 CCJI1PLETION TIME Ill1Tlediately Irrmediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
| |
| Amendment 1 7 7 VC Filtration System 3.7.10 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.7.10.2 Perform required VC Filtration System filter testing in accordance with the Ventilation Filter Testing Program (VFTP). In accordance wi th the VFTP SR 3.7.10.3 Verify each VC Fi ltrati on System tra-i n actuates on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.7.10.4 Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program. In accordance with the Control Room Envelope Habitabil ity Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.10 4 Amendment VC Temperature Control System 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Ventilation (VC) Temperature Control System LCO 3.7.11 APPLICABILITY:
| |
| Two VC Temperature Control System trains shall be OPERABLE.MODES 1. 2. 3. 4, 5. and 6.During movement of irradiated fuel assemblies.
| |
| ACTIONS -CONDITION REQUIRED ACTION COMPLETION TIME A. One VC Temperature A.1 Restore VC 30 days Control System train Temperature Control inoperable.
| |
| System train to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met in MODE 1. 2.3. or 4. B.2 Be in MODE 5. 36 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.11 -I Amendment 98 V~ ~ ~~~ " Thp a ur CrP ,] risle ci i j ./ ii ACTIONS (continued)
| |
| CONDITION REQUIRED AiCTION 0COHPLETION TIME C..1 I Place OPERABLE VC imediately Temperature Control C. Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.
| |
| System train in AN[C.1.2 OR Verify OPERABLE VC Irmediately Temperature Control System train is capable of being powered by an OPERABLE emergency power source.Suspend movement of Irmiediately irradiated fuel assemblies.
| |
| Suspend positive Immediately reactivity additions.(continued)
| |
| C.2.1 AND C. 2.2 I BPRAIDWOOD
| |
| -UNITS 1 & 2 uFffeYd" 14 0 VC Temperature Control System 3.7.11 ACTIONS (continued)
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME D. Two VC Temperature Control System trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.
| |
| E. Two VC Temperature Control System trains inoperable in MODE 1, 2, 3, or 4. 0.1 AND 0.2 E.1 Suspend movement of i rrad i ated fuel assemblies.
| |
| Suspend pas it i ve reactivity additions.
| |
| Enter LCO 3.0.3. Immediately Immediately Immediately SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify control room temperature gO°F. In accordance with the Surveil 1 ance Frequency Control Program SR 3.7.11.2 Verify each VC Temperature Control train has the capability to remove required heat load. System the In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UN ITS 1 & 2 3.7.11 -3 Amendment Nonaccessible Area Exhaust Filter Plenum Ventilation System 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Nonaccessible Area Exhaust Filter Plenum Ventilation System LCO 3.7.12 Three Nonaccessible Area Exhaust Filter Plenum Ventilation System trains shall be OPERABLE.
| |
| with two trains aligned for operation and one train aligned in standby.~~~- --NOTE-I-- -------~-~Nonaccessible Area Exhaust Filter Plenum Ventilation System alignment requirement may be suspended intermittently under administrative controls for purposes of train realignment.
| |
| APPLICABILITY:
| |
| MODES 1. 2, 3. and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Nonaccessible Area A.1 Restore Nonaccessible 7 days Exhaust Filter Plenum Area Exhaust Filter Ventilation System Plenum Ventilation train inoperable.
| |
| System train to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.12 -1 Amendment 98 Nonaccessible Area Exhaust Filter Plenum Ventilation System 3.7.12 SURVEILLANCE REQUIREMENTS SR 3.7.12.1 SURVEI LLANCE Operate each Nonaccessible Area Exhaust Filter Plenum Ventilation System train for ;;:: 15 minutes. FREQUENCY In accordance with the Surveillance Frequency Control Program SR SR 3.7.12.2 3.7.12.3 Perform required Nonaccessible Area Exhaust lter Pl enum Vent il at; on System fi lter testing in accordance with the Ventilation Filter Test-jng Program (VFTP). I Verify each Nbnaccessible Area Exhaust Filter Plenum Ventilation System train actuates on a manual, an actual, or a simulated actuation signal. In accordance with the VFTP In accordance with the Surveillance Frequency Control Program SR 3.7.12.4 Verify two Nonaccessible Area Exhaust Filter Plenum Ventilation System trains can maintain a pressure -0.25 inches water gauge relative to atmospheric pressure dur-j ng the emergency mode of operat i on at a flow rate of 73,590 cfm per tra-j n. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.12-2 Amendment FHB Venltilation tem 3.7.13.7. PLu-I iT BYS S E 3.7 .13 Fuel Handling Buildi ng E-xhatist Filter Plenium (FHB), Ventilation Sy'st.e-m, LCO 3.7.13 APPLICABI LITY: Two FHB Ventilation System trains shall be OPERABLE.During movement of RECENTLY .IRRADIATED FUEL assemblies in the fuel building, During movement of RECENTLY 1PF'DIATED FUEL assemblies in the containment with the equipment hatch not intact.I I i ACTIONS-------------------------------------
| |
| NOTE -------------------------------------
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION jCOMPLETION TIME A,. One FHB Ventilation A.1 Restore FHB 7 days System train Ventilation System inoperable, train to OPERABLE status.B. Required Action and B.1.1 Place OPERABLE FHB Immediately associated Completion Ventilation System Time not met. train in emergency.
| |
| mode.AND B.1.2 Verify OPERABLE FHB Immediately Ventilation System train is capable of being powered by an OPERABLE emergency power source.OR I _(continued)
| |
| BRAIDWOOD-,UNITS 1 & 2 11. 1 I L1 1 7. , I An-re-Indrieent 140 FFIB Venti I ation y m 3.7.13 A ,CTIOrlS _4__ __CONDITION ) REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.2.1 SLispend movement of Imediately RECENTLY I RRADIATED FUEL assemblies in the fuel handling building.AND B.2.2 -------- NOTE ---------Only required with equipment hatch not intact.Suspend movement of Immediately RECENTLY I RRADIATED FUEL assemblies in the containment.(continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3ý.7.13 -: 2 A--r,4111=1 11 '4'_" e I-I'L- 14 0
| |
| ------------------
| |
| --FHB Ventilation System 3.7.13 ACTIONS (continued)
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME C. FHB Ventilation C.l Suspend movement of Immediately System trai ns RECENTLY IRRADIATED inoperable.
| |
| FUEL assemblies in the fuel handling buil di ng. AND ------NOTE ------Only required with equipment hatch not intact.
| |
| movement of Immediately REC NTLY IRRADIATED FUEL assemblies in the containment.
| |
| SURVEILLANCE SR 3.7.13.1 Operate each FHB Ventilation System train for 15 minutes.
| |
| In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.7.13 -Amendment FHB Ventilation System 3.7.13 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.7.13.2 Perform required FHB Ventilation System filter testing in accordance with the Ventilation Filter Testing Program (VFTP). In accordance with the VFTP SR 3.7.13.3 Only required during movement of RECENTLY IRRADIATED FUEL assemblies with the equipment hatch not intact. Verify one FHB Ventilation System train can maintain a pressure S -0.25 inches water gauge relative to atmospheric pressure during the emergency mode of operation.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.7.13.4 Verify each FHB Ventilation System train actuates on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.7.13.5 -Only required during movement of RECENTLY IRRADIATED FUEL assemblies in the fuel handl i ng buil di ng with the equi pment hatch intact. Verify one FHB Ventilation System train can maintain a pressure $ 0.25 inches water gauge relative to atmospheric pressure during the emergency mode of operation at a flow rate $ 23,100 cfm. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.13 4 Amendment Spent Fuel Pool Water Level 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Water Level LCO 3.7.14 The spent fuel pool water level shall be 23 ft over the top of irradiated fuel assemblies seated in the storage racks. APPLICABILITY:
| |
| During movement of irradiated fuel assemblies in the spent fuel pool. ACTIONS LCO 3.0.3 is not applicable.
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME A. Spent fuel pool water 1 evel not withi n 1 i mit. A.l Suspend movement of i rradi ated fuel assemblies in the spent fuel pool. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.14.1 Verify the spent fuel pool water level is 23 ft above the top of the irradiated fuel assemblies seated in the storage racks.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.14 -1 Amendment Spent Fuel Pool Boron Concentration 3.7.15 3.7 PLANT 3.7.15 Spent Fuel Pool Boron LCD 3.7.15 The spent fuel pool boron concentration shall be ;;:: 300 APPLICABILITY:
| |
| Whenever fuel assemblies are stored in the spent fuel LCD 3.0.3 is not applicable.
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME A. Spent fuel pool boron concentration not wi thi n 1 imit. A.l Suspend movement of fuel assemblies in the spent fuel pool. Immediately AND A.2 Initiate action to restore spent fuel pool boron concentration to withi n 1 imit. Imllediately SURVEILLANCE SR 3.7.15.1 Verify the spent fuel pool boron concentration is within limit.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.7.15 -1 Amendment Spent Fuel Assembly Storage 3.7.16 3.7 PLANT1 SYSTEMS 3.7.16 Spent Fuel Assembly Storage LCO 3. 7.16 Each spent fuel assembly stored in the spent fuel pool shall, as applicable:
| |
| : a. Region 1 of Holtec spent fuel, pool storage racks Have an initial nominal enrichment of ý 5..0 weight percent U->235 to permit storage in any cell locatIon.b. Region 2 of Holtec spent fuel pool storage racks Have a combination of initial enrichment and burnup within the Acceptable Burnup Domain of Figure 3.7.16-1.Whenever fuel assemblies are stored in the spent fuel pool.APPLICABILITY:
| |
| -----CT----------
| |
| ONS-- NOTE---------------------------------
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A. 1 Initiate action to Immediately LCO not met. move the noncomplying fuel assembly into a location which restores compliance.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 371 mnmn 4 3.7.16 -1 Amendment 145 Spent Fuel Assembly Storage 3.7.16 SURVEILLANCE REQUIREMENTS
| |
| *SURVEILLANCE FREQUENCY SR 3.1.16.1 Verify by administrative means the initial Prior to*nominal enrichment of the fuel assembly is storing the:5 5.0 weight percent U-235. fuel assembly in Region 1 SR 3.7.16.2 Verify by administraLi~e means the Prior to combination of initial enrichment, burnup, storing the and decay time, as applicable, of the fuel fuel assemblyv assembly is within the Acceptable Burnup in Region2 Domain of Figure 3 .7.16-1.BRAIDWOOD
| |
| -UNITS 1 & 2 371 mnmn 4 3.7.16 -2 Amendment 145 Spent Fuel Assembly Storage 3.7.16 45000.40000-35000 2 S30000 7-9500O>. 20000 S15000 S10000 5000, 0 F -4I--+)___ACCEPTABLE
| |
| ~ ~ 1_BURNUP DOMAIN I~ I-I A NACETAL-~ __f-TIBURNUP DOMAIN 9 4-2.5 33.5 4 INITIAL U-235, ENRICHMENT (w/o)4.5 5 Figure 3.7.16-1 (page 1 of 1)Region 2 Fuel Assembly Burnup Requirements (Holtec Spent Fuel Pool Storage Racks)I BRAIDWOOD
| |
| -UNITS 1 & 2 371 mnmn 4 3.7.16 -3 Amendment 145 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 sources shall be OPERABLE: a. Two qualified circuits per bus between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and b. Two Diesel Generators MOGs) capable of supplying the onsite Class 1E AC Electrical Power Distribution System.APPLICABILITY:
| |
| MODES 1, 2, 3, and 4.ACTIONS-------------------
| |
| NOTE---------------------------------
| |
| LCO 3.0.4.b is not applicable to DGs.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more buses with A.1 Perform SR 3.8.1.1 1 hour one required qualified for the required circuit inoperable.
| |
| OPERABLE qualified AND circuits.Once per 8 hours thereafter AND A.2 Restore required 72 hours qualified circuit(s) to OPERABLE status. AND 17 days from discovery of failure to meet LCO (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1 -I Amendment 134 AC Sources- Operating 3.8.1 ACTIONS (continued)
| |
| CONDITION I REQUIRED ACTION COMPLETION TIME I B. One required DG inoperable.
| |
| B.1 1 hour Verify both opposite-unit DGs OPERABLE.It AND B.2 AND B.3 Perform SR 3.8.1.1 for the required qualified circuits.Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable.
| |
| AND Once per 24 hours thereafter 1 hour AND Once per 8 hours thereafter 4 hours from discovery of Condition 8 concurrent with inoperability of redundant required feature(s) 24 hours 24 hours (continued)
| |
| AD B.4.1 Determine OPERABLE DG is not inoperable due to common cause failure.OR B.4.2 Perform SR 3.8.1.2 for OPERABLE DG.AND BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1 -2 Amendment 108 SEP O 1 2/O
| |
| -AC Sources -Operating
| |
| | |
| ====3.8.1 ACTIONS====
| |
| I CONDITION J REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| I B.5 Restore DG to 14 days OPERABLE status.AND 17 days from discovery of failure to meet LCO C. Required Action and C.1 Restore DG to 72 hours associated Completion OPERABLE status.Time of Required Action B.1 not met.D. One or more buses with D.1 Restore one required 24 hours two required qualified qualified circuit per circuits inoperable.
| |
| bus to OPERABLE status.I I E. One DG inoperable and one or more buses with one required qualified circuit inoperable.
| |
| I OR One DG inoperable and one bus with two required qualified circuits inoperable.
| |
| ----NOTE --- ---------Enter applicable Conditions and Required Actions of LCO 3.8.9. "Distribution Systems -Operating." when Condition E is entered with no AC power source to a division._ _ _ __ _ -_ _ -----_ _ _ _ __-- -E.1 Restore required qualified circuit(s) to OPERABLE status.12 hours OR I E.2 Restore DG to OPERABLE status.12 hours______________
| |
| £ _________________________
| |
| J.(continued)
| |
| Amendment 108 20 1 G00 BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1 -3 AC Sources -Operating 3.8.1 I ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME F. Two DGs inoperable.
| |
| F.1 Restore one DG to 2 hours OPERABLE status.G. Required Action and G.1 Be in MODE 3. 6 hours associated Completion Time of Condition A. AND C. D. E, or F not met.G.2 Be in MODE 5. 36 hours OR Required Action and associated Completion Time of Required Action B.2. B.3.B.4.1. B.4.2. or B.5 not met.H. Two DGs inoperable.
| |
| H.1 Enter LCO 3.0.3. Immediately and one or more buses with one or more required qualified circuits inoperable.
| |
| OR One DG inoperable.
| |
| one bus with two required qualified circuits inoperable, and the second bus with one or more required qualified circuits inoperable.
| |
| I BRAIDWOOD
| |
| -UNITS I & 2 3.8.1 -4 Amendment 108 SEP 0 1 2S0, AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated power availability for each required qualified circuit. In accordance with the Surveillance Frequency , Control Program SR 3.8.1.2 ---A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met. Performance of SR 3.8.1.7 satisfies this SR. Verify each DG starts from standby condition and achieves steady state voltage 3950 V and $ 4580 V and frequency 58.8 Hz and $ 61.2 Hz. In accordance with the Surveillance Frequency Control Program SR 3.8.1.3 I. DG loadings may include gradual 1 oad-j ng 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 Surveillance 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 operates for 60 minutes at a load 4950 kW and $ 5500 kW. In accordance with the Survei 11 ance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.8.1 -5 Amendment 165/165 AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SR 3.8.1.4 SURVEILLANCE Verify each day tank conta-ins fue 1 oi 1 . 450 gal of FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.8.1.5 Check for and remove each day tank. accumulated water from In accordance with the Surveillance Frequency Control Program SR 3.8.1.6 Verify the fuel oil transfer system operates to automatically transfer fuel from storage tank(s) to the day tank. oil In accordance with the Surveillance Frequency Control Program SR 3.8.1. 7 Verify each DG starts from normal standby condition and achieves:
| |
| : a. In $ 10 seconds, voltage 3950 V and frequency 58.8 Hz; and b. Steady state voltage 3950 V and $ 4580 V, and frequency 58.8 Hz and $ 61. 2 Hz. In accordance with the Surveillance Frequency Control Program SR 3.8.1.8 Verify manual transfer of AC power from the required normal qualified circuit(s) to the reserve required qualified circuit(s).
| |
| sources In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1-6 Amendment 165/165 AC Sources-Operating 3.8. l SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.8.1.9 SURVEILLANCE
| |
| -------------------NOTE--------------------
| |
| This Surveillance shall not be performed in MODE 1 or 2. Verify each DG rejects a load greater than or equal to its associated single largest post-accident load, and: a. Following load rejection, the frequency is s 64.5 Hz; b. Following load rejection, the steady state voltage is 3950 V and s 4580 V; and c. Following load rejection, the steady state frequency is maintained 58.8 Hz and s 61.2 Hz. SR 3.8.1.10 -------------------NOTES-------------------
| |
| : 1. Momentary transients above the voltage limit immediately following a load rejection do not invalidate this test. 2. This Surveillance shall not be performed in MODE 1 or 2. 3. If performed with DG synchronized with offsite power, it shall be performed at a power factors 0.89. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.
| |
| Verify each DG does not trip and voltage is maintained s 5600 V during and following a load rejection 4950 kW and s 5500 kW. BRAIDWOOD UNITS 1 & 2 3.8.l 7 FREQUENCY In accordance with the Surveillance Frequency Contra l Program In accordance with the Surveillance Frequency Control Program (continued)
| |
| Amendment 187 AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.8.1.11 ----------
| |
| This Surveillance shall not be performed in MODE 1, 2, 3, or 4. Verify on an actual or simulated loss of offsite power signal: De energization of ESF buses; Load sheddi ng from ESF buses; and DG auto-starts from standby condition and: energizes permanently connected loads in 10 seconds, energizes auto-connected shutdown loads through the shutdown load sequence timers, maintains steady state voltage 3950 V and 4580 V, maintains steady state frequency 58.8 Hz and 61.2 Hz, and supplies permanently connected and auto-connected shutdown loads for 5 minutes.
| |
| In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1 -Amendment 165/165 AC Sources Operating 3.8.1 SURVEI LLANCE REOUIREMENTS (conti nued) SR 3.8.1.12 SURVE I LLANCE Verify on an actual or simulated Engineered Safety Feature (ESF) actuation signal each DG auto-starts from standby condition and: a. In 10 seconds achieves voltage 3950 V and frequency 58.8 Hz; b. Achieves steady state voltage 3950 V and 4580 V and frequency 58.8 Hz and 61.2 Hz; and c. Operates for 5 minutes. FREQUENCY In accordance with the Surve-j 11 ance Frequency Control Program SR 3.8.1.13 Verify each DG's automatic trips are bypassed on actual or simulated loss of voltage signal on the emergency bus concurrent with an actual or simulated ESF actuation signal except: a. Engine overspeed; and b. Generator differential current. In accordance with the Surveillance Frequency Control Program SR 3.8.1.14 Momentary transients outside the load range do not invalidate this test. Verify each DG operates for 24 hours: a. For 2 hours loaded 5775 kWand 6050 kW; and b. For the remaining hours of the test loaded 4950 kW and 5500 kW. In accordance with the Surveillance Frequency Control Program (continued)
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| BRAIDWOOD
| |
| -UNITS 1 &2 3.8.1 -9 Amendment AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR
| |
| ---NOTES-This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 hours loaded 4950 kW and 5500 kW or until operating temperature has stabilized. Momentary transients outside of load range do not invalidate this test. Verify each DG starts and achieves:
| |
| In accordance the In 10 seconds, voltage 3950 V Surveillance Frequency and frequency 58.8 Hz; and Control ProgramSteady state voltage 3950 V and 4580 V, and frequency 58.8 Hz and 61.2 Hz. SR 3.8.1.16 ----Surveillance shall not be performed in 1, 2, 3, or 4. Verify each DG: In accordance the a. Synchronizes with offsite power source Surveillance while loaded with emergency loads upon Frequency a simulated restoration of offsite Control Program power; Transfers loads to offsite power source; and Returns to ready-to-load operation. (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 Amendment AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SR 3.8.1.17 SURVEILLANCE ------NOTE ---------This Surveillance shall not be performed in MODE 1, 2, 3, or 4. FREQUENCY Verify, with a DG operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by: a. Returning DG to ready-to-load operation; and b. Automatically energizing the emergency load from offsite power. In accordance with the Surveillance Frequency Control Program SR 3.8.1.18 This Surveillance shall not be performed in MODE I, 2, 3, or 4. Verify interval between each sequenced load block is within +/- 10% of design interval for each safeguards and shutdown sequence timer. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.8.1 -11 Amendment AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.1.19 -----------------NOTE----------
| |
| ----Surveillance shall not be performed in 1, 2, 3, or 4. Verify on an actual or s-imulated loss of In accordance offsite power signal in conjunction with an the actual or simulated ESF actuation signal: Surveillance Frequency De-energization of ESF buses; Control Program Load shedding from ESF buses; and DG auto-starts from standby condition and: energizes permanently connected loads in 10 seconds, energizes auto-connected emergency loads through the safeguards sequence timers, achieves steady state voltage 3950 V and 4580 V, achieves steady state frequency 58.8 Hz and 61.2 Hz, and supplies permanently connected and auto-connected emergency loads for 5 minutes. In accordance standby condition, each DG achieves:
| |
| SR 3.8.1.20 Verify when started simultaneously from the Surveillance Frequency and frequency 58.8 Hz; and In 10 seconds, voltage 3950 V Control Program Steady state voltage 3950 V and 4580 V, and frequency 58.8 Hz and 61.2 Hz. BRAIDWOOD
| |
| -UNITS 1 &2 3.8.1 -Amendment 165/165 AC Sources -Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources- Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE: a. One qualified circuit between the offsite transmission network and the onsite Class lE AC electrical power distribution subsystem(s) required by LCO 3.8.10."Distribution Systems -Shutdown":
| |
| and b. One Diesel Generator (DG) capable of supplying one division of the onsite Class lE AC electrical power distribution subsystem(s) required by LCO 3.8.10.APPLICABILITY:
| |
| MODES 5 and 6.During movement of irradiated fuel assemblies.
| |
| ACTIONS-NOTE LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. Required qualified NOTE --circuit inoperable.
| |
| Enter applicable Conditions and Required Actions of LCO 3.8.10. with one required division de-energized as a result of Condition A.A.1 Declare affected Immediately required feature(s) with no offsite power available inoperable.
| |
| OR (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.2 -1 Amendment 98 AC Sources -Shutdown 3.8.2 ACTIONS CONDITION E REQUIRED ACTION I COMPLETION TIME A. (continued)
| |
| A.2.1 Suspend CORE ALTERATIONS.
| |
| AND A.2.2 Suspend movement of irradiated fuel assemblies.
| |
| AND A.2.3 Initiate action to suspend operations involving positive reactivity additions.
| |
| AND A.2.4 Initiate action to restore required qualified circuit to OPERABLE status.AND A.2.5 Declare affected Low Temperature Overpressure Protection (LTOP)feature(s) inoperable.
| |
| Immediately Immediately Immediately Immediately Immediately (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.2 -2 Amendment 98 AC Sources -Shutdown 3.8.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required DG B.1 Suspend CORE Immediately inoperable.
| |
| ALTERATIONS.
| |
| AND B.2 Suspend movement of Immediately irradiated fuel assemblies.
| |
| AND B.3 Initiate action to Immediately suspend operations involving positive reactivity additions.
| |
| AND B.4 Initiate action to Immediately restore required DG to OPERABLE status.AND B.5 Declare affected LTOP Immediately feature(s) inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.2 -3 Amendment 98 AC Sources -Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 -------------
| |
| --NOTE-----
| |
| -The following SRs are not required to be performed:
| |
| SR 3.8.1.3 SR 3.8.1.14 SR 3.8.1.9 SR 3.8.1.15 SR 3.8.1.10 SR 3.8.1.16 SR 3.8.1.11 SR 3.8.1.18 SR 3.8.1.13 SR 3.8.1.19.For AC sources required to be OPERABLE, the In accordance following SRs are applicable:
| |
| with applicable SRs SR 3.8.1.1 SR 3.8.1.11 SR 3.8.1.2 SR 3.8.1.12 SR 3.8.1.3 SR 3.8.1.13 SR 3.8.1.4 SR 3.8.1.14 SR 3.8.1.5 SR 3.8.1.15 SR 3.8.1.6 SR 3.8.1.16 SR 3.8.1.7 SR 3.8.1.18 SR 3.8.1.9 SR 3.8.1.19.SR 3.8.1.10 BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.2- 4 Amendment 98 Diesel Fuel Oil 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil LCO 3.8.3 The stored diesel fuel oil required Diesel Generator shall (DG).be within limits for each APPLICABILITY:
| |
| When associated DG is required to be OPERABLE.ACTIONS I 1n rr Separate Condition entry is allowed 11MU I I-for each DG.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with A.1 Restore stored fuel 48 hours stored fuel volume oil volume to within< 44,000 gal and limits.> 41,138 gal in storage tank(s).B. One or more DGs with B.1 Restore fuel oil 7 days stored fuel oil total total particulates particulates not within limit.within limit.C. One or more DGs with C.1 Restore stored fuel 30 days new fuel oil. oil properties to properties not within within limits.( tmits.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.3 -1 Amendment 98 Diesel Fuel on 3.8.3 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Conditions A, B, or C not met. OR One or more DGs with diesel fuel oil not within limits for reasons other than Condition A, B, or C. D.1 Declare associated DG inoperable.
| |
| Immediately SURVEILLANCE SURVE I LLANCE FREQUENCY SR 3.8.3.1 Verify each DG fuel oil storage tank(s) contains 44,000 gal of fuel. In accordance with the Surveillance Frequency Control Program SR 3.8.3.2 Verify fuel oil properties of new and stored fuel oil are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program. In accordance with the Diesel Fuel Oil Testing Program SR 3.8.3.3 Check for and each fuel oil remove accumulated water from storage tank. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.8.3 -2 Amendment DC Sources-Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCO 3.8.4 APPLICABILITY:
| |
| Division 11(21) and Division 12(22) DC electrical power subsystems shall be OPERABLE and not crosstied to the opposite unit.MODES 1, 2, 3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One battery charger A.1 Crosstie 2 hours.-inoperable.
| |
| opposite-unit bus with associated OPERABLE battery charger to the affected division.AND A.2 Restore battery 2 hours terminal voltage to greater than or equal to the minimum established float voltage.AND A.3 Verify battery float Once per 12 current < 3 amps. hours AND A.4 Restore battery 7 days charger to OPERABLE status.(continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.4 -1 Amendment SEP 1 9 124 202 DC Sources-Operating
| |
| | |
| ====3.8.4 ACTIONS====
| |
| (continued)
| |
| B. One DC electrical B.1 Open at least one 204 hours power division crosstie breaker crosstied to between the crosstied opposite-unit DC divisions.
| |
| electrical power subsystem that has an inoperable battery charger, while opposite unit is in MODE 1, 2, 3, or 4.C. One DC electrical C.1 ---------NOTE--------
| |
| power division Only required when crosstied to opposite unit has an opposite-unit DC inoperable battery.electrical power subsystem with an inoperable source, Verify opposite-unit Once per whi -opsosite unit is DC bus load 12 hours in MODE , 6, or < 200 amps.defueled.AND C.2 Open at least one 7 days crosstie breaker between the crosstied divisions.
| |
| D. One DC electrical D.1 Restore DC electrical 2 hours power subsystem power subsystem to inoperable for reasons OPERABLE status.other than Condition A, B, or C.E. Required Action and E.1 Be in MODE 3. 6 hours Associated Completion Time not met. AND E.2 Be in MODE 5. 36 hours I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.4 -2 Amendment 124 CEP 1 9 2002 DC Sources-Operating
| |
| | |
| ====3.8.4 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater In accordance than or equal to the minimum established with the float voltage. Surveillance Frequency Control Program SR 3.8.4.2 Verify each battery charger supplies a load In accordance equal to the manufacturer's rating at with the greater than or equal to the minimum Surveillance established float voltage for 8 hours. Frequency Control Program OR Verify each battery charger can recharge the battery to the fully charged state within 24 hours while supplying the largest coincident demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state. SR 3.8.4.3 ----------NOTES-------1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of the service test in SR 3.8.4.3. 2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4. In accordance Verify battery capacity is adequate to supply, and maintain OPERABLE status, the with the Surveillance required emergency loads for the design Frequency duty cycle when subjected to a battery Control Program servi ce test. BRAIDWOOD
| |
| -UN ITS 1 & 2 3.8.4 -3 Amendment 165/165 DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 -DC Sources-Shutdown LCO 3.8.5 One DC electrical power subsystem shall be OPERABLE.I--------------
| |
| :----NOTE----------------------------
| |
| The required DC electrical power subsystem may be crosstied to the opposite unit, when the opposite unit is in MODE 1, 2, 3, or 4 with an inoperable battery charger.I I APPLICABILITY:
| |
| MODES 5 and 6, During movement of irradiated fuel assemblies.
| |
| ACTIONS-------------------
| |
| NOTE-------------------------------------
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One required DC A.1 Declare affected Immediately electrical power required feature(s) subsystem inoperable inoperable.
| |
| for reasons other than Condition B. OR (continued)
| |
| I I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.5 -1 Amendment 124 SEP 19 29 O DC Sources-Shutdown
| |
| | |
| ====3.8.5 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2.1 Suspend CORE Immediately ALTERATIONS.
| |
| AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.
| |
| AND A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions.
| |
| AND A.2.4 Initiate action to Immediately restore required DC electrical power subsystem to OPERABLE status.AND A.2.5 Declare affected Low Immediately Temperature Overpressure Protection feature(s) inoperable.(continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.5 -2 Amendment 124 SEP 19 2M2 DC Sources-Shutdown
| |
| | |
| ====3.8.5 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. One required DC B.1 ---------NOTE--------
| |
| electrical power Only required when subsystem crosstied to opposite unit has an opposite-unit DC inoperable battery.electrical power subsystem with an inoperable source, Verify opposite-unit Once per while opposite unit is DC bus load is 12 hours in MODE 5, 6, or < 200 amps.defueled.AND B.2 Open at least one 7 days crosstie breaker between the crosstied divisions.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 -------------------
| |
| NOTE--------------------
| |
| The following SRs are not required to be performed:
| |
| SR 3.8.4.2 and SR 3.8.4.3.For DC sources required to be OPERABLE, the In accordance following SRs are applicable:
| |
| with applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.5 -3 Amendment 124 SEP 1 q Mt Battery Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters I LCO 3.8.6 APPLICABILITY:
| |
| Battery parameters for Division 11(21) and Division 12(22)batteries shall be within limits.When associated DC electrical power subsystems are required to be OPERABLE.I ACTIONS------------------------------------
| |
| NOTE------------------------------------
| |
| Separate Condition entry is allowed for each battery.CONDITION REQUIRED ACTION COMPLETION TIME A. One battery with one A.1 Perform SR 3.8.4.1. 2 hours or more cells with float voltage AND< 2.07 V.A.2 Perform SR 3.8.6.1 2 hours AND A.3 Restore affected cell 24 hours float voltage to> 2.07 V.B. One battery with float B.1 Perform SR 3.8.4.1 2 hours current > 3 amps.AND B.2 Restore battery float 12 hours current to < 3 amps.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.6 -1 Amendment 124 SEP 19 2 Battery Parameters
| |
| | |
| ====3.8.6 ACTIONS====
| |
| (continued)
| |
| C. -------NOTE---------
| |
| Required Action C.2 must be completed if electrolyte level was below the top of plates.------------
| |
| NOTE-------------
| |
| Required Actions C.1 and C.2 are only applicable if electrolyte level was below the top of plates.One battery with one or more cells with electrolyte level less than minimum established design limits.C.1 AND C.2 AND C.3 Restore affected cell electrolyte level to above the top of plates.8 hours 12 hours 31 days Verify no leakage.evidence of Restore affected cell electrolyte level to greater than or equal to minimum established design limits.D. One battery with D.1 Restore pilot cell 12 hours pilot cell electrolyte electrolyte temperature to temperature less than greater than or equal minimum established to minimum design limits. established design limits.E. Two batteries with E.1 Restore battery 2 hours battery parameters parameters for one not within limits. battery to within limits.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.6 -2 Amendment 124 SEP 19 2X02 Battery Parameters
| |
| | |
| ====3.8.6 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and associated Completion Time of Condition A, B, C, D or E not met. One battery with one or more cells with float voltage < 2.07 V and float current > 3 amps. F.1 Declare associated battery inoperable.
| |
| Immediately SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.8.6.1 --------NOTE Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1. Verify each battery float current is S 3 amps. In accordance with the Surveillance Frequency Control Program SR 3.8.6.2 Verify each battery pilot cell float voltage is 2.07 V. In accordance with the Surveillance Frequency Control Program SR 3.8.6.3 Verify each battery cell electrolyte level is greater than or equal to minimum established design limits. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.8.6 3 Amendment 165/165 Battery Parameters
| |
| | |
| ====3.8.6 SURVEILLANCE====
| |
| | |
| REQUIREIVIEIHS (cont-inued)
| |
| SURVEI LLANCE FREQUENCY SR 3.8.6.4 Verify each battery pilot cell electrolyte temperature is greater than or equal to minimum established design limits. In accordance with the Surveillance Frequency Control Program SR 3.8.6.5 Verify each battery cell float voltage is ?: 2.07 V. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -LIN ITS 1 & 2 3.8.6 -4 Amendment 165/165 Battery Parameters
| |
| | |
| ====3.8.6 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.8.6.6 --------NOTE--This Surveillance shall not be performed in MODE 1, 2, 3, or Verify battery capacity is 80% of manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
| |
| In accordance with the Surveillance Frequency Control Program AND 12 months when battery shows degradation or has reached 85% of the expected 1 i fe with capacity < 100% of manufacturer's rating 24 months when battery has reached 85% of the expected life with capaci ty 100% of manufacturer's rating BRAIDWOOD
| |
| -UNITS 1 &2 3.8.6 -5 Amendment 165/165
| |
| -Inverters-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters-Operating LCO 3.8.7 APPLICABILITY:
| |
| Four instrument bus inverters shall be OPERABLE.MODES 1, 2, 3, and 4.ACTIONS ._ ._ = _ _CONDITION REQUIRED ACTION COMPLETION TIME A. One instrument bus A.1 --------NOTE-inverter inoperable.
| |
| Enter applicable Conditions and Required Actions of LCO 3.8.9,"Distribution Systems-Operating" with any instrument bus de-energized.
| |
| Restore inverter to 7 days OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.7 -1 Amendment 129 Inverters-Operating
| |
| | |
| ====3.8.7 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE SR 3.8.7.1 Verify correct inverter voltage and breaker alignment to AC instrument buses.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.8.7 -2 Amendment Inverters-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters-Shutdown LCO .3.8.8 Two inverters shall be OPERABLE.I I APPLICABILITY:
| |
| MODES 5 and 6, During movement of irradiated fuel assemblies.
| |
| ACTIONS-------------------
| |
| NOTE-------------------------------------
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One -or more required A.1 Declare affected -Immediately inverters inoperable.
| |
| required feature(s) inoperable.
| |
| OR__ (continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.8 -1 Amendment 124 SEP 19 2S2 ACTIONS CONDITION REQU I RED ACTI A. (continued)
| |
| A.2.1 Suspend CORE ALTERATIONS.
| |
| AND A.2.2 Suspend movement of i rradi ated fuel assemblies.
| |
| AND A.2.3 Initiate action to suspend operations involving positive reactivity additions.
| |
| AND A.2.4 Initiate action to restore required inverters to OPERABLE status. AND A.2.5 Declare affected Low Temperature Overpressure Protection feature(s) inoperable.
| |
| Inverters-Shutdown
| |
| | |
| ====3.8.8 COMPLETION====
| |
| Irrmediately Irrmediately Irrmediately Irrmediately Irrmediately SURVEILLANCE SR 3.8.8.1 Verify correct inverter voltage and breaker alignment to required AC instrument buses.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.8.8 -2 Amendment 165/165 Distribution Systems -Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems -Operating LCO 3.8.9 The following AC. DC. and AC instrument bus electrical power distribution subsystems shall be OPERABLE for the applicable unit: Unit 1 Unit 2 A. Division 11 AC Subsystem 4.16 kV Bus 141 480 volt Bus 131X Division 11 AC Instrument Bus Subsystem A. Division 21 AC Subsystem 4.16 kV Bus 241 480 volt Bus 231X Division 21 AC Instrument Bus Subsystem=Instrument Bus 111 Instrument Bus 113 Division 11 DC Subsystem Instrument Bus 211 Instrument Bus 213 Division 21 DC Subsvstem 125 VDC Bus 111 B. Division 12 AC Subsystem 4.16 kV Bus 142 480 volt Bus 132X Division 12 AC Instrument Bus Subsystem 125 VDC Bus 211 B. Division 22 AC.Subsystem 4.16 kV Bus 242 480 volt Bus 232X Division 22 AC Instrument Bus Subsvstem Instrument Bus 112 Instrument Bus 114 Division 12 DC Subsystem Instrument Bus 212 Instrument Bus 214 Division 22 DC Subsystem 125 VDC Bus 112 125 VDC Bus 212 APPLICABILITY:
| |
| MODES 1. 2. 3. and 4.S 1 & 2 3.8.9.-1 BRAIDWOOD
| |
| -UNIT!Amendment 98 Distribution Systems -Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC electrical A.1 Restore AC electrical 8 hours power distribution power distribution subsystem inoperable.
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| subsystem to OPERABLE AND status.16 hours from discovery of failure to meet LCO B. One AC instrument bus B.1 Restore AC instrument 2 hours electrical power bus electrical power distribution subsystem distribution AND inoperable.
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| subsystem to OPERABLE status. 16 hours from discovery of failure to meet LCO C. One DC electrical C.1 Restore DC electrical 2 hours power distribution power distribution subsystem inoperable.
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| subsystem to OPERABLE AND status.16 hours from discovery of failure to meet LCO D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time of Condition A. AND B. or C not met.D.2 Be in MODE 5. 36 hours (continued)
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| I BRAIDWOOD
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| -UNITS 1 & 2 3.8.9 -2 Amendment 104 & 104*OCT 1 3 %399 Di stri buti on Systems-Operat-j ng 3.8.9 ACTI (INS ( cant in ued ) CONDITION REQUIRED ACTION COMPLETION TIME E. Two electrical power distribution subsystems inoperable that result in a loss of safety function.
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| E.1 Enter LCD 3.0.3. Immediately SURVEILLANCE REQUIREMENTS SURVEI LLANCE SR 3.8.9.1 Verify correct breaker alignments and voltage to AC, DC, and AC instrument bus electrical power distribution subsystems.
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| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.8.9 3 Amendment 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 following AC. DC, and AC instrument bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE for the applicable unit.Unit 1 Unit 2 A. Division 11 AC Subsystem 4.16 kV Bus 141 480 volt Bus 131X Division 11 AC Instrument Bus Subsystem A. Division 21 AC Subsystem 4.16 kV Bus 241 480 volt Bus 231X Division 21 AC Instrument Bus Subsystem Instrument Bus 111 Instrument Bus 113 Division 11 DC Subsystem Instrument Bus 211 Instrument Bus 213 Division 21 DC Subsystem 125 VDC Bus 111 B. Division 12 AC Subsystem 4.16 kV Bus 142 480 volt Bus .132X Division 12 AC Instrument Bus Subsystem 125 VDC Bus 211 B. Division 22 AC Subsystem 4.16 kV Bus 242 480 volt Bus 232X Division 22 AC Instrument Bus Subsystem Instrument Bus 112 Instrument Bus 114 Division 12 DC Subsystem Instrument Bus 212 Instrument Bus 214 Division 22 DC Subsystem 125 VDC Bus 112 125 VDC Bus 212 APPLICABILITY:
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| MODES 5 and 6.During movement of irradiated fuel assemblies.
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| BRAIDWOOD
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| -UNITS 1 & 2 3.8.10 -1 Amendment 98 Distribution Systems -Shutdown 3.8.10 ACTIONS-NOTE LCO 3.0.3 is not applicable.
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| CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC. or AC supported required instrument bus feature(s) electrical power inoperable.
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| distribution subsystems OR inoperable.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.8.10 -2 Amendment 98 Distribution Systems -Shutdown 3.8.10 ACTIONS CONDITION
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| -- REQUIRED ACTION COMPLETION TIME A. (continued)
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| A.2.1 Suspend CORE ALTERATIONS.
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| AND A.2.2 Suspend movement of irradiated fuel assemblies.
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| AND A.2.3 Initiate action to suspend operations involving positive reactivity additions.
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| AND A.2.4 AND A.2.5 Initiate actions to restore required AC.DC, and AC instrument bus electrical power distribution subsystem(s) to OPERABLE status.Declare associated required residual heat removal train(s)inoperable and not in operation.
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| Immediately Immediately Immediately Immediately Immediately Immediately AND A.2.6 Declare affected Low Temperature Overpressure Protection feature(s) inoperable.
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| BRAIDWOOD
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| -UNITS 1 & 2 3.8.10 -3 Amendment 98 Distribution SU RV ElL LANC E REQU I SR 3.8.10.1 Verify correct breaker alignments and voltage to required AC, DC, and AC -j nst rument bus elect ri ca 1 powe r distribution subsystems.
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| In accordance with the Surve-Ill ance Frequency Control Program BRAIDWOOD
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| -UNITS 1 & 2 3.8.10-4 Amendment Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS
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| | |
| ====3.9.1 Boron====
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| Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR. APPLICABILITY:
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| MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not within limit. A.l Suspend CORE ALTERATIONS.
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| Immediately AND A.2 Suspend positive reactivity additions.
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| Immediately AND A.3 Initiate action to restore boron concentration to within limit. Immediately SURVEILLANCE SURVEI LLANC SR 3.9.1.1 Verify boron concentration is within the limit specified in the COLR.
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| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.9.1 -1 Amendment Unborated Water Source Isolation Valves 3.9.2 3.9 REFUELING OPERATIONS
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| | |
| ====3.9.2 Unborated====
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| | |
| Water Source Isolation Valves LCO 3.9.2 Each valve secured in used to isolate unborated water sources shall be the closed position.APPLICABILITY:
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| ACTIONS MODE 6.NOTEa -for each unborated water Separate valve.Condition entry is allowed source isolation CONDITION REQUIRED ACTION COMPLETION TIME A. -- NOTE- -- A.1 Suspend CORE Immediately Required Action A.3 ALTERATIONS.
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| must be completed whenever Condition A AND is entered.__ A.2 Initiate actions to Immediately secure valve in One or more valves not closed position.secured in closed position.
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| AND A.3 Perform SR 3.9.1.1. 4 hours BRAIDWOOD
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| -UNITS 1 & 2 3.9.2-.1 Amendment 98 Unborated Water Source Isolation Valves 3.9.2 SURVEILLANCE REQUIREMENTS SURVEI SR 3.9.2.1 Verify each valve that isolates unborated water sources is secured in the closed position.
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| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.9.2 2 Amendment Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS
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| | |
| ====3.9.3 Nuclear====
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| Instrumentation LCO 3.9.3 APPLICABILITY:
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| Two source range neutron flux monitors shall be OPERABLE.MODE 6.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source A.1 Suspend CORE Immediately range neutron flux ALTERATIONS.
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| monitor inoperable.
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| A.2 Suspend positive Immediately reactivity additions.
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| B. Two required source B.1 Initiate action to Immediately range neutron flux restore one source monitors inoperable.
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| range neutron flux monitor to OPERABLE status.AND B.2 Perform SR 3.9.1.1. Once per 12 hours I I BRAIDWOOD
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| -UNITS 1 & 2 3.9.3 -1 Amendment 102 & 102 JUN 0 2 1999 Nuclear Instrumentation
| |
| | |
| ====3.9.3 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.9.3.2 Neutron detectors are excluded from CHANNEL CALIBRATION.
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| Perform CHANNEL CALIBRATION.
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| In accordance with the Survei 11 ance Frequency Control Program BRAIDWOOD
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| -UNITS 1 &2 3.9.3 2 Amendment Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS
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| | |
| ====3.9.4 Containment====
| |
| | |
| Penetrations LCD 3.9.4 The containment penetrations shall be in the following status: a. One door in the personnel air lock closed and the equipment hatch held in place 4 bolts; b. One door in the emergency air lock closed; and c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere closed by a manual or automatic isolation valve, blind flange, or equivalent.
| |
| ----------------------------NOTE----------------------------
| |
| LCD 3.9.4.a is not required to be met when in compliance with LCD 3.7.13, "Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System," or its associated Conditions and Required Actions. APPLICABILITY:
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| During movement of RECENTLY IRRADIATED FUEL assemblies within containment.
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| ACTIONS CONDITION A. One or more containment penetrations not in required status. BRAIDWOOD
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| -UNITS 1 & 2 A.l REQUIRED ACTION Suspend movement of RECENTLY IRRADIATED FUEL assemblies within containment.
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| 3.9.4-1 COMPLETION TIME Immediately Amendment 1 7 8 SURVEILLANCE REQUIREMENTS SR 3.9.4.1 SURVEILLANCE Verify each required containment penetration is in the required status. BRAIDWOOD
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| -UNITS 1 & 2 3.9.4-2 Containment Penetrations
| |
| | |
| ====3.9.4 FREQUENCY====
| |
| | |
| In accordance with the Surveillance Frequency Control Program Amendment 1 7 8 RHR and Coolant Circulation-High Water Level 3.9.5 3.9 REFUELING OPERATIONS
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| | |
| ====3.9.5 Residual====
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| Heat Removal MRHR) and Coolant Circulation-High Water Level LCO 3.9.5 One RHR loop shall be OPERABLE and in operation.
| |
| ---NOTE----, The required RHR loop may be removed s 1 hour per 8 hour period, provided permitted that would cause reduction System boron concentration.
| |
| from operation for no operations are of the Reactor Coolant APPLICABILITY:
| |
| MODE 6 with the water level 2 23 ft above the top of reactor vessel flange.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR loop requirements A.1 Suspend operations Immediately not met. involving a reduction in reactor coolant boron concentration.
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| AND A.2 Suspend loading Immediately irradiated fuel assemblies in the core.AND A.3 Initiate action to Immediately satisfy RHR loop requirements.
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| AND (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.9.5 -1 Amendment 98 ACTIONS RHR and Coolant Circulation-High Water Level 3.9.5 CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
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| A.4 Close all containment 4 hours penetrations providing direct access from containment atmosphere to outside atmosphere.
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| SURVEILLANCE REQUIREMENTS SR 3.9.5.1 SR 3.9.5.2 SURVEILLANCE Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of 1000 gpm. Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water. FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
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| -UNITS 1 & 2 3.9.5 -2 Amendment No. 183 RHR and Coolant Circulation
| |
| -Low Water Level 3.9.6 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.6 Residual====
| |
| Heat Removal (RHR) and Coolant Circulation-Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE.
| |
| and one RHR loop shall be in operation.
| |
| ~~- --NOTE -------One required RHR loop may be removed from operation and considered OPERABLE: a. To support filling and draining the reactor cavity when aligned to. or during transitioning to or from, the refueling water storage tank provided the required RHR loop is capable of being realigned to the Reactor Coolant System (RCS): or b. To support required testing provided the required RHR loop is capable of being realigned to the RCS.APPLICABILITY:
| |
| MODE 6 with the water level < 23 ft above vessel flange.the top of reactor ACTIONS CONDITION
| |
| .REQUIRED ACTION COMPLETION TIME A. One or more RHR loops A.1 Initiate action to Immediately inoperable.
| |
| restore RHR loop(s)to OPERABLE status.OR A.2 Initiate action to Immediately establish 2 23 ft of water above the top of reactor vessel flange.(continued)
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| BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.6 -1 Amendment 98 RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION B. No RHR loop in operation.
| |
| B.l Suspend operations involving a reduction in reactor coolant boron concentration.
| |
| AND B.2 Initiate action to restore one RHR loop to operation.
| |
| AND B.3 Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.
| |
| SURVEILLANCE REQUIREMENTS SR 3.9.6.1 SR 3.9.6.2 SR 3.9.6.3 SURVEILLANCE Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of 1000 gpm. Verify correct breaker alignment and indicated power available to the required RHR pump that is not in operation.
| |
| Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water. COMPLETION TIME Immediately Immediately 4 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.6 -2 Amendment No. 183 Refueling Cavity Water Level 3.9.7 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.7 Refueling====
| |
| | |
| Cavity Water Level LCO 3.9.7 Refueling cavity water level shall be maintained 23 ft above the top of reactor vessel flange. APPLICABILITY:
| |
| During movement of irradiated fuel assemblies within conta -j nment . ACTIONS CONDITION REQU I RED ACTI ON COMPLETION TIME A. Refueling cavity water level not within 1 imit. A.l Suspend movement of i rradi ated fuel assemblies within containment.
| |
| Immediately SURVEILLANCE REQUIREMENTS SURVEI LLANCE SR 3.9.7.1 Verify refueling cavity water level is 23 ft above the top of reactor vessel flange.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.9.7 -1 Amendment Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site Location The site is ]ocated in Reed Township, approximately 20 mi (32 kin)south-southwest of the city of Joliet in northern Illinois.4.1.2 Exclusion Area Boundary (EAB)The EAB shall not be less than 1591 ft (485 meters) from the outer containment wall.4.1.3 Low Population Zone (LPZ)The LPZ shall be a 1.125 mi (1811 meter) radius measured from the midpoint between the two reactors.4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies.
| |
| Each assembly, with exceptions as noted below, shall consist of a matrix of Zircaloy or ZIRLO cl-ad fuel rods with an initial composition of natural or slihlY'0ce uranium dioxide (UO ) as fuel material.
| |
| Limited substitutions of zirconium alloy or stainless steel filler rods or vacancies 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 fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.Up to 8 AREVA NP Advanced Mark-BW(A) fuel assemblies containing M5 alloy may be placed in nonlimiting Unit 1 core regions for evaluation during Cycles 15, 16, and 17.*4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies.
| |
| The control material shall be silver indium cadmium, hafnium, or a mixture of both types.BRAIDWOOD
| |
| -UNITS 1 & 24. -1Amnet15 4.0 -1 Amendment 145 Design Features 4,0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality The spent fuel storage racks are designed and shall be maintained, as applicable, with: a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;b. For Holtec spent fuel pooi storage racks, k,,-, 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Holtec International Report flI-982094, "Criticality Analysis for Byron/Braidwood Rack Installation Project," Project No. 80944, 1998;c. For Holtec spent fuel pool storage racks, a nominal 10.888 inch north-south and 10.574 inch east-west center to center distance between fuel assemblies placed in Region 1 racks;and'd. For Holtec spent fuel pool storage racks, a nominal 8.97 inch center to center distance between fuel assemblies placed in Region 2 racks.*4.3.2 Drainage The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 410 ft, 0 inches.4.3.3 Capacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 2984 fuel assemblies.
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| BRAIDWOOD
| |
| -UNITS 1 & 240 2Amnet14 4.0 -2 Amendment 145 Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The station manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.5.1.2 A Senior Reactor Operator (SRO) shall be responsible for the control room command function while either unit is in MODE 1. 2, 3. or 4. For each unit., an SRO may be designated as responsible for the control-room command function.
| |
| While both units are in MODE 5 or 6. or defueled, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.BRAIDWOOD
| |
| -UNITS 1 & 2 5.1- 1 Amendment 98 Organization 5.2 5X 0-ADMINISTRATIVE-CONTROLS 5.2 Organization" 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for facility operation and corporate management, respectively.
| |
| The onsite and offsite, organizations shall include the-positions for activities affecting safety of the nuclear power plant.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 ela a ,ionships, and job descri ptions for key personnel positions, or in equivalent forms of documentation.
| |
| These requirements, including the generic titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Quality Assurance Program;b. The station manager shall be responsible for overall safe operationof the plant and shall have control over those onsite activities necessary for safe operation and maintenanceof the plant;C. The Chief Nuclear Officer shall be responsible 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, or perform health physics or quality assurance functions, may report to theappropriate onsite manager; however, these individuals
| |
| .shall have sufficient organizational freedom to ensure their independence from operating pressures.
| |
| BRAIWOOD UN ITS 1. & 2.5.2 -1 Amendment 147 Organization 5.2 5.2 Organization Facility Staff The facility staff organization shall include the following:
| |
| : a. A total of three non-licensed operators for the two units is required all conditions.
| |
| At least one of the required non-licensed operators shall be assigned to each unit. b. Shift crew composition may be less than the minimum of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours in order to unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew to within the minimum requirements.
| |
| : c. A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
| |
| : d. Del eted. e. The operations manager or the supervisor in charge of the operations shift crews shall hold an SRO license. f. The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plant analysis with to the safe operation of the facility.
| |
| In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shi ft. BRAT DWOOD -UN ITS 1 & 2 5.2 -Amendment 1
| |
| | |
| ===5.0 ADMINISTRATIVE===
| |
| | |
| CONTROLS 5.3 Facility Staff Qualifications Facility Staff Qualifications 5.3 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
| |
| : 1) either the senior health physics supervisor or lead health physicist, shall meet or exceed the qualifications for "Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and 2) the licensed operators who shall comply only with the requirements of 10 CFR 55. BRAIDWOOD
| |
| -UNITS 1 & 2 5.3-1 Amendment 173 Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures
| |
| | |
| ====5.4.1 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. Section 7.1: c. Fire Protection Program implementation:
| |
| and d. All programs specified in Specification 5.5.BRAIDWOOD
| |
| -UNITS 1 & 2 5.4 -I Amendment
| |
| : 98.
| |
| Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.
| |
| | |
| ====5.5.1 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;b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radi6active Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3: and c. Licensee initiated changes to the ODCM: 1. Shall be documented and records of reviews performed shall be retained.
| |
| This documentation shall contain: i. sufficient information to support the change(s)together with the appropriate analyses or evaluations justifying the change(s), and ii. a determination that the change(s) maintain the levels of radioactive effluent control required by 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. pr setpoint calculations:
| |
| : 2. Shall become effective after the approval of the station manager: and BRAIDWOOD
| |
| -UNITS 1 & 2 5.5- 1 Amendment 98 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued)
| |
| : 3. Shall be submitted toW 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 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 recirculation portions of the Containment Spray, Safety Injection, Chemical and Volume Control, and Residual Heat Removal. The program shall include the following:
| |
| : a. Preventive maintenance and periodic visual inspection requirements; and b. Integrated leak test requirements for each system at least once per 18 months.The provisions of SR 3.0.2 are applicable.
| |
| 5.5.3 Deleted.BRAIDW0OD -UNITS 1 & 2 5.5 -2 Amendment I.51 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 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 shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.
| |
| The programinclude the following elements: 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; Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendix B, Table 2, Column 2 (to paragraphs 20.1001 -20.2402); Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; 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; Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the [lDCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the aDeM at least every 31 days; BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 --Amendment 156 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
| |
| : 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 re1eases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment.
| |
| conforming to 10 CFR 50.Appendix I: g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the following:
| |
| : 1. For noble gases: 5 a dose rate of 500 mrem/yr to the whole body and 5 a dose rate of 3000 mrem/yr to the skin, and 2. For Iodine-131.
| |
| Iodine-133.
| |
| Tritium. and for all radionuclides in particulate form with half lives> 8 days: 5 a dose rate of 1500 mrem/yr to any organ: 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 190.5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR. Section 3.9.cyclic and transient occurrences to ensure that components are maintained within the design limits.BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -4 Amendment 98 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity.
| |
| The program shall include baseline measurements prior to initial operations.
| |
| The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC. Determining stressing forces for inspections shall be consistent with the recornendat ions of Regulatory Guide 1.35.1, July 1990. The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
| |
| | |
| ====5.5.7 Reactor====
| |
| Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975. For reactor coolant pump motor serial numbers 4S88P961 and IS88P961, in lieu of Regulatory Position c.4.bCl) and c.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flyWheel to the circle of one-half the outer radius or a surface examination CMT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI. For all other reactor coolant pump motors, in lieu of Regulatory Position c.4.bCl) and c.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheelto the circle of one-half the outer radius or a surface examination CMT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years. BRAIDWOOD
| |
| -UNITS 1 &2 5.5 -5 Amendment 163 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Inservice Testing Proqram This program provides controls Class 1, 2, and 3 components.
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| following: ,or inservice testing of ASME Code The program shall include the a. Testing frequencies applicable to the ASME Operation and Maintenance of Nuclear Power Code) and applicable Addenda as follows: Code for Plants (ASME OM ASME OM Code and applicable Addenda terminology for inservice testing activities I Requi red Frequencies for performing inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years At At least once per least once per 7 days 31 days.At least once per 92 days At At At least least least once once once per 184 days per 276 days per 366 days At least once per 731 days;b. The provisions of SR 3.0.2 are applicable to the above required ,Frequencies and to other normal and accelerated Frequencies specified.
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| as 2 years or less in the Inservice Testing Program 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 the requirements of OM Code shall be construed to supersede any Technical Specification.
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| I BPA!DWOOD
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| -UNITS I & 2 5,5- 6 Amendment 153 Programs and Manuals 5.5 5.5 Programs and Manuals Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure SG tube integrity is maintained.
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| In addition, the Steam Generator Program shall include the following:
| |
| : a. Provisions for condition monitoring assessments.
| |
| Condition assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met. b. Performance criteria for SG tube integrity.
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| SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE. 1. Structural integrity performance criterion:
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| All service steam generator tubes shall retain structural i ntegr-j ty over the full range of normal operati ng
| |
| ("including startup, operation in the power range, standby, and cool down), all anticipated transients included in the design specification, and design basis accidents.
| |
| This includes retaining a safety factor of 3.0 against burst under normal steady state power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials.
| |
| Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse.
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| In the assessment of tube integrity, those loads that do significantly affect burst. or collapse shall be determi ned and assessed combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads. BRAIDWOOD UNITS 1 &2 5.5 --Amendment 172/172 Proqrams and Manuals -5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued)
| |
| : 2. Accident induced leakage performance criterion:
| |
| The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed a total of 1 gpm for all SGs. 3. The operational LEAKAGE performance criteria is specifi ed in LCO 3.4.l3, "Res Operat i ana 1 LEAKAGE." c. Provisions for SG tube plugging criteria.
| |
| Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal wall thickness shall be plugged. The following alternate tube plugging criteria shall be applied as an alternative to the 40% depth based criteria:
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| For Unit 2, tubes with service-induced flaws located greater than 14.01 inches below the top of the tubesheet do not require plugging.
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| Tubes with service-induced flaws located in the portion of the tube from the top of the tubesheet to 14.01 inches below the top of the tubesheet shall be plugged upon detection.
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| Amendment 172/172 BRAIDWOOD
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| -UNITS 1 &2 5.5 8 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued)
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| : d. Provisions for SG tube inspections.
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| Periodic SG tube inspections shall be performed.
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| The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tubesheet weld at the tube outlet, and that may satisfy the applicable tube plugging criteria.
| |
| For Unit 2, portions of the tube below 14.01 inches from the top of the tubesheet are excl uded from thi s requ-j rement. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.l, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is mainta-ined until the next SG inspection.
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| A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what 1 ocati ons. 1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.
| |
| : 2. For Unit 1, after the first refueling outage following SG installation, inspect each SG at least every 72 effective full power months or at least every third refueling outage (whichever results in more frequent inspections).
| |
| In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection peri od as defi ned -j n a, b, c, and d below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated.The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that a new form of degradation could BRAIDWOOD
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| -UNITS 1 & 2 5.5 9 Amendment 172/1 72 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued) potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage. After the first refueling outage following SG installation, inspect 100% of the tubes during the next 144 effective full power months. This constitutes the first inspection period; During the next 120 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the third inspection period; and During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the fourth and subsequent inspection periods. For Uni t 2, after the fi rst refue l-j ng outage fo 11 owi ng SG installation, inspect each SG at least every 48 effective full power months or at least every other refueling outage (whichever results in more frequent inspections).
| |
| In addition, the minimum number of -j nspected at each schedul ed i nspecti on shall be the number of tubes in all SGs divided by the number of inspection outages scheduled in each inspection period as defined in a, b, and c below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated.The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SGis scheduled to be BRAIDWOOD
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| -UNITS 1 & 2 5.5 -Amendment 172/172 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued) inspected in the inspection period after the determ-ination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage. After the first refueling outage following SG installation, inspect 100% of the tubes during the next 120 effective full power months. This constitutes the first inspection period; Dur-ing the next 96 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; and During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the third and subsequent inspection periods. For Unit 1, if crack indications are found in any SG then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent -inspections).
| |
| For Unit 2, if crack indications are found in any SG tube from 14.01 inches below the top of the tubesheet on the hot leg side to 14.01 inches below the top of the tubesheet on the cold leg side, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent -i nspecti ons). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack. Provisions for monitoring operational primary to secondary LEAKAGE. BRAIDWOOD
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| -UNITS 1 & 2 5.5 Amendment 172/172 Programs and Manuals 5.5 5.5 Programs andManuals 5.5.10 Secondary Water Chemistry Proqram This program provides controls for monitoring secondary wa~ter chemistry to inhibit SG tube degradation.
| |
| The program shall inc ude: a. Identification of a sampling schedule for the critical variables and control points for these variables;
| |
| : b. Identification of the procedures used to measure the values of the critical variables;, c. Identification of process samplingpoints, which shall include monitoring-the discharge of the condensate pumps for evidence of condenser inleakage;
| |
| : d. Procedures for the recording and management of data;e. Procedures defining corrective actions for all off control point chemistry conditions; and f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.BRAIDWOOD
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| -UNITS I & 2 5.5 -12 Amendment 150 Programs and.Manuals 5.5, 5..5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP)A program shall be established to implement the following required testing of Enqineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in conformancewith Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR.a. Demonstrate for each of the ESF filter systems that an inplace test of the High Efficiency Particulate Air (HEPA) filters shows a penetration specified below when tested in conformance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR, at the system flow rate specified below. Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.10.4, 3.7.12.4, and 3.7.13.5, as applicable:
| |
| ESF Ventilation System Control Room Ventilation (VC)Filtration System (makeup)Nonaccessibl e Area Exhaust Filter Plenum Ventilation System (after structural maintenance of the HEPA filter housings)Nonaccessi bl e Area Exhaust Filter Plenum Ventilation System (for reasons other than structural maintenance of the HEPA filter housings)Fuel Handling Building Exhaust Filter Plenum (FHB)Ventilation System Flow Rate Penetration
| |
| > 5400 cfm and< 6600 cfm> 60,210 cfm'and< 73,590 cfm per train, and> 20,070 cfm and< 24,530 cfm per bank< 0.05%< 1%< 1%< 1%> 60,210< 73,590 train cfm and cfm per> 18,900 cfm and< 23,100 cfm BRATIDWOOD
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| -UNITS I & 2 5.5 -13 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)
| |
| : b. Demonstrate for each of the ESF filter systems that an inplace test of the charcoal adsorber shows a bypass specified below when tested in conformance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR, at the system flow rate specified below. Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.10.4, 3.7.12.4, and' 3.7.13.5, as applicable:
| |
| ESF Ventilation System Flow Rate Bypass VC Filtration System (makeup)VC Filtration System*(reci rculati on, charcoal bedt after complete or partial replacement)
| |
| VC Filtration System (reci rcul ation for reasons other than complete or partial charcoal bed replacement)
| |
| Nonaccessible Area Exhaust Filter Plenum Venti l ation System (after structural maintenance of the charcoal adsorber housings)Nonaccessi bl e Area Exhaust Filter Plenum Ventilation System (for reasons other than structural maintenance of the charcoal adsorber housings)FHB Ventilation System> 5400 cfm and< 6600 cfm> 44,550 cfm and< 54,450 cfm> 44,550 cfm and< 54,450 cfm> 60,210 cfm and< 73,590 cfm per train, and> 20,070 cfm and< 24,530 cfm per bank< 0.1%< 2%< 1%< 1%< 1%> 60,210< 73,590 train cfm and cfm per> 18,900 cfm and< 23,100 cfm per train BRAiDWOOD
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| -UNITS 1 & 2 5.5 -14 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testinq Program (VFTP) (continued)
| |
| : c. Demonstrate for each of the ESF filter 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 conformance with Regulatory Guide 1.52, Revision-2, ANSI N510-1980, and ASTM D3803-1989, with any exceptions noted in Appendix A of the UFSAR, at a temperature of 30 0 C and a Relative Humidity (RH) specified below: ESF Ventilation System Penetration RH VC Filtration System 2.0% 70%(makeup)VC Filtration System 4% 70%(reci rcul ati on)Nonaccessible Area 4.5% 70%Exhaust Filter Plenum Ventilation System FHB Ventilation System 10% 95%d. Demonstrate for each of the ESF filter systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers is < 6 inches of water gauge when tested in conformance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR, at the system flow rate specified below. Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.10.4, 3.7.12.4, and 3.7.13.5, as applicable:
| |
| ESF Ventilation System Flow Rate VC Filtration System > 5400 cfm and _< 6600 cfm (makeup)Nonaccessible Area _ 60,210 cfm and Exhaust Filter Plenum 5 73,590 cfm per train Ventilation System FHB Ventilation System > 18,900 cfm and< 23,100 cfm BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -15 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)
| |
| : e. Demonstrate for each of the ESF filter systems that a bypass test of the combined HEPA filters and damper leakage shows a total bypass specified below at the system flow rate specified below. Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.12.4 and 3.7.13.5, as applicable:
| |
| ESF Ventilation System Flow Rate Bypass Nonaccessible Area Exhaust Filter Plenum Ventilation System FHB Ventilation Systemt60,210 cfm and! 73,590 cfm per train 18,900 cfm and< 23,100 cfm<1%< 1%f. Demonstrate that the heaters for each of the ESF filter systems dissipate the value specified below when tested in conformance with ANSI N510-1980, with anyexceptions noted in Appendix A of the UFSAR.ESF Ventilation System Wattage VC Filtration System The provisions of SR 3.0.2 test frequencies.
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| _< 29.9 kW and >_ 24.5 kW and SR 3.0.3 are applicable to the VFTP BRAIDWOOD
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| -UNITS 1 & 2 5.5 -16 Amendment 1.50 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Explosive Gas and' Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mi.t_. ur. .otaed in. t.he waste gas system,Ulte quantity of radioactivity contained in gas decay tanks or fed into the off gas treatment system, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. 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." The liquid radwaste quantities shall be determined in accordance with the ODCM.The program shall include: a. The limits for concentrations of hydrogen and oxygen in the waste gas system and a surveillance program to ensure the limits are maintained.
| |
| Such limits shall be appropriate to the system's 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 contained in each gas decay tank and fed into the offgas treatment system is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks'contents.The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.
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| BRAIDWOOD
| |
| -UNITS I & 2 5.5 -17 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Diesel Fuel Oil Testing ProQram 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, and 3. a clear and bright appearance with proper color or a water and sediment content within limits;b. Other properties of new fuel oil are within limits within 30 days following sampling and addition to storage tanks;and c. Total particulate concentration of the fuel oil is 1 10 mg/l when tested every 31 days.The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test frequencies.
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| BRAIDWOOD
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| -UNITS 1 & 2 5.5 -18 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Technical Specifications (TS) Bases Control ProQram This program provides a means for processing changes to the Bases of these Technical Specifications.
| |
| : a. Changes to the Bases of the TS shaltl be made under appropriate administrative controls and reviews.b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
| |
| : 1. a change in the TS incorporated in the license; or 2. a change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.d. Proposed changes that meet the criteria of Specification 5.5.14.b above shall be reviewed and approved by the NRC prior to implementation.
| |
| Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e) as modified by approved exemptions.
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| BRAIDWOOD
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| -UNITS 1 & 2 5.5 -19 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP)This program ensures loss of safety function is detected and appropriate actions taken, Upon entry, into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exi~sts.Additionally, other appropriate actions may 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. The SFDP shall contain the following:
| |
| : a. Provisions for cross train 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 system's Completion Time is not inappropriately extended as a result of multiple support system i noperabil i ties; and d. Other appropriate limitations and remedial or compensatory actions.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 the system(s) supported by the inoperable support system is also inoperable; or b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.
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| BRAIDWOOD
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| -UNITS 1 & 2-5.5 -20 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 5.5.16 Safety Function Determination Program (SFDP) (continued)
| |
| 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 LCD in which the loss of safety function exists are required to be entered. Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option 8, as modified by approved exemptions.
| |
| This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, September 1995 and NEI 94-01, Revision 0, as modified by the following exceptions:
| |
| : 1. NEI 94-01 -1995, Section 9.2.3: The first Unit 1 Type A test performed after the October 5, 1998 Type A test sr1a ll be performed no later than October 5, 2013. 2. NEI 94-01 -1995, Section 9.2.3: In support of the Spring 2014 refueling outage, Unit 2 shall be placed in a MODE of operation where containment is not required to be OPERABLE in accordance with Technical Specification 3.6.1, "Containment," no later than May 4, 2014. The first Unit 2 Type A test performed after the May 4, 1999 Type A test shall be performed prior to entering MODE 4 at the start of Unit 2, Cycle 18. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 42.8 psig for Unit 1 and 38.4 psig for Unit 2 The maximum allowable containment leakage rate, L 3 , at P 0 , shall be 0.20% of containment air weight per day. Leakage Rate acceptance criteria are: a. Containment leakage rate acceptance criterion 1.0 During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type 8 and C tests and< 0.75 La for Type A tests; and BRAIDWOOD
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| -UNITS 1 & 2 5.5-21 Amendment 175 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program (continued)
| |
| : b. Air lock testing acceptance criteria are: I. Overall air lock leakage rate is 0.05 La when tested at Pa; and 2. For each door, seal leakage rate is: i. < 0.0024 L, when pressurized to 3psig, and ii. < 0.01 La, when pressurized to 1 10 psig.The provisions of SR 3.0.2 do not apply-to the test frequencies specified in the Containment Leakage Rate Testing Program.The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.5.5.17 Battery Monitoring and Maintenance Program This program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries For Stationary-Applications," or of the battery manufacturer of the following:
| |
| : a. Actions to restore battery cells with float voltage< 2.13 V, and b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.5.5.18 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Ventilation (VC) Filtration System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge.
| |
| The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.
| |
| The program shall include the following elements: BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -22 Amendment iso Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Envelope Habitability Program (continued)
| |
| : a. The definition of the CRE and CRE boundary.b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
| |
| : c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with. the testing methods and at the Frequencies specified in'Sections C.1 and C.2 of Regulatory Gbide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.d. Measurement of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the VC Filtration System, operating at the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.e., The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph
| |
| : c. The unfilitered air inleakage limit for radiological challenges is the inleakage flow rate assumend in the licensing basis analyses of DBA consequences.
| |
| Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
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| BRAIDWOOD
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| -UNITS 1 & 2 5.5 -23 Amendment 150 Programs Manuals 5.5 5.5 Programs and Manuals Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies.
| |
| The program shall ensure that Survei 11 ance Requi rements specifi ed in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met. a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program. b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI "Risk-Informed Method for Control of Surveillance Frequenci es," Revi si on 1. c. The Provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program. BRAIDWOOD
| |
| -UNITS 1 &2 5.5 -Amendment Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.5.6.1 (Deleted)
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| I BRAIDWOOD
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| -UNITS 1 & 2 5.6 -1 Amendment 136 Reporting Requirements 5.6 5.6 Reporting Requirements
| |
| | |
| ====5.6.2 Annual====
| |
| Radiological Environmental Operating Report-------------------------------
| |
| NOTE-------------------------------
| |
| A single submittal may be made for the facility.
| |
| The submittal should combine sections common to both units.The Annual Radiological Environmental Operating Report covering the operation of the facility 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.5.6.3 Radioactive Effluent Release Report-------------------
| |
| NOTE-------------------------------
| |
| A single submittal may be made for the facility.
| |
| The submittal shall combine sections connon to both units.The Radioactive Effluent Release Report covering the operation of the facility 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 facility.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 Part 50, Appendix I, Section IV.B.1.5.6.4 (Deleted)BRAIDWOOD
| |
| -UNITS I & 2 5.6 -2 Amendment 136 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 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:
| |
| SL 2.1.1. "Reactor Core SLs": LCO 3.1.1. "SHUTDOWN MARGIN (SDM)": LCO 3.1.3. "Moderator Temperature Coefficient":
| |
| LCO 3.1.5. "Shutdown Bank Insertion Limits": LCO 3.1.6. "Control Bank Insertion Limits";LCO 3.1.8. "PHYSICS TESTS Exceptions
| |
| -MODE 2";LCO 3.2.1. "Heat Flux Hot Channel Factor (Fo(Z))";LCO 3.2.2. "Nuclear Enthalpy Rise Hot Channel Factor (F1H)";LCO 3.2.3. "AXIAL FLUX DIFFERENCE (AFD)";LCO 3.2.5. "Departure from Nucleate Boiling Ratio (DNBR)";LCO 3.4.1. "RCS Pressure, Temperature.
| |
| and Flow Departure from Nucleate Boiling (DNB) Limits"; and LCO 3.9.1. "Boron Concentration":
| |
| I b. The analytical methods used to determine the core operating limits shall be those previously reviewed and a pproved by the NRC. specifically those described in the following documents:
| |
| : 1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluations Methodology," July 1985.2. WCAP-12472-P-A. "BEACON Core Monitoring and Operations Support System," August 1994.3. NFSR-0016. "Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods." July 1983.4. NFSR-0081, "Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods Using the Phoenix-P and ANC Computer Codes." July 1990.BRAIDWOOD
| |
| -UNITS 1 & 2 5.6- 3 Amedgept 15
| |
| | |
| ===5.6 Reporting===
| |
| | |
| Requirements Reporting Requirements 5.6 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
| |
| : 5. CornEd letter from D. Saccomando to the Office of Nuclear Reactor Regulation dated December 21, 1994, transmitting an attachment that documents applicable sections of WCAP-11992/11993 and CornEd application of the UET methodology addressed in "Additional Information Regarding Application for Amendment to Facility Operating Licenses-Reactivity Control Systems." 6. WCAP-16009-P-A, Revision 0, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005. 7. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," August 1985. 8. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using NOTRUMP Code," August 1985. 9. WCAP-10216-P-A, Revision 1, "Relaxation of Constant Axial Offset Control -F 0 Surveillance Technical Specification," February 1994. 10. WCAP-8745-P-A, "Design Bases for the Thermal Overpower
| |
| ,1T and Thermal Overtemperature
| |
| ,1T Trip Functions," September 1986. 11. WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Hydraulic Safety Analysis," October 1999; 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; and d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC. BRAIDWOOD
| |
| -UNITS 1 & 2 5.6-4 Amendment No. 174 Reporti ng Requirements 5.6 5.6 Reporting Requirements
| |
| | |
| ====5.6.6 Reactor====
| |
| Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates, and Power Operated Relief Valve (PORV) lift settings shall be established and documented in the PTLR for the following:
| |
| LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits," and LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)System";b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the fol lowing documents:
| |
| : 1. NRC letter dated January 21, 1998, "Byron Station Units 1 and 2, and Braidwood Station, Units 1 and 2, Acceptance for Referencing of Pressure Temperature Limits Report," 2. NRC letter dated August 8, 2001, "Issuance of Exemption from the requirements of 10 CFR 50.60 and Appendix G for Byron Station, Units 1 and 2 and Braidwood Station, Units 1 and 2," 3. Westinghouse WCAP-16143, "Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2," and 4. The PTLR will contain the complete identification for each of the TS referenced Topical Reports used to prepare the PTLR (i.e., report number, title, revision, date, and any supplements);
| |
| and c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.5.6.7 Post Accident Monitoring Report When a report is required by Condition C or G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.BRAIDWOOD
| |
| -UNITS 1 & 2 5.6-5S Amendment 142 Reporting Requirements 5.6 5.6 Reporting Requirements Tendon Surveillance Report Any abnormal degradation of the containment structure detected during tests required by the Pre Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Summary Report in accordance with 10 CFR 50.55a and ASME Section XI. Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE following completion of an inspection performed in accordance with Specification 5.5.9, Steam Generator (SG) Program.The report shall include: The scope of inspections performed on each SG, Degradation mechanisms found, Nondestructive examination techniques utilized for each mechanism, d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, Number of tubes plugged during the inspection outage for each degradation mechanism, I The number and percentage of tubes plugged to date, and the I effective plugging percentage in each steam generator, The results of condition monitoring, including the results of tube and in-situ testing, BRAIDWOOD
| |
| -UNITS 1 &2 5.6 -Amendment 172/172 Reporting Requirements 5.6 5.6 Reporting Requirements
| |
| | |
| ====5.6.9 Steam====
| |
| Generator (SG) Tube Inspection Report (continued)
| |
| : h. For Unit 2, the operational primary to secondary leakage ratel observed (greater than three gallons per day) in each steam generator (if it is not practical to assign the leakage to an individual steam generator, the entire primary to secondary leakage should be conservatively assumed to be from one steam generator) during the cycle preceding the inspection which is the subject of the report, i. For Unit 2, the calculated accident induced leakage rate from I the portion of the tubes below 14.01 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 3.11 times the max"imum operational primary to secondary leakage rate, the report should describe how it was determined, and j. For Unit 2, the results of monitoring for tube axial displacement (slippage).
| |
| If slippage is discovered, the implications of the discovery and corrective action shall be provided.
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 5.6 -7 Amendment 172/172 High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area This Specification provides alternate methods for controlling access to high radiation areas and does not apply to very high radiation areas as defined in 10 CFR 20.5.7.1 Pursuant to 10 CFR 20. paragraph 20.1601(c).
| |
| in lieu of the requirements of 10 CFR 20.1601. each high radiation area, as defined in 10 CFR 20. in which the intensity of radiation is> 100 mnrem/hr but 5 1000 mrem/hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP) or equivalent document that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
| |
| Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 5 1000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
| |
| : a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received..
| |
| Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.BRAIDWOOD
| |
| -UNITS 1 & 2 5.7 -.1 Amendment 98 High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 (continued)
| |
| : c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device. who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the RWP or equivalent document.5.7.2 In addition to the requirements of Specification
| |
| | |
| ====5.7.1. areas====
| |
| accessible to personnel with radiation levels > 1000 mrem/hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates shall require the following:
| |
| : a. Doors shall be locked to prevent unauthorized entry and shall not prevent individuals from leaving the area. In place of locking the door, direct or continuous electronic surveillance that is capable of preventing unauthorized entry may be used. The keys shall be maintained under the administrative control of the Shift Manager on duty or health physics supervision:
| |
| : b. Personnel access and exposure control requirements of activities being performed within these areas shall be specified by an approved RWP or equivalent document that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures;c. Each person entering the area shall be provided with an alarming radiation monitoring device that continuously integrates the radiation dose rate (such as an electronic dosimeter).
| |
| Surveillance and radiation monitoring by health physics personnel may be substituted for an alarming dosimeter:
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 5.7 -2 Amendment 98 High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 (continued)
| |
| : d. For individual high radiation areas accessible to personnel with radiation levels of > 1000 mrem/hr at 30 cm (12 inches)that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device: and e. Except for individuals qualified in radiation protection procedures, or personnel escorted by such individuals, entry into such areas shall be made after dose rates in the area have been determined and entry personnel are knowledgeable of them. Individuals escorted will receive a pre-job briefing prior to entry into such areas.BRAIDWOOD
| |
| -UNITS 1 & 2 5.7 -3 Amendment 98 APPENDIX B TO FACILITY OPERATING LICENSE NOS. NPF-72 & NPF-77 I EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION UNITS 1 & 2 DOCKET NOS. 50-456 AND 50-457 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)
| |
| I Amendment 138 BRAIDWOOD STATION UNITS 1 and 2 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)
| |
| TABLE OF CONTENTS Section 1.0 2.0 2.1 2.2 3.0 3.1 3.2 3.3 4.0 4.1 5.0 5.1 5.2 5.3 5.4 Objectives of the Environmental Protection Plan Environmental Protection Issues Aquatic Issues Terrestrial Issues ...Consistency Requirements.
| |
| .Plant Design and Operation Reporting Related to the NPDES Permits and State Certification
| |
| ....Changes Required for Compliance with Other Environmental Regulations
| |
| .Environmental Conditions Unusual or Important Environmental Events Administrative Procedures
| |
| .Review and Audit Records Retention
| |
| .Changes in Environmental Protection Plan.Plant Reporting Requirements Page 1-1 2-1 2-1 2-1 3-1 3-1 3-2 3-2 4-1 4-1 5-1 5-1 5-1 5-1 5-2 Amendment 138
| |
| | |
| ===2.0 Environmental===
| |
| | |
| Protection Issues In the FES-OL dated June, 1984, the staff considered the environmental impacts associated with the operation of the two unit Braidwood Station. No environmental issues were identified which required study or license conditions to resolve environmental concerns and to assure adequate protection of the environment.
| |
| | |
| ===2.1 Aquatic===
| |
| Issues No specific aquatic issues were raised by the staff in the FES-OL.Aquatic matters are addressed by the effluent limitations, monitoring requirements and the Section 316(b) demonstration requirement contained in the effective NPDES permit issued by the Federal or State permitting authority.
| |
| The NRC will rely on these agencies for regulation of matters involving water quality and aquatic biota.2.2 Terrestrial Issues No specific terrestrial issues were raised by the staff in the FES-OL.2-1 Amendment 138
| |
| | |
| A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns:
| |
| (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level or (3) a matter, not previously reviewed and evaluated in the documents specified in (1) of this Subsection, which may have a significant adverse environmental impact.The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection.
| |
| These records shall include written evaluations which provide bases for the determination that the change, test or experiment does not involve an unreviewed environmental question or constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0.3.2 Reporting Related to the NPDES Permit and State Certification The NRC shall be provided with a copy of the current NPDES permit or State Certification within 30 days of approval.
| |
| Changes to the NPDES permit or State Certification shall be reported to the NRC within 30 days of the date the change is approved.3.3 Changes Required for Compliance with Other Environmental Regulations Changes in plant design or operation and performance of tests or experiments which are either regulated or mandated by other Federal, State, and local environmental regulations are not subject to the requirements of Section 3.1. However, if any environmental impacts of a change are not evaluated under other Federal, State or local environmental regulations, then those impacts are subject to the requirements of Section 3.1.3-2 Amendment 138
| |
| | |
| ===4.0 Environmental===
| |
| | |
| Conditions
| |
| | |
| ===4.1 Unusual===
| |
| or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to plant operation shall be recorded and reported to the NRC within 24 hours followed by a written report in accordance with Subsection 5.4.2. If an event is reportable under 10 CFR 50.72, then a duplicate immediate report under this-subsection is not required.
| |
| However, a follow-up written report is required in accordance with Subsection 5.4.2. The following are examples:
| |
| excessive bird impaction events, onsite plant or animal disease outbreaks, mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973, fish kills, increase in nuisance organisms or conditions, and unanticipated or emergency discharge of waste water or chemical substances.
| |
| No routine monitoring programs are required to implement this condition.
| |
| 4-1 Amendment 138
| |
| | |
| ===5.0 Administrative===
| |
| | |
| Procedures
| |
| | |
| ===5.1 Review===
| |
| and Audit The licensee shall provide for review and audit of compliance with the EPP. The audits shall be conducted independently of the individual or groups responsible for performing the specific activity.
| |
| A description of the organization structure utilized to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.
| |
| | |
| ===5.2 Records===
| |
| Retention Records associated with this EPP shall be made and retained in a manner convenient for review and inspection.
| |
| These records shall be made available to NRC on request.Records of modifications to station structures, systems and components determined to potentially affect the continued protection of the environment shall be retained until the date of termination of the operating license. All other records relating to this EPP shall be retained for five years or, where applicable, in accordance with the requirements of other agencies.5.3 Changes in Environmental Protection Plan Requests for changes in the EPP shall include an assessment of the environmental impact of the proposed change and a supporting justification.
| |
| Implementation of such changes in the EPP shall not commence prior to NRC approval of the proposed changes in the form of a license amendment incorporating the appropriate revision to the EPP.5-1 Amendment 138
| |
| | |
| ===5.4 Plant===
| |
| Reporting Requirements
| |
| | |
| ====5.4.1 Deleted====
| |
| 5.4.2 Nonroutine Reports A written report shall be submitted to the NRC within 30 days of an occurrence of an unusual or important environmental event. The report shall (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact, and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (e) indicate the agencies notified and their preliminary responses.
| |
| Events reportable under this subsection which also require reports to other Federal, State or local agencies shall be reported in accordance with those reporting requirements in lieu of the requirements of this subsection.
| |
| The NRC shall be provided a copy of such report at the same time it is submitted to the other agency.5-2 Amendment 138 145 ADDITIONAL FACILITY OPERATING LICENSE NO. The licensee shall comply with the following conditions on the schedules noted below: Amendment Number Additional Condition The safety limit equation specified in TS 2.1.1.3 regarding fuel centerline melt temperature (Le., less than 5080 of, decreasing by 58 of per 10,000 MWD/MTU burnup as described in WCAP-12610-P-A, "VANTAGE+
| |
| Fuel Assembly Reference Core Report," April 1995) is valid for uranium oxide fuel without the presence of poisons mixed homogeneously into the fuel pellets. If fuel pellets incorporating homogeneous poisons are used, the topical report documenting the fuel centerline melt temperature basis must be reviewed and approved by the NRC and referenced in this license condition.
| |
| TS 2.1.1.3 must be modified to also include the fuel centerline melt temperature limit for the fuel with homogeneous poison. During operation in Cycles 15, 16, and 17, up to eight (8) AREVA NP Advanced BW(A) fuel assemblies containing fuel pellets incorporating homogeneous poisons may be placed in non limiting Unit 1 core locations provided the fuel cycle designs are developed such that the TS 2.1.1.3 Safety Limit equation for Westinghouse fuel is bounding.
| |
| The design basis for the AREVA NP fuel rod centerline melt follows that given in BAW-10162P-A, "TAC03 -Fuel Pin Thermal Analysis Computer Code," October 1989, and BAW-10184P-A, "GDTACO -Urania Gadolinia Fuel Pin Thermal Analysis Code," February 1995. With mentation of the ment AMENDMENT NO. 160 ADDITIONAL FACILITY OPERATING LICENSE NO. The licensee shall comply with the following conditions 011 Ihe schedules floled Amendment Number Additional Condition Implementation Date 146 Upon implementation of Amendment No. 146 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by With menlallon of lhe amendment SR accordance with TS 5.5.18.c.(I), the assessment of CRE habitability as required by Specification 5.5.18.c.(ii), and.the measurement of eRE pressure as required by Speclflcatlon 5.5.18.d, shaH be considered met. Following Implementation: (a) The first performance of SR 3.7.10.4, in accordance with SpecifICation 5.5.18.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month anowance of SR 3.0.2, as measured from November 7.2004, the date of the most recent successful tracer gas test, as stated in the February 7,2005 letter response to Generic letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test Is greater than 6 years. (b) The r"sf performance of the periodic assessment of eRE habitability, Specification 5.5.18.c.(ii).
| |
| shall be within 3 years, pIus the month allowance 01 SR 3.0.2, as measured from November 7,2004, the date of the most recent successful tracer gas test. as staled In the February 7,2005 reUer response to Generic letter 2003-01, or within the next 9 months if the time period since' the most recent successful tracer gas test is greater than 3 years. (c) The first performance of the periodic measurement of eRE pressure, Specfficatlon 5.5.18.d, shall be INilhin 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recen" successful pressure measurement test, or within 138 days if not performed previously.
| |
| AMENDMENT NO. 160 BRAIDWOOD
| |
| - UNITS 1 & 2 i Amendment 110
| |
| | |
| TABLE OF CONTENTS
| |
| - TECHNICAL SPECIFICATIONS
| |
| | |
| 1.0 USE AND APPLICATION
| |
| | |
| ===1.1 Definitions===
| |
| ..........................................1.1-1 1.2 Logical Connectors
| |
| ...................................1.2-1 1.3 Completion Times
| |
| .....................................1.3-1 1.4 Frequency ............................................1.4-1
| |
| | |
| ===2.0 SAFETY===
| |
| LIMITS (SLs) 2.1 SLs .................................................2.0-1 2.2 SL Violations
| |
| ........................................2.0-1
| |
| | |
| ===3.0 LIMITING===
| |
| CONDITION FOR OPERATION (LCO) AND SURVEILLANCE REQUIREMENT (SR) APPLICABILITY
| |
| .......................3.0-1
| |
| | |
| ===3.1 REACTIVITY===
| |
| CONTROL SYSTEMS
| |
| | |
| ====3.1.1 SHUTDOWN====
| |
| MARGIN (SDM)
| |
| ................................3.1.1-1 3.1.2 Core Reactivity
| |
| ......................................3.1.2-1 3.1.3 Moderator Temperature Coefficient (MTC)
| |
| ..............3.1.3-1 3.1.4 Rod Group Alignment Limits
| |
| ...........................3.1.4-1 3.1.5 Shutdown Bank Insertion Limits
| |
| .......................3.1.5-1 3.1.6 Control Bank Insertion Limits
| |
| ........................3.1.6-1 3.1.7 Rod Position Indication
| |
| ..............................3.1.7-1 3.1.8 PHYSICS TESTS Exceptions
| |
| -MODE 2 ......................3.1.8-1
| |
| | |
| ===3.2 POWER===
| |
| DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (F Q(Z)) .................3.2.1-1 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor
| |
| )F (N H ........3.2.2-1 3.2.3 AXIAL FLUX DIFFERENCE (AFD)
| |
| .........................3.2.3-1 3.2.4 QUADRANT POWER TILT RATIO (QPTR)
| |
| .....................3.2.4-1 3.2.5 Departure from Nucleate Boiling Ratio (DNBR)
| |
| .........3.2.5-1
| |
| | |
| ===3.3 INSTRUMENTATION===
| |
| | |
| ====3.3.1 Reactor====
| |
| Trip System (RTS) Instrumentation
| |
| ............3.3.1-1 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation
| |
| ..........................3.3.2-1 3.3.3 Post Accident Monitoring (PAM) Instrumentation
| |
| .......3.3.3-1 3.3.4 Remote Shutdown System ...............................3.3.4-1 3.3.5 Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation
| |
| ..................................3.3.5-1 3.3.6 Containment Ventilation Isolation Instrumentation
| |
| ....3.3.6-1 3.3.7 Control Room Ventilation (VC) Filtration System Actuation Instrumentation
| |
| ........................3.3.7-1 3.3.8 Fuel Handling Building Exhaust Filter Plenum (FHB)
| |
| Ventilation System Actuation Instrumentation
| |
| ....3.3.8-1 3.3.9 Boron Dilution Protection System (BDPS)
| |
| ..............3.3.9-1 TABLE OF CONTENTS -TECHNICAL SPECIFICATIONS
| |
| | |
| ===3.4 REACTOR===
| |
| COOLANT SYSTEM (RCS)3.4.1 RCS Pressure, Temperature, and Flow Departure.from Nucleate Boiling (DNB) Limits ...............
| |
| 3.4.1-1 3.4.2 RCS Minimum Temperature for Criticality
| |
| ..............
| |
| 3.4.2-1 3.4.3 RCS Pressure and Temperature (P/T) Limits ............
| |
| 3.4.3-1 3.4.4 RCS Loops-MODES 1 and 2 ..............................
| |
| 3.4.4-1 3.4.5 RCS Loops-MODE 3... ... ............................
| |
| 3.4.5-1 3.4.6 RCS Loops-MODE 4 ..............
| |
| ........................
| |
| 3.4.6-1 3.4.7 RCS Loops-MODE 5, Loops Filled .......................
| |
| 3.4.7-1 3.4.8 RCS Loops-MODE 5, Loops Not Filled ...................
| |
| 3.4.8-1 3.4.9 Pressurizer
| |
| ..............................
| |
| 3.4.9-1 3.4.10 Pressurizer Safety Valves ............................
| |
| 3.4.10-1 3.4.11 Pressurizer Power Operated Relief Valves (PORVs) ..... 3.4.11-1 3.4.12 Low Temperature Overpressure Protection (LTOP)System ..............
| |
| 3.4.12-1 3.4.13 RCS Operational LEAKAGE ..............................
| |
| 3.4.13-1 3.4.14 RCS Pressure Isolation Valve (PIV) Leakage ...........
| |
| 3.4.14-1 3.4.15 RCS Leakage Detection Instrumentation
| |
| ...............
| |
| 3.4.15-1 3.4.16 RCS Specific Activity ........ ................
| |
| 3.4.16-1 3.4.17 RCS Loop Isolation Valves ............................
| |
| 3.4.17-1 3.4.18 RCS Loops-Isolated
| |
| ...................
| |
| ...........
| |
| 3.4.18-1 3.4.19 Steam Generator (SG) Tube Integrity
| |
| .................
| |
| 3.4.19-1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.1 Accumulators
| |
| .........................................
| |
| 3.5.1-1 3.5.2 ECCS-Operating
| |
| .......................................
| |
| 3.5.2-1 3.5.3 ECCS-Shutdown
| |
| .................
| |
| .3.5.3-1 3.5.4 Refueling Water Storage Tank (RWST).............
| |
| 3.5.5 Seal Injection Flow ..................................
| |
| 3.5.5-1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment
| |
| ..........................................
| |
| 3.6.1-1 3.6.2 Containment Air Locks....
| |
| ...... 3.6.2-1 3.6.3 Containment Isolation Valves....
| |
| ........ ....... 3.6.3-1 3.6.4 Containment Pressure .................................
| |
| 3.6.4-1 3.6.5 Containment Air Temperature
| |
| ..........................
| |
| 3.6.5-1 3.6.6 Containment Spray and Cooling Systems ................
| |
| 3.6.6-1 3.6.7 Spray Additive System ................................
| |
| 3.6.7-1 3.6.8 (Deleted)
| |
| ............................................
| |
| 3.6.8-1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs) .....................
| |
| 3.7.1-1 3.7.2 Main Steam Isolation Valves (MSIVs) ..................
| |
| 3.7.2-1 3.7.3 Secondary Specific Activity ..........................
| |
| 3.7.3-1 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs) ..............
| |
| .3.7.4-1 3.7.5 Auxiliary Feedwater (AF) System ......................
| |
| 3.7.5-1 3.7.6 Condensate Storage Tank (CST) ........................
| |
| 3.7.6-1 BRAIDWOOD
| |
| -UNITS 1 & 2 ii Amendment 144 BRAIDWOOD
| |
| - UNITS 1 & 2 iii Amendment 124
| |
| | |
| TABLE OF CONTENTS
| |
| - TECHNICAL SPECIFICATIONS
| |
| | |
| ===3.7 PLANT===
| |
| SYSTEMS (continued)
| |
| | |
| ====3.7.7 Component====
| |
| Cooling Water (CC) System
| |
| ..................3.7.7-1 3.7.8 Essential Service Water (SX) System
| |
| ..................3.7.8-1 3.7.9 Ultimate Heat Sink (UHS)
| |
| .............................3.7.9-1 3.7.10 Control Room Ventilation (VC) Filtration System
| |
| ......3.7.10-1 3.7.11 Control Room Ventilation (VC) Temperature Control System
| |
| ...................................3.7.11-1 3.7.12 Nonaccessible Area Exhaust Filter Plenum Ventilation System
| |
| ...............................3.7.12-1 3.7.13 Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System
| |
| .........................3.7.13-1 3.7.14 Spent Fuel Pool Water Level
| |
| ..........................3.7.14-1 3.7.15 Spent Fuel Pool Boron Concentration
| |
| ..................3.7.15-1 3.7.16 Spent Fuel Assembly Storage
| |
| ..........................3.7.16-1
| |
| | |
| ===3.8 ELECTRICAL===
| |
| POWER SYSTEMS 3.8.1 AC Sources
| |
| -Operating ................................
| |
| .3.8.1-1 3.8.2 AC Sources
| |
| -Shutdown ..................................3.8.2-1 3.8.3 Diesel Fuel Oil
| |
| ......................................3.8.3-1 3.8.4 DC Sources
| |
| -Operating ................................
| |
| .3.8.4-1 3.8.5 DC Sources
| |
| -Shutdown ..................................3.8.5-1 3.8.6 Battery Cell Parameters
| |
| ..............................3.8.6-1 3.8.7 Inverters-Operating ..................................3.8.7-1 3.8.8 Inverters-Shutdown ...................................3.8.8-1 3.8.9 Distribution Systems
| |
| -Operating .......................3.8.9-1 3.8.10 Distribution Systems
| |
| -Shutdown ........................3.8.10-1
| |
| | |
| ===3.9 REFUELING===
| |
| OPERATIONS
| |
| | |
| ====3.9.1 Boron====
| |
| Concentration
| |
| ..................................3.9.1-1 3.9.2 Unborated Water Source Isolation Valves
| |
| ..............3.9.2-1 3.9.3 Nuclear Instrumentation
| |
| ..............................3.9.3-1 3.9.4 Containment Penetrations .............................3.9.4-1 3.9.5 Residual Heat Removal (RHR) and Coolant Circulation
| |
| -High Water Level
| |
| .....................3.9.5-1 3.9.6 Residual Heat Removal (RHR) and Coolant Circulation
| |
| -Low Water Level
| |
| ......................3.9.6-1 3.9.7 Refueling Cavity Water Level
| |
| .........................3.9.7-1
| |
| | |
| ===4.0 DESIGN===
| |
| FEATURES 4.1 Site .................................................4.0-1 4.2 Reactor Core
| |
| .........................................4.0-1 4.3 Fuel Storage
| |
| .........................................4.0-2 BRAIDWOOD
| |
| - UNITS 1 & 2 iv Amendment 110
| |
| | |
| TABLE OF CONTENTS
| |
| - TECHNICAL SPECIFICATIONS
| |
| | |
| ===5.0 ADMINISTRATIVE===
| |
| CONTROLS
| |
| | |
| ===5.1 Responsibility===
| |
| .......................................5.1-1 5.2 Organization
| |
| .........................................5.2-1 5.3 Facility Staff Qualifications
| |
| ........................5.3-1 5.4 Procedures
| |
| ...........................................5.4-1 5.5 Programs and Manuals
| |
| ................................
| |
| .5.5-1 5.6 Reporting Requirements
| |
| ...............................5.6-1 5.7 High Radiation Area
| |
| ..................................5.7-1 Definitions 1.1 1.0 USE AND APPLICATION
| |
| | |
| ===1.1 Definitions===
| |
| The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.Term ACTIONS ACTUATION LOGIC TEST AXIAL FLUX DIFFERENCE (AFD)CHANNEL CALIBRATION Definition ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.An ACTUATION LOGIC TEST shall be the application of various simulated or actual input combinations in conjunction with each possible interlock logic state and the verification of the required logic output. The ACTUATION LOGIC TEST, as a minimum.shall include a continuity check of output devices.AFD shall be the difference in normalized flux signals between the top and bottom halves of a two section excore neutron detector.A CHANNEL CALIBRATION shall be the adjustment.
| |
| as necessary, of the channel so that it responds within the required range and accuracy to known inputs. The CHANNEL CALIBRATION shall encompass the entire channel. including the required sensor.alarm. -interlock.
| |
| display. and trip functions.
| |
| 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 calibrations or total channel steps so that the entire channel is calibrated.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 1.1-1 Amendment 98 Definitions 1.1 1.1 Definitions CHANNEL CHECK CHANNEL OPERATIONAL TEST (COT)CORE ALTERATION CORE OPERATING LIMITS REPORT (COLR)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.
| |
| A COT shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify the OPERABILITY of required alarm, interlock, display, and trip functions.
| |
| The COT shall include adjustments, as necessary, of the required alarm, interlock.
| |
| and trip setpoints so that the setpoints are within the required range and accuracy.CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel. Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle. These cycle specific parameter limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Unit operation within these limits is addressed in individual Specifications.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 1.1 -2 Amendment 98 Definitions 1.1 1.1 Definitions DOSE EQUIVALENT 1-131 DOSE EQUIVALENT XE-133 ENGINEERED SAFETY FEATURE (ESF) RESPONSE TIME DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries per gram) that alone would produce the same dose when inhaled as the combined activities of iodine isotopes 1-131, 1-132, 1-133, 1-134, and 1-135 actually present. The determination of DOSE EQUIVALENT 1-131 shall be performed using the Committed Effective Dose Equivalent (CEDE) dose conversion factors from Table 2.1 of EPA Federal Guidance Report No. II, 1988, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion." DOSE EQUIVALENT XE-133 shall be that concentration of Xe-133 (microcuries per gram) that alone would produce the same acute dose to the whole body as the combined activities of noble gas nuclides Kr-85m, Kr-85, Kr-87, Kr-88, Xe-131m, Xe-133m, Xe-133, Xe-135m, Xe-135, and Xe-138 actually present. If a specific noble gas nuclide is not detected, it should be assumed to be present at the minimum detectable activity.
| |
| The determination of DOSE EQUIVALENT XE-133 shall be performed using effective dose conversion factors for air submersion listed in Table 111.1 of EPA Federal Guidance Report No. 12, 1993, "External Exposure to Radionuclides in Air, Water, and Soi 1. " The ESF RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF 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.
| |
| In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. BRAIDWOOD
| |
| -UNITS 1 &2 1.1-3 Amendment 162 Definitions
| |
| * " 1.1 1.1 Definitions LEAKAGE LEAKAGE shall be: a. Identified LEAKAGE 1. LEAKAGE, such as that from pump seals or valve packing (except Reactor Coolant pump (RCP) seal water injection or leakoff), that is captured and conducted to collection systems or a sump or collecting tank;2. LEAKAGE into the containment 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; or 3. Reactor Coolant System (RCS) LEAKAGE through a steam generator to the Secondary System (primary to secondary LEAKAGE);b. Unidentified LEAKAGE All LEAKAGE (except RCP seal water injection or leakoff) that is not identified LEAKAGE;c. Pressure Boundary LEAKAGE LEAKAGE (except primary to secondary LEAKAGE)through a nonisolable fault in an RCS component body, pipe wall, or vessel wall.MASTER RELAY TEST A MASTER RELAY TEST shall consist of energizing each master relay and verifying the OPERABILITY of each relay. The MASTER RELAY TEST shall include a continuity check of each associated slave relay.BRAIDWOOD
| |
| -UNITS 1 & 2 1.1- 4 Amendment 144 Definitions
| |
| : 1. 1 1.1 Definitions MODE A MODE shall correspond to any one inclusive combination of core reactivity condition, power level, average reactor coolant temperature.
| |
| and reactor vessel head closure bolt tensioning specified in Table 1.1-1 with fuel in the reactor vessel.OPERABLE -OPERABILITY PHYSICS TESTS A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, train.component, or device to perform its specified safety function(s) are a so capable of performing their related support function(s).
| |
| 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 UFSAR: b. Authorized under the provisions of'10 CFR 50.59: or c. Otherwise approved by the Nuclear Commission.
| |
| Regulatory BRAIDWOOD
| |
| -UNITS 1 & 2 1.1 -5 Amendment 98
| |
| | |
| ===1.1 Definitions===
| |
| | |
| PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) QUADRANT POWER TILT RATIO (QPTR) RATED THERMAL POWER CRTP) REACTOR TRIP SYSTEM CRTS) RESPONSE TIME RECENTLY IRRADIATED FUEL BRAIDWOOD
| |
| -UNITS 1 & 2 Definitions 1.1 The PTLR is the unit specific document that provides the reactor vessel pressure and temperature limits including heatup and cooldown rates, and the pressurizer Power Operated Relief Valve (PORV) lift settings for the current reactor vessel fluence period. These pressure and temperature limits shall be determined for each fluence period in accordance with Specification 5.6.6. QPTR shall be the ratio of the maximum upper excore detector calibrated output to the average of the upper excore detector calibrated outputs, or the ratio of the maximum lower excore detector calibrated output to the average of the lower excore detector calibrated outputs, whichever is greater. RTP shall be a total reactor core heat transfer rate to the reactor coolant of 3645 MWt. The RTS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RTS trip setpoint at the channel sensor until loss of stationary gripper coil voltage. 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.
| |
| In lieu of measurement, response time may be verified for selected components provided that the components and methodology for verification have been previously reviewed and approved by the NRC. Fuel that has occupied part of a critical reactor core within the previous 48 hours. Note that all fuel that has been in a critical reactor core is referred to as irradiated fuel. 1.1-6 Amendment No. 174 Definitions 1.1 1.1 Definitions SHUTDOWN MARGIN (SDM)SDM shall be-the instantaneous amount of reactivity by which the reactor is subcritical or would be subcritical from its present condition assuming: a. All Rod Cluster Control Assemblies (RCCAs) are fully inserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn.
| |
| With any RCCA not capable of being fully inserted, the reactivity worth of the RCCA must be accounted for in the determination of SDM: and b. In MODES 1 and 2. the fuel and moderator temperatures are changed to the hot zero power temperature.
| |
| SLAVE RELAY TEST STAGGERED TEST BASIS THERMAL POWER A SLAVE RELAY TEST shall consist of energizing each slave relay and verifying the OPERABILITY of each slave relay. The SLAVE-RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.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 shall be the-total reactor core heat transfer rate to the reactor coolant.BRAIDWOOD
| |
| -UNITS 1 & 2 1.1 -7 Amendment 98 Definitions 1.1 1.1 Definitions TRIP ACTUATING DEVICE OPERATIONAL TEST (TADOT)A TADOT shall consist of operating the trip actuating device and verifying the OPERABILITY of required alarm, interlock, display. and trip functions.
| |
| The TADOT shall include adjustment, as necessary.
| |
| of the trip actuating device so that it actuates at the required setpoint within the required accuracy.BRAIDWOOD
| |
| -UNITS 1 & 2 1.1 -8 Amendment 98 MODE TITLE 1 Power Operation 2 Startup 3 Hot Standby 4 Hot Shutdown(b) 5 Co 1 d Shutdown(b) 6 Refue 1 i ngrcJ (a) Exe 1 udi ng decay heat. Table 1.1-1 (page 1 of 1) MODES % RATED REACTIVITY THERMAL CONDITION POWER( a) ( ko++) 2 0.99 > 5 2 0.99 5 < 0.99 NA < 0.99 NA < 0.99 NA NA NA Definitions
| |
| | |
| ===1.1 AVERAGE===
| |
| REACTOR COOLANT TEMPERATURE (oF) NA NA 2 350 350 > TilVO > 200 200 NA (b) All required reactor vessel head closure bolts fully tensioned. (c) One or more required reactor vessel head closure bolts less than fully tensioned.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 1.1 -9 Amendment 186 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 indentations 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 connectors.
| |
| the use of logical BRAIDWOOD
| |
| -UNITS 1 & 2 1.2- 1 Amendment 98 Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)
| |
| EXAMPLE 1.2-1 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.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 1.2 -2 Amendment 98 Logical Connectors 1.2 1.2 Logical Connectors EXAMPLES (continued)
| |
| EXAMPLE 1.2-2 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 theological 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.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 1.2 -3 Amendment 98 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 trains.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.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 1.3- 1 Amendment 98 Completion Times 1.3 1.3 Completion Times DESCRIPTION (continued)
| |
| However, when a subsequent train, 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:
| |
| : 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 hours: or b. The stated Completion Time as measured from discovery of the subsequent inoperability.
| |
| The.above Completion Time extension does not apply to those Specifications that have exceptions that allow completely separate-re-entry into the Condition (for each train.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 hours," 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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -2 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
| |
| EXAMPLE 1.3-1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours met.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 6 hours AND in MODE 5 within 36 hours. A total of 6 hours is allowed for reaching MODE 3 and a total of 36 hours (not 42 hours) is allowed for reaching MODE 5 from the time that Condition B was entered. If MODE 3 is reached within 3 hours. the time allowed for reaching MODE 5 is the next 33 hours because the total time allowed for reaching MODE 5 is 36 hours.If Condition B is entered while for reaching MODE 5 is the next in MODE 3. the time allowed 36 hours.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -3 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-2 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. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 5. 36 hours met.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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -4 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| 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.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 OPERAB[E status was the first inoperable pump. A.24 hour extension to the stated 7 days is allowed. provided this does not result in the second pump being inoperable for> 7 days.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -5 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-3 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Restore 7 days Function X Function X train train to OPERABLE AND inoperable.
| |
| status.10 days from discovery of failure to meet the LCO B. One B.1 Restore 72 hours Function Y Function Y train train to OPERABLE AND inoperable.
| |
| status.10 days from discovery of failure to meet the LCO C. One C.1 Restore 72 hours Function X Function X train train to OPERABLE inoperable.
| |
| status.AND OR One C.2 Restore 72 hours Function Y Function Y train train to OPERABLE inoperable.
| |
| status.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -6 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| When one Function X train and one Function Y train are inoperable.
| |
| Condition A and Condition B are concurrently applicable.
| |
| The Completion Times for Condition A and Condition B are tracked separately for each train starting from the time each train was declared inoperable and the Condition was entered. A separate Completion Time is established for Condition C and tracked from the time the second train 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 train 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 aMlows 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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -7 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve(s) 4 hours valves to OPERABLE inoperable.
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| status.B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours met.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.
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| 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 hours provided this does not result in any subsequent valve being inoperable for > 4 hours.If the Completion Time of 4 hours (plus the extension) expires while one or more valves are still inoperable.
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| Condition B is entered.BRAIDWOOD
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| -UNITS 1 & 2 1.3 -8 Amendment
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| : 98.
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| Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-5 ACTIONS Separate Condition valv.-n-t-y -NOTE --a f entry is allowed for each inoperable CONDITION REQUIRED ACTION COMPLETION TIME A. One or more A.1 Restore valve to 4 hours valves OPERABLE status.inoperable.
| |
| B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2 Be in MODE 4. 12 hours met.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.
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| 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.
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| Condition A is entered for each valve and separate Completion Times start and are tracked for each valve.BRAIDWOOD
| |
| -UNITS 1 & 2 1.3 -9 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
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| 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.EXAMPLE 1.3-6 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Perform Once per inoperable.
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| SR 3.x.x.x. 8 hours OR A.2 Reduce THERMAL 8 hours POWER to< 50% RTP.B. Required B.1 Be in MODE 3. 6 hours Action and associated Completion Time not met.BRAIDWOOD
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| -UNITS 1 & 2 1.3 -10 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
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| 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.
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| The initial 8 hour interval of Required Action A.1 begins when Condition A is entered and the initial performance of Required Action A.1 must be complete within the first 8 hour interval.
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| 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 hours 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.BRAIDWOOD
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| -UNITS 1 & 2 1.3 -11 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| EXAMPLE 1.3-7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One A.1 Verify affected 1 hour subsystem subsystem inoperable.
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| isolated.
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| AND Once per 8 hours thereafter AND A.2 Restore subsystem 72 hours to OPERABLE status.B. Required B.1 Be in MODE 3. 6 hours Action and associated AND Completion Time not B.2. Be in MODE 5. 36 hours met.Required Action A.1 has two Completion Completion Time begins at the time the and each "Once per 8 hours thereafter" performance of Required Action A.1.Times. The 1 hour Condition is entered interval begins upon BRAIDWOOD
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| -UNITS 1 & 2 1.3 -12 Amendment 98 Completion Times 1.3 1.3 Completion Times EXAMPLES (continued)
| |
| If after Condition A is entered, Required Action A.1 is not met within either the initial 1 hour or any subsequent 8 hour 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.IMMEDIATE When "Immediately" is used as a Completion Time, the COMPLETION TIME Required Action should be pursued without delay and in a controlled manner.BRAIDWOOD
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| -UNITS 1 & 2 1.3 -13 Amendment 98 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 Limiting Condition for Operation CLCO). -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.
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| 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.
| |
| Sometimes special situations dictate when the requirements of a.Survei11ance 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 1.4-5 discusses these special situations.
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| BRAIDWOOD
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| -UNITS 1 & 2 1.4 -I1 Amendment 98 Frequency 1.4 1.4 Frequency DESCRIPTION (continued)
| |
| The use of "met" or "performed" in these instances conveys specific meaning. 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.EXAMPLES The following examples illustrate the various ways that Frequencies are specified.
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| In these examples, the Applicability of the LCO (LCO not shown) is MODES 1, 2, and 3. The examples do not reflect the potential application of LCO 3.0.4.b.BRAIDWOOD
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| -UNITS 1 & 2 1.4 -2 Amendment 134 Frequency 1.4 1.4 Frequency EXAMPLES (continued)
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| EXAMPLE 1.4-1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Perform CHANNEL CHECK. 12 hours Example 1.4-1 contains the type of SR most often encountered in the Technical Specifications (TS). The Frequency specifies an interval (12 hours) during which the associated Surveillance must be performed at least one time.Performance of the Surveillance initiates the subsequent interval.
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| Although the Frequency is stated as 12 hours, an extension of the time interval to 1.25 times the stated 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 Example 1.4-3). then SR 3.0.3 becomes applicable.
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| 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.
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| the-Surveillance must be performed within the Frequency requirements of SR 3.0.2 prior to entry into the MODE or other specified condition.
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| Failure to do so would result in a violation of SR 3.0.4.BRAIDWOOD
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| -UNITS 1 & 2 1.4 -3 Amendment 98 Frequency 1.4 1.4 Frequency EXAMPLES (continued)
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| EXAMPLE 1.4-2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify flow is within limits. Once within 12 hours after 2 25% RTP AND 24 hours 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 2 25% RTP. the Surveillance must be performed within 12 hours.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.BRAIDWOOD
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| -UNITS 1 & 2 1.4 -4 Amendment 98
| |
| --.Frequency 1.4 1.4 Frequency EXAMPLES (continued)
| |
| EXAMPLE 1.4-3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY----NOTED Not required to be performed until 12 hours after 2 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 hours after power reaches 2 25% RTP to perform the Surveillance.
| |
| The Surveillance is still considered to be performed within the"specified Frequency." Therefore.
| |
| if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval.
| |
| 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 hours with power a 25% RTP.Once the unit reaches 25% RTP. 12 hours would be allowed for completing the Surveillance.
| |
| If the Surveillance were not performed within this 12 hour 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.BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -5 Amendment 98 Frequency 1.4 1.4 Frequency EXAMPLES (continued)
| |
| EXAMPLE 1.4-4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY-NO4TE----Only required to be performed in MODE 1.Perform complete cycle of the valve. 7 days The interval continues, whether or not the unit operation is in MODE 1. 2, or 3 (the assumed Applicability of the associated LCO) between performances.
| |
| As the Note modifies the required performance of the Surveillance, the note is construed to be part of the"specified Frequency." Should the 7 day interval be exceeded while operation is not in MODE 1. this Note allows entry into and operation in MODES 2 and 3 to perform the Surveillance.
| |
| The Surveillance is still considered to be performed within the "specified Frequency" if completed prior to MODE 1. Therefore.
| |
| if the Surveillance were not performed within the 7 day (plus the extension allowed by SR 3.0.2) interval, but operation was not in MODE 1. 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 result in entry into MODE 1.Once the unit reaches MODE 1. the requirement for the Surveillance to be performed within its specified Frequency applies and would require that the Survei11ance had been performed.
| |
| If the Surveillance were not performed prior to MODE 1. there would then be a failure to perform a Surveillance within the specified Frequency, and the provisions of SR 3.0.3 would apply.BRAIDWOOD
| |
| -UNITS 1 & 2 1.4 -6 Amendment 98 Frequency 1.4 1.4 Frequency EXAMPLES (continued)
| |
| EXAMPLE 1.4-5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY--NOTE--Only required to be met in MODE 1.Verify leakage rates are within limits. 24 hours Example 1.4-5 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 hour interval (plus the extension allowed by SR 3.0.2).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 hour Frequency exceeded, provided the MODE change was not made into MODE 1. Prior to entering MODE 1 (assuming again that the 24 hour Frequency were not met), SR 3.0.4 would require satisfying the SR.BRAIDWOOD
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| -UNITS 1 & 2 1.4 -7 Amendment 98 SLs 2.0 2.0 SAFETY LIMITS CSLs) 2.1 Sls 2.1.1 Reactor Core Sls In MODES 1 and 2, the combination of THERMAL POWER, Reactor Coolant System CRCS) highest loop average temperature, and pressurizer pressure shall not exceed the limits specified in the COLR; and the following Sls shall not be exceeded.
| |
| 2.1.1.1 In MODE 1, the Departure from Nucleate Boiling Ratio CDNBR) shall be 1.24 for the WRB-2 DNB correlation for a thimble cell, 1.25 for the WRB-2 DNB correlation for a typical cell 1.19 for the ABB-NV DNB correlation for a thimble cell and a typical cell. 2.1.1.2 In MODE 2, the DNBR shall be 1.17 for the WRB-2 DNB correlation, 1.13 for the ABB-NV DNB correlation 1.18 for the WLOP DNB correlation.
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| 2.1.1.3 In MODES 1 and 2, the peak fuel centerline temperature shall be maintained as follows: a. < 5080°F decreasing by 58°F per 10,000 MWD/MTU burnup for Westinghouse fuel, b. < 5173°F decreasing by 65°F per 10,000 MWD/MTU burnup for AREVA NP fuel (Unit 1 only), and c. < 5189°F decreasing by 65°F per 10,000 MWD/MTU burnup for AREVA NP fuel containing Gadolinia (Unit 1 only). 2.1.2 RCS Pressure SL In MODES 1, 2, 3, 4, and 5, the RCS pressure shall be maintained
| |
| :-::; 2735 psig. 2.2 SL Violations 2.2.1 If SL 2.1.1 is violated, restore compliance and be in MODE 3 within 1 hour. 2.2.2 If SL 2.1.2 is violated:
| |
| 2.2.2.1 In MODE 1 or 2, restore compliance and be in MODE 3 within 1 hour. 2.2.2.2 In MODE 3, 4, or 5, restore compliance within 5 minutes. BRAIDWOOD
| |
| -UNITS 1 & 2 2.0 -1 Amendment No. 174 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 hour to place the unit, as applicable, in: a. MODE 3 within 7 hours: b. MODE 4 within 13 hours: and c. MODE 5 within 37 hours.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. 3. and 4.BRAIDWOOD
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| -UNITS 1 & 2 3.0 -1 Amendment 98 LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.4 When an LCO is not met, entry into a MODE or other specified condition in the Applicability shall only be made: a. 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;b. After performance of a risk assessment addressing inoperable systems and components, consideration of the results, determination of the acceptability of entering the MODE or other specified condition in the Applicability, and establishment of risk management actions, if appropriate; exceptions to this Specification are stated in the individual Specifications, or c. When an allowance is stated in the individual value, parameter, or other Specification.
| |
| This Specification shall not prevent changes in MODES or other specified conditions in the Ap licability that are required to comply with ACTIONS or that are part of a shutdown of the unit.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 required testing to demonstrate OPERABILITY.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.0 -2 Amendment 134 LCO Applicability 3.0 3.0 LCO Applicability 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, an evaluation shall be performed in accordance with Specification 5.5.15, "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 system's 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.BRAIDWOOD
| |
| -UNITS 1 & 2 3.0 -3 Amendment 98 LCO Applicability 3.0 3.0 LCO Applicability LCO 3.0.7 Exception LCOs allow specified Technical Specification (TS)requirements to be changed to permit performance of special tests and operations.
| |
| Unless otherwise specified, all other TS requirements remain unchanged.
| |
| Compliance with Exception LCOs is optional.
| |
| When an Exception LCO is desired to be met but is not met, the ACTIONS of the Exception LCO shall be met. When an Exception LCO is not desired to be met.entry into a MODE or other specified condition in the Applicability shall be made in accordance with the other applicable Specifications.
| |
| LCO 3.0.8 LCOs. including associated ACTIONs, shall apply to each unit individually, unless otherwise indicated.
| |
| Whenever the LCO refers to a system or component that is.shared by both units, the ACTIONs will apply to both units simultaneously.
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| BRAIDWOOD
| |
| -UNITS 1 & 2 3.0- 4 Amendment 98 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 erform 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.
| |
| BRAIDWOOD
| |
| -'UNITS 1 & 2 3.0- 5 Amendment 98 SR Applicability 3.0 3.0 SR APPLICABILITY 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 hours or up to the limit of the specified Frequency, whichever is greater. This delay period is permitted to allow performance of the Surveillance.
| |
| A risk evaluation shall be performed for any Surveillance delayed greater than 24 hours and the risk impact shall be managed.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.SR 3.0.4 Entry into a MODE or other specified condition in the Applicability of an LCO shall only be made when the LCO's Surveillances have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4 This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.SR 3.0.5 SRs shall apply to each unit individually, unless otherwise indicated.
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| BRAIDWOOD
| |
| -UNITS 1 & 2 3.0 -6 Amendment 134 SDM 3.1.1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.1 SHUTDOWN MARGIN LCO 3.1.1 SDM shall be within the limits specified in the APPLICABILITY:
| |
| MODE 2 with < 1.0, kffif MODES 3, 4, and 5. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. SDM not within limit. A.1 Initiate boration to restore SDM to within 1 imit. 15 minutes SURVEILLANCE SR 3.1.1.1 Verify SDM is with-in the limits specified in the COLR.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.1.1 1 Amendment Core Reactivity 3.1.2 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Core Reactivity LCO 3.1.2 The measured core predicted values.reactivity shall be within +/- 1% Ak/k of APPLICABILITY:
| |
| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Measured core A.1 Re-evaluate core 7 days reactivity not within design and safety limit. analysis.
| |
| and determine that the reactor core is acceptable for continued operation.
| |
| AND A.2 Establish appropriate 7 days operating restrictions and SRs.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met.BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.2 -1 Amendment 98 Core Reactivity
| |
| | |
| ====3.1.2 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify measured core reactivity is within Prior to +/- 1%
| |
| of predicted values. entering MODE 1 after each refueling SR 3.1.2.2 -----------
| |
| : 1. Only required to be performed after 60 Effective Full Power Days (EFPD). 2. The predicted reactivity values may be adjusted (normalized) to correspond to the measured core reactivity prior to exceeding a fuel burnup of 60 EFPD after each fuel loading. Verify measured core reactivity is within In accordance
| |
| +/- 1%
| |
| of predicted values. with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.2 2 Amendment MTC 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Moderator Temperature Coefficient (MTC)LCO 3.1.3 APPLICABILITY:
| |
| The MTC shall be maintained within the limits specified in the COLR. The maximum upper limit shall be that specified in Figure 3.1.3-1.MODE 1 and MODE 2 with keff 2 -1.0 for the upper MTC limit.MODES 1. 2. and 3 for the lower MTC limit.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. MTC not within upper A.1 Establish 24 hours limit. administrative withdrawal limits for control banks to maintain MTC within limit.B. Required Action and B.1 Be in MODE 2 with 6 hours associated Completion keff < 1.0.Time of Condition A not met.C. MTC not within lower C.1 Be in MODE 4. 12 hours limit.BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.3 -1 Amendment 98 MTC 3.1.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.3.1 Verify MTC is within upper limit. Prior to entering MODE 1 after each refueling SR 3.1.3.2 -NOTES- --1. Not required to be performed until 7 Effective Full Power Days (EFPD)after reaching the equivalent of an equilibrium RTP All Rods Out (ARO)boron concentration of 300 ppm.2. If the MTC is more negative than the 300 ppm Surveillance limit (not LCO limit) specified in the COLR.SR 3.1.3.2 shall be repeated once per 14 EFPD during the remainder of the fuel cycle.3. SR 3.1.3.2 need not be repeated if the MTC measured at the equivalent of equilibrium RTP-ARO boron concentration of < 60 ppm is less negative than the 60 ppm Surveillance limit specified in the COLR.Verify MTC is within lower limit. Once each cycle BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.3 -2 Amendment 98 MTC 3.1.3 0 C.)E.0 P-4 Ed Q 0 H-4.A:D Ed 04-4¢-a E-C4 9 8 7 6 5 4 3 UNACCEPTABLE OPERATI ON ACCEPTj OPERAI ABLE'ION 50 60 70 80 90 100 21 I 0'1 0 10 20 30 40 PERCENT RTP Figure 3.1.3-1 (page 1 of 1)Moderator Temperature Coefficient vs. Power Level BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.3 -3 Amendment 98 Rod Group Alignment Limits 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Rod Group Alignment Limits LCO 3.1.4 All shutdown and control rods shall be OPERABLE.AND Individual indicated rod positions shall be within 12 steps of their group step counter demand position.APPLICABILITY:
| |
| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more rod(s) A.1.1 Verify SDM is within 1 hour inoperable.
| |
| the limits specified in the COLR.OR A.1.2 Initiate boration to 1 hour restore SDM to within limit.AND A.2 Be in MODE 3. 6 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.4 -1 Amendment 98 Rod Group Alignment Limits 3.1.4 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION ICOMPLETION TIME B. One rod not within I alignment limit.B.1.1 Verify 5DM is within the limits specified in the COLR.OR B.1.2 Initiate boration to restore SDM to within limit.AND B.2 B.3 AND B.4 Reduce THERMAL POWER to 5 75% RTP.Verify SDM is within the limits specified in the COLR.Determine Heat Flux Hot Channel Factor (Fa(Z)) and Nuclear Enthalpy Rise Hot Channel Factor (FNH)-1 hour 1 hour 2 hours from discovery of Condition B concurrent with inoperability of Power Distribution Monitoring System (PDMS)Once per 12 hours 72 hours (continued)
| |
| AND A. A.BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.4 Amendment 110 Fe, ^ .-11.
| |
| Rod Group Alignment Limits 3.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.5 Re-evaluate safety 5 days analyses and confirm results remain valid for duration of operation under these conditions.
| |
| C. More than one rod not C.1.1 Verify SDM is within 1 hour within alignment the limits specified limit. in the COLR.OR C.1.2 Initiate boration to 1 hour restore required SDM to within limit.AND C.2 Be in MODE 3. 6 hours from discovery of Condition C concurrent with inoperability of PDMS AND C.3 -NOTE Only required to be performed when PDMS is OPERABLE.Restore rod(s) to 72 hours within alignment limit.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.4 -3 Amendment 110 FEB 1 Zr 2J:?
| |
| Rod Group Alignment Limits 3.1.4 ACTIONS (continued)
| |
| CONDITION REOU I RED ACTI ON COMPLETION TIME D. Required Action and associated Completion Time of Condition B or Required Action C.3 not met. D.1 Be in MODE 3. 6 hours SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.1.4.1 Verify individual alignment limit. rod positions within In accordance with the Surveillance Frequency Control Program SR 3.1.4.2 Verify rod freedom of movement (trippability) by moving each rod not fully inserted in the core 10 steps in either direction.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.1.4.3 Verify rod drop time of each rod, from the fully withdrawn position, is 2.7 seconds from the beginning of decay of stationary gr-j pper coil voltage to dashpot entry, with: a. Tavg 550°F; and b. All reactor coolant pumps operating.
| |
| Prior to cri t i ca 1 ity after each removal of the reactor head BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.4 -4 Amendment Shutdown Bank Insertion Limits 3.1.5 3.1 REACTIVITY CONTROL SYSTEMS 3.1.5 Shutdown Bank Insertion Limits LCO 3.1.5 Each shutdown bank shall be within the insertion limits specified in the COLR.-NOTE- -w p o-- g not applicable while performing This LCO is SR 3.1.4.2.APPLICABILITY:
| |
| MODES 1 and 2.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more shutdown A.1.1 Verify SDM is within 1 hour banks not within the limits specified limits. in the COLR.OR A.1.2 Initiate boration to 1 hour restore SDM to within limit.AND A.2 Restore shutdown 2 hours bank(s) to within limits.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met.BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.5 -1 Amendment 98 Shutdown Bank Insertion SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1. 5.1 Verify each shutdown bank is within the insertion limits specified in the COLR. 3.1.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.5 -2 Amendment Control Bank Insertion Limits 3.1.6 3.1 REACTIVITY CONTROL SYSTEMS 3.1.6 Control Bank Insertion Limits LCO 3.1.6 Each control bank shall be within the insertion, sequence.and overlap limits specified in the COLR.This LCO is t ap--i --NOTE--- i --not applicable while performing SR 3.1.4.2.APPLICABILITY:
| |
| MODE 1.MODE 2 with keff 2 1.0.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Control bank insertion A.1.1 Verify SDM is within 1 hour limits not met. the limits specified in the COLR.OR A.1.2 Initiate boration to 1 hour-restore SDM to within limit.AND A.2 Restore control 2 hours bank(s) to within .limits.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.6 -1 Amendment 98 Control Bank Insertion Limits 3.1.6 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Control bank sequence or overlap limits not met. B.1.1 OR Verify SDM is within the limits specified in the COLR. 1 hour B.1.2 AND Initiate boration to restore SDM to within 1 imit. 1 hour C. Required Action and associated Completion Time not met. B.2 C.1 Restore control bank sequence and overlap to within limits. Be in MODE 2 with keff < 1. O. 2 hours 6 hours SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.1.6.1 Verify estimated critical control bank position is within the limits specified in the COLR. Within 4 hours prior to criticality SR 3.1.6.2 Verify each control bank is within the insertion limits specified in the COLR. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.1.6 -2 Amendment 165/165 Control Bank Insertion SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.1. 6.3 Verify each control bank not fully withdrawn from the core is within the sequence and overlap limits specified in the COLR.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.1.6 3 Amendment I Rod Position Indication 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Rod Position Indication LCO 3.1.7 APPLICABILITY:
| |
| The Digital Rod Position Indication (DRPI) System and the Demand Position Indication System-shall be OPERABLE.MODES 1 and 2.ACTIONS t InTr-__-_-Fu-"I ll I-Separate position_II." I _Condition entry is allowed for each inoperable DRPI indicator.
| |
| and each demand CONDITION REQUIRED ACTION COMPLETION TIME A. One DRPI per group A.1 Verify the position Once per 8 hours inoperable for one or of the rods with more groups. inoperable DRPIs.OR A.2 Reduce THERMAL POWER 8 hours to s 50% RTP.B. One or more rods with B.1 Initiate action to Immediately inoperable DRPIs have verify the position been moved in excess of the rods with of 24 steps in one inoperable DRPIs.direction since the last determination of OR the rod's position.B.2 Reduce THERMAL POWER 8 hours to s 50% RTP.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.7-1 Amendment 110 FEB 'L SO 201 Rod Position Indication
| |
| | |
| ====3.1.7 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. One demand position C.1.1 Verify by Once per 8 hours indicator per bank administrative means inoperable for one or all DRPIs for the more banks. affected bank(s) are OPERABLE.C;1.2 Verify the most Once per 8 hours withdrawn rod and the least withdrawn rod of the affected bank(s) are S 12 steps apart.OR C.2 Reduce THERMAL POWER 8 hours to < 50X RTP.D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time not met.SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify each DRPI agrees within 12 steps of Prior to the group demand position for the full criticality indicated range of rod travel. after each removal of the reactor head.BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.7-2 Amendment 98 PHYSICS TESTS Exceptions -MODE 2 3.1.8 3.1 REACTIVITY CONTROL SYSTEMS 3.1.8 PHYSICS TESTS Exceptions -MODE 2 LCO 3.1.8 During the performance of PHYSICS TESTS. the requirements of LCO LCO LCO LCO LCO 3.1.3.3.1.4.3.1.5.3.1.6.3.4.2."Moderator Temperature Coefficient (MTC)": "Rod Group Alignment Limits": "Shutdown Bank Insertion Limits": "Control Bank Insertion Limits": and"RCS Minimum Temperature for Criticality" may be suspended, provided: a. Reactor Coolant System (RCS) lowest loop average temperature is 2 530 0 F: b. SDM is within the limits specified in the COLR: and c. THERMAL POWER is s 5% RTP.APPLICABILITY:
| |
| MODE 2 during PHYSICS TESTS.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.. SDM not within limit. A.1 Initiate boration to 15 minutes restore SDM to within limit.AND.A.2 Suspend PHYSICS TESTS 1 hour exceptions.
| |
| B. THERMAL POWER not B.1 Open reactor trip Immediately within limit. breakers.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.1.8 -1 Amendment 98 PHYSICS TESTS Exceptions-MODE 2 3.1.8 ACTIONS (continued)
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME C. RCS lowest loop average not within imit. C.1 Restore RCS lowest loop average temperature to within 1 imit. 15 minutes D. Required Action and associated Completion Time of Condition C not met. 0.1 Be in MODE 3. 15 minutes SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.1.8.1 Perform CHANNEL OPERATIONAL TEST on power range and -j ntermedi ate range channel s per SR 3.3.1.7, SR 3.3.1.8, and Table 3.3.1.1-1.
| |
| Prior to initiation of PHYSICS TESTS SR 3.1.8.2 Verify the RCS lowest loop average temperature is 530°F. In accordance with the Surveillance Frequency Control Program SR 3.1.8.3 Verify THERMAL POWER is 5% RTP. In accordance with the Surveillance Frequency Control Program SR 3.1.8.4 Ve rify SDM is wi th-j n the 1-j mits speci fi ed in the COLR. In accordance with the Su rvei 11 ance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.1.8-2 Amendment I Fo(Z)3.2.1 3.2 POWER DISTRIBUTION LIMITS 3.2.1 Heat Flux Hot Channel Factor (Fo(Z))LCO 3.2.1 Fo(Z). as approximated by Fo(Z) and Fo(Z). shall be within the limit specified in the COLR.I APPLICABILITY:
| |
| MODE 1.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fo(Z) not within A.1 Reduce THERMAL POWER 15 minutes limit. k 1% RTP for each 1% Fo(Z) exceeds limit.AND A.2 Reduce Power Range 72 hours Neutron Flux- High trip setpoints 2 1%for each 1% Fo(Z)exceeds limit.AND A.3 Reduce Overpower AT 72 hours trip setpoints 2 1%for each 1% Fo(Z)exceeds limit.B. Fo(Z) not within B.1 Reduce THERMAL POWER 4 hours limit. k 1% RTP for each 1% Fo(Z) exceeds limit.AND (conti nued)BRAIDWOOD
| |
| -UNITS 1 & 2 3.2.1 -1 Amendment 110 FEB I 3 2 0o I F 0 (Z)3.2.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.2 Reduce Power Range 72 hours Neutron Flux-High trip setpoints
| |
| ; 1%for each 1% Fow(Z)exceeds limit.AND B.3 Reduce Overpower AT 72 hours trip setpoints 2 1X for each 1% Fw(Z)exceeds limit.C. Required Action and C.1 Be in MODE 2. 6 hours associated Completion Time not met.I BRAIDWOOD
| |
| -UNITS 1 & 2 3.2.1 -2 Amendment 110 FED I :3 2aIl SURVEILLANCE SURVEI SR -------NOTES -----During power escalation at the beginning of each cycle, THERMAL POWER may be increased until an equilibrium power level has been achieved, at which a power distribution map is obtained. Not required to be performed until 12 hours after declaring Power Distribution Monitoring System (PDMS)inoperable.
| |
| Performance of SR 3.2.1.3 satisfies the initial performance of this SR after declaring PDMS inoperable.
| |
| Verify is within limit specified in the COLR.
| |
| Prior to exceeding 75% RTP after each refueling AND Once within 12 hours after achieving equil i bri um conditions after exceeding, by 2 10% RTP, the THERMAL POWER at whi ch F5 (D was last verified In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.2.1 -3 Amendment 165/165 F 0 (Z)3.2.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.2.1.2 NOTES 1. During power escalation at the beginning of each cycle. THERMAL POWER may be increased until an equilibrium power level has been achieved.
| |
| at which a power distribution map is obtained.2. If Fo(Z) measurements indicate that the[ Fo(Z) 1 maximum over z K(Z) j has increased since the previous evaluation of Fo(Z): a. Increase Fo"(Z) by the greater of a factor of 1.02 or by an appropriate factor specified in the COLR and reverify Fo(Z) is within limits specified in the COLR; or b. Repeat SR 3.2.1.2 once per 7 EFPD until either a. above is met or two successive flux maps indicate that the[ F. (Z)1 maximum over z K(Z)has not increased.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.2.1- 4 Amendment 110.FE13 1 3 -a2l SURVEILLANCE REQUIREt"IENTS SR 3.2.1.2 (continued) Not required to be performed until 12 hours after declaring PDMS inoperable.
| |
| Performance of SR 3.2.1.4 satisfies the initial performance of this SR after declaring PDMS inoperable.
| |
| Verify (Z) is wi thi n 1 i mi t specifi ed in the COLR.
| |
| Prior to exceeding 75% RTP after each refueling Once within 12 hours after achieving equi l-j br-j um conditions after exceeding, by 10% RTP, the THERMAL POWER at whi ch was last verified In accordance with the Surveillance Frequency Control Program (cont -j n ued ) BRAIDWOOD
| |
| -UNITS 1 &2 3.2.1 -Amendment 165/165 Fo(l) 3.2.1 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.2.1.3 Only required to be performed when PDMS is OPERABLE.
| |
| Verify Fg(n the COLR. is within limit specified in In accordance with the Surveillance Frequency Control Program SR 3.2.1.4 --NOTE --Only required to be performed when PDMS is OPERABLE.
| |
| Verify F;(Z) the COLR. is within limit specified in In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.2.1 6 Amendment FNH 3.2.2 3.2 POWER DISTRIBUTION LIMITS 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor (F&H)I LCO 3.2.2 APPLICABILITY:
| |
| F&H shall be within the limit specified in the COLR.MODE 1.I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----NOTE -A.1 Reduce THERMAL POWER 4 hours Required Actions A.2 to < 50% RTP.and A.4 must be completed whenever AND Condition A is entered. A.2 Determine F&H. 24 hours AND F^H not within limit.A.3 Reduce Power Range 72 hours Neutron Flux- High trip setpoints to< 55% RTP.AND (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.2.2 -1 Amendment 110 FEB 1 3 2O31 3NAH 3.2.2 I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.4 NOTE THERMAL POWER does not have to be reduced to comply with this Required Action.Determine F&H* Prior to exceeding 50% RTP AND Prior to exceeding 75% RTP AND 24 hours after reaching 2 95% RTP B. Required Action and B.1 Be in MODE 2. 6 hours associated Completion Time not met.BRAIDWOOD
| |
| -UNITS 1 & 2 3.2.2 -2 Amendment 110.E3 D I 2-31 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.2.2.1 -------------NOTE-
| |
| --------Not requi red to be performed untn 12 hours after declaring POMS inoperable.
| |
| Performance of SR 3.2.2.2 satisfies the initial performance of this SR after declaring POMS Verify is within limits specified in COLR. SR 3.2.2.2 --------------NOTE----Only required to be performed when POMS is OPERABLE.
| |
| Verify F: H is with-j n 1 imit specifi ed in the COLR. Prior to exceeding 75% RTP after each refueling In accordance with the Surveillance Frequency i Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.2.2 3 Amendment AFD 3.2.3 3.2 POWER DISTRIBUTION LIMITS 3.2.3 AXIAL FLUX DIFFERENCE LCD 3.2.3 The AFD shall be maintained within the limits specified the COLR. ------------
| |
| ---NOTE The AFD shall be considered outside limits when two or more OPERABLE excore channels indicate AFD to be outside limits. APPLICABILITY:
| |
| MODE 1 with THERMAL POWER 50% RTP when Power Distribution Monitoring System (PDMS) is inoperable.
| |
| ACTIONS CONDITION REQU I RED ACTI ON COMPLETION TIME A. AFD not within limits. A.l Reduce THERMAL POWER 30 mi nutes to < 50% RTP. SURVEILLANCE SURVEI SR ---------NOTE-------
| |
| -------Not required to be performed until 12 hours after declaring PDMS inoperable.
| |
| Verify AFD is within limits for each OPERABLE excore channel.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.2.3 1 Amendment I QPTR 3.2.4 3.2 POWER DISTRIBUTION LIMITS 3.2.4 QUADRANT POWER TILT RATIO (QPTR)LCO 3.2.4 APPLICABILITY:
| |
| The QPTR shall be s 1.02.MODE 1 with THERMAL POWER > 50% RTP when Power Distribution Monitoring System (PDMS) is inoperable.
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. QPTR not within limit. A.1 Reduce THERMAL POWER 2 hours after 2 3% from RTP for each QPTR each 1% of QPTR determination
| |
| > 1.00.AND A.2 Determine QPTR and Once per reduce THERMAL POWER 12 hours 2 3% from RTP for each 1% of QPTR> 1.00.AND A.3 Perform SR 3.2.1.1. 24 hours after SR 3.2.1.2. and achieving SR 3.2.2.1. equilibrium conditions from a THERMAL POWER reduction per Required Action A.1 AND Once per 7 days thereafter AND (continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3.2.4 -1 Amendment 110 FEB 13 2aO1.
| |
| QPTR 3.2.4 ACTIONS CONDITION I REQUIRED ACTION I COMPLETION TIME A. (continued)
| |
| A.4 Re-evaluate safety analyses and confirm results remain valid for duration of operation under this condition.
| |
| AND A. 5-----NOTES------
| |
| : 1. Perform Required Action A.5 only after Required Action A.4 is completed.
| |
| : 2. Required Action A.6 shall be completed whenever Required Action A.5 is performed.
| |
| Prior to exceeding the THERMAL POWER limit of Required Action A.1 Prior to exceeding the THERMAL POWER limits of Required Action A.1.(continued)
| |
| Normalize excore detectors to restore QPTR to within limits.AND BRAIDWOOD
| |
| -UNITS 1 & 2 3.2.4 -2 Amendment 98 I QPTR 3.2.4 I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.6 NOTE Perform Required Action A.6 only after Required Action A.5 is completed.
| |
| Perform SR 3.2.1.1. 24 hours after SR 3.2.1.2. and achieving SR 3.2.2.1. equilibrium conditions at RTP not to exceed 48 hours after exceeding the THERMAL POWER limit of Required Action A.1 B. Required Action and B.1 Reduce THERMAL POWER 4 hours associated Completion to 5 50% RTP.Time not met.BRAIDWOOD
| |
| -UNITS 1 & 2 3.2.4 -3 Amendment 110 FEB 13 2001 QPTR 3.2.4 SLiRVEI LLANCE REQLI I REMENTS SURVEILLANCE FREQUENCY SR 3.2.4.1 -------------
| |
| NOTES --------------
| |
| : 1. With input from one Power Range Neutron Flux channel inoperable and THERMAL POWER $ 75% RTP, the remaining three power range channel inputs can be used for calculating QPTR. 2. SR 3.2.4.2 may be performed in lieu of this Surveillance.
| |
| : 3. Not required to be performed until 12 hours after declaring PDMS i noperab 1 e. Verify QPTR is $ 1.02 by calculation.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.2.4.2 ----------------
| |
| NOTES ------------------
| |
| : 1. Not required to be performed until 12 hours after input from one Power Range Neutron Flux channel is inoperable with THERMAL POWER > 75% RTP. 2. Not required to be performed until 12 hours after declaring PDMS i noperab 1 e. Verify QPTR is $ 1.02 using the movable In accordance incore detectors.
| |
| with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.2.4 4 Amendment DNBR 3.2.5 3.2 POWER DISTRIBUTION LIMITS 3.2.5 Departure from Nucleate Boning Ratio LCO 3.2.5 DNBR shall be within the limit specified in the APPLICABILITY:
| |
| MODE 1 with THERMAL POWER 50% RTP when Power Monitoring System (PDMS) is OPERABLE.
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. DNBR not within limit. A.1 Restore ONBR to within limit. 2 hours B. Required Action and associated Completion Time not met. B.1 Reduce THERMAL POWER to < 50% RTP. 4 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.5.1 Verify DNBR is within limit specified in the COLR.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.2.5 1 Amendment
| |
| | |
| 3.3.1 RTS Instrumentation ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. One channel inoperable.
| |
| or train While this LCO is not met for Function 18, 19, or 20 in MODE 5, making the Rod Control System capable of rod withdrawal is not permitted.
| |
| C.1 Restore channel or train to OPERABLE status. 48 hours OR C.2.1 Initiate action to fully insert all rods. 48 hours AND C.2.2 Place the Rod Control System in a condition incapable of rod withdrawal.
| |
| 49 hours BRAIDWOOD UNITS 1 &2 3.3.1-2 Amendment ACTIONS (continued)
| |
| CONDITION D. One Power Range Neutron Flux-High channel inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 REQUIRED ACTION -------------NOTE------------
| |
| One channel may be bypassed for up to 12 hours for surveillance testing and setpoint adjustment.
| |
| D.l OR D.2 Place channel in trip. Be in MODE 3. RTS Instrumentation
| |
| | |
| ====3.3.1 COMPLETION====
| |
| | |
| TIME 72 hours 78 hours (continued) . ' 3.3.1-3 Amendment No. 180 ACTIONS (continued)
| |
| CONDITION E. One channel inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 REQUIRED ACTION -------------NOTE------------
| |
| One channel may be bypassed for up to 12 hours for surveillance testing. E.1 OR E.2 Place channel in trip. Be in MODE 3. RTS Instrumentation
| |
| | |
| ====3.3.1 COMPLETION====
| |
| | |
| TIME 72 hours 78 hours (continued) 3.3.1-4 Amendment No. 180 3.3.1 RTS Instrumentation ACTI ONS (conti n ued ) CONDITION REQUI RED ACTI ON COMPLETION TIME F. One Intermediate Range Neutron Flux channel inoperable.
| |
| F.l Reduce THERMAL POWER to < P-6. OR 2 hours F.2 Increase THERMAL POWER to > P-I0. 2 hours G. Two Intermediate Range Neutron Flux channels inoperable.
| |
| G.l Suspend operations involving positive reactivity additions.
| |
| AND G.2 Reduce THERMAL POWER to < P-6. Imnediately 2 hours H. One Source Range Neutron Flux channel inoperable.
| |
| H.l Suspend operations involving positive reactivity additions.
| |
| Imnediately
| |
| : 1. Two Source Range Neutron Flux channels inoperable.
| |
| 1.1 Open Reactor Trip Breakers (RTBs). Imnediately J. One Source Range Neutron Flux channel inoperable.
| |
| J.l Restore channel to OPERABLE status. OR 48 hours J.2.1 Initiate action to fully insert all rods. AND 48 hours J.2.2 Place the Rod Control System in a condition incapable of rod withdrawal.
| |
| 49 hours (contlnued)
| |
| BRAIDWOOD UNITS 1 &2 3.3.1 5 Amendment 169 ACTIONS (continued)
| |
| CONDITION K. One channel inoperable.
| |
| L. One Turbine Trip channel inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 REQUIRED ACTION ------------NOTES------------
| |
| : 1. For Functions with installed bypass test capability (Functions 8a, 9, 10), one channel may be bypassed for up to 12 hours for surveillance testing. 2. For Functions with no installed bypass test capability (Functions 12 and 13), the inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels.
| |
| -----------------------------
| |
| K.1 Place channel in trip. OR K.2 Reduce THERMAL POWER to< P-7. ------------NOTE-------------
| |
| The inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels.
| |
| -----------------------------
| |
| L.1 Place channel in trip. OR L.2 Reduce THERMAL POWER to < P-8. RTS Instrumentation
| |
| | |
| ====3.3.1 COMPLETION====
| |
| | |
| TIME 72 hours 78 hours 72 hours 78 hours (contlnued) 3.3.1-6 Amendment No. 180 RTS Instrumentation
| |
| | |
| ====3.3.1 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME M. One train inoperable. One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE.
| |
| M.1 OR Restore train to OPERABLE status. M.2 Be in MODE 3. 24 hours 30 hours N. One RTB trai n inoperable.
| |
| One train may be bypassed for up to 4 hours for surveillance testing, provided the other train is OPERABLE. ---N.1 Restore train to OPERABLE status. OR 24 hours N.2 Be in MODE 3. 30 hours O. One or more channels 0.1 Verify interlock is in 1 hour i noperab 1required state for existing unit conditions.
| |
| OR Be in MODE 3. 7 hours (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 -Amendment 169 3.3.1 RTS Instrumentation ACTIONS (continued)
| |
| CONDITION REOUI RED ACTI ON P. One or more channels inoperable.
| |
| P.1 Verify interlock is in required state for existing unit conditions.
| |
| OR 1 hour P.2 Be in MODE 2. 7 hours O. One trip mechanism inoperable for one RTB. 0.1 Restore inoperable trip mechanism to OPERABLE status. OR 48 hours 0.2 Be in MODE 3. 54 hours R. One Reactor Coolant Pump (RCP) Breaker Pos it ion cha nne 1 (per train) inoperable. --
| |
| The inoperable channel may be bypassed for up to 4 hours for surveillance testing of other channels.
| |
| --R.1 Place channel in trip. OR 6 hours R.2 Reduce THERMAL POWER to < P-7. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.1 -8 Amendment 169 3.3.1 RTS Instrumentation SURVEILLANCE REQUIREMENTS
| |
| -------------------
| |
| --------NOTE-
| |
| ------------
| |
| Refer to Table 3.3.1-1 to determine which SRs apply for each RTS Function.
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.1 Perform CHANNEL CHECK. In accordance the Surveillance Frequency Control Program SR 3.3.1.2 --------Adjust NIS channel if absolute difference is > 2%. Not required to be performed until 12 hours after THERMAL POWER is 15% RTP. Compare results of calorimetric heat In accordance the balance calculation to Nuclear Instrumentation System (NIS) channel Surveillance output. Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.3.1 -Amendment RTS Instrumentation
| |
| | |
| ====3.3.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.3.1.3
| |
| : 1. Adjust NIS channel if absolute difference is 3%. 2. Only required to be performed with THERMAL POWER> 15% RTP. Compare results of the incore measurements to NIS AFD. Prior to exceeding 75% RTP after each refueling In accordance with the Surveillance Frequency Control Program SR 3.3.1.4 This Surveillance must be performed on the RTBB prior to placing the bypass breaker in service. Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.5 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UN 1 &2 3.3.1 -10 Amendment 3.3.1 RTS Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE QUENCY SR 3.3.1.6 Not required to be performed until 24 hours after THERMAL POWER is 75% RTP. Calibrate excore channels to agree with In accordance incore measurements.
| |
| with the Surveillance Frequency Control Program SR 3.3.1. 7 -----
| |
| : 1. Not required to be performed for source range instrumentation prior to entering MODE 3 from MODE 2 until 4 hours after entry into MODE 3. 2. The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capabi 1 i ty Perform In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.3.1 -11 Amendment 3.3.1 RTS SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.3.1.8
| |
| : 1. This Surveillance shall include verification that interlocks P 6 and P-I0 are in their required state for existing unit conditions.
| |
| : 2. The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capabi 1 ity. Perform COT.
| |
| Only required when not performed within the Frequency specified in the Survei II ance Frequency Control Program Prior to reactor sta rtup Four hours after reducing power below P 10 for power and intermediate instrumentation Four hours after reducing power below P 6 for source range instrumentation (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 -12 Amendment 3.3.1 RTS Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.1.8 (continued)
| |
| In accordance with the Surve-i 11 ance Frequency Control Program SR 3.3.1.9 -
| |
| Verification of setpoint is not required.
| |
| Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.10 This Surveillance shall include verification that the time constants are adjusted to the prescribed values. Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.3.1.11 Neutron detectors CALIBRATION. are excluded from CHANNEL Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.1 l3 Amendment 171 3.3.1 RTS Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.3.1.12 ----NOTE --------The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
| |
| Perform COT.
| |
| In accordance with the . Survei 11 ance Frequency I Control Program SR 3.3.1.13 ----NOTE --Verification of setpoint is not required.
| |
| Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.1.14 Verification of setpoint is not required.
| |
| Perform TADOT. Only required when not performed within previous 31 days Prior to reactor startup continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 -14 Amendment 171 3.3.1 RTS SURVEI LLANCE REQU I REMENTS (continued)
| |
| SURVEI LLANCE SR 3.3.1.15 -------------------NOTE---
| |
| -
| |
| Neutron detectors are excluded from response time Verify RTS RESPONSE TIME is within In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.3.1 15 Amendment RTS Instrumentation
| |
| | |
| ====3.3.1 Table====
| |
| 3.3.1-1 (page 1 of 6) Reactor Trip System Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVE I LLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 1. Manual Reactor Tri p 1,2 2 B SR 3.3.1.13 NA 2 C SR 3.3.1.13 NA 2. Power Range Neutron Flux a. High 1,2 4 0 SR 3.3.1.1 SR 3.3.1.2 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15 s; 110.8% RTP b. Low lib) ,2 4 E SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.15 s; 27.0% RTP 3. Power Range Neutron Flux-High Positive Rate 1,2 4 E SR 3.3.1.7 SR 3.3.1.11 S; 6.2% RTP with time constant 2 sec 4. Intermeciate Range Neutron Fl ux lib), 21cl 2 F,G SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 s; 30.0% RTP 5. Source Range Neutron Flux 2'dl 2 H, I SR 3.3.1.1 SR 3.3.1.8 SR 3.3.1.11 SR 3.3.1.15 s; 1.42 E5 cps 31al, 41al, 5 1a ) 2 I,J SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.11 SR 3.3.1.15 S; 1.42 E5 cps (continued) (al With Rod Control System capable of rod withdrawal or one or more rods not fully inserted. (b) Below the P-I0 (Power Range Neutron Flux) interlock. (c) Above the P-6 (Source Range Block Permissive) interlock. (d) Below the P-6 (Source Range Block Permissive) interlock.
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 -16 Amendment 1 RTS Instrumentation
| |
| | |
| ====3.3.1 Table====
| |
| 3.3.1-1 (page 2 of 6) Reactor Trip System Instrumentation APpLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CONDlTlONS CHANNELS CONDITIONS REQU I REMENTS VALUE Overtemperature 1,2 4 E SR 3.3.1.1 to SR 3.3.1.3 SR 3.3.1.6 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 Overpower 1.2 4 E SR SR SR SR
| |
| : 8. Pressurizer Pressure Low 1 ,,: 4 K SR 3.3.1.1 1875 psig SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 High 1,2 4 E SR 3.3.1.1 2393 psig SR3.3.1.7 SR3.3.1.10 SR 3.3.1.15 1 (c)Water 3 SR 3.3.1.1 93.5% of SR 3.3.1.7 instrument SR 3.3.1.10 span 10. Reactor 1 (El 3 K SR 3.3.1.1 (per loop) SR SR SR 1 (ei (RCP) (per 11. Reactor Cool ant R SR 3.3.1.13 NA (continued) (el Above the P-7 (Low Power Reactor Trips Block) interlock.
| |
| BRAIDWOOD UNITS 1 & 2 3.3.1 Amendment RTS Instrumentation
| |
| | |
| ====3.3.1 Table====
| |
| 3.3.1-1 (page 3 of 6) Reactor Trip System Instrumentation FUNCTION APpLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEILLANCE REQU I REMENTS ALLOWABLE VALUE 12. Undervol tage RCPs (per train) 4 K SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.15 :?: 4920 V 13. Underfrequency RCPs (per train) 4 K SR 3.3.1.9 SR 3.3.1.10 SR 3.3.1.15 :?: 56.08 Hz 14. (SG) a. Unit 1 1,2 4 E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 :?: 16.1% of narrow range instrument D. Unit 2 1,2 4 E SR 3.3.1.1 SR 3.3.1.7 SR 3.3.1.10 SR 3.3.1.15 2: 34.8% of na rrow range instrument span 15. Turbine Trip a. Emergency Trip Header PressClre (per train) 1 (f) 3 L SR3.3.1.10 SR 3.3.1.14 2: 910 psig b. I(f) 4 L SR 3.3.1.10 SR 3.3.1.14 2: 1% open 16. Safety Injection (SI) Input from Engineered Safety Feature Actuation System (ESFAS) 1,2 Z trai ns SR 3.3.1.13 NA (continued) (e) Above the P*7 (Low Power Reactor Trips Block) interlock. (f) Above the P*8 (Power Range Neutron Flux) interlock.
| |
| BRAIDWOOD UNITS 1 & 2 3.3.1 18 Amendment 171 RTS Instrumentation
| |
| | |
| ====3.3.1 Table====
| |
| 3.3.1-1 (page 4 of 6)Reactor Trip System Instrumentation APpLICABLE MODES OR OTHEr< SPECIFIED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE Reactor Trip System Source Range Block 2 0 SR 1.11 ?: 6£*11 amp Penni 5si ve. SR 1.12 Power Block. (1) P*lO 3 P SR 3.3.1.11 NA SR 3.3.1.12 P-13 Input 2 P SR 3.3.1.10 NA SR 3.3.1.12 Power Range 3 P SR 3.3.1.11 ::; 32.1% RTP Neutron Flux. P*8 Sr< 3.3.1.12 1.2 3 0 SR 3.3.1.11 ?: 7.9% RTP and SR 3.3.1.12 ::; 12.1% RTP Turbine l1iu15e 2 P SR 1.10 ::; 12.1% Pressure.
| |
| -13 SR 1.12 turbi ne power Reactor Tri¥ 1.2 2 trains N SR 3.3.1.4 NA Breakers (R Bs) I,) 3(d) I 4: 0) I 5 id) 2 trains C SR 3.3.1.4 NA Reactor Trip Breaker 1.2 1 each per RTB Q SR 3.3.1.4 NA Undervo 1 tage and Shunt ('Trip Mechanisms 3 (3). 4 1 ,). 5(a) 1 each per RTB \., SR 3.3.1.4 NA Automatic Trip Logic 1.2 2 trains M SR 3.3.1.5 NA ('4(3). 5 1a) 2 trains \., SR 3.3.1.5 NA (al With Rod Control System capable of rod witharawal or one or rrore rods not fully inserted. (d) Below the P-6 (Source Range B'ock Pennissive) lnterlock. (g) Including any reactor trip bypass breakers that are racked in and closed for bypassing an RTB. BRAIDWOOD UNITS 1 & 2 3.3.1 Amendment 3.3.1 AT( 5) [_1_]5 A ( 1+T 2 5) 1+T3 5 RTS Instrumentation Table 3.3.1-1 (page 5 of Reactor Trip System Note 1: Overtemperature 6T The Overtemperature 6T Function Allowable Value shall not exceed the following Trip Setpoint by more than 1.04% of 6T span. 6T is measured Reactor Coolant System (RCS) 6T, 6T o is the indicated 6T at RTP, of. sis the Lapl ace transform operator, sec l , T is the measured RCS average temperature, OF. T/ is the nomi na 1 at RTP, :5 *. P is the measured pressurizer pressure, pi is the nominal RCS operating pressure, =K 1 --* K, ,: =
| |
| * K3 T1 =
| |
| * T2
| |
| * T 3 <-T 4 --* T, 5 --* T, 6 <-f l (6I) = *{* + (qt -qb)} when qt -qb <
| |
| * RTP 0% of RTP when
| |
| * RTP :5 qt -qb :5
| |
| * RTP *{ (qt -qb) *} when qt qb >
| |
| * RTP Where qt and qb are percent RTP in the upper and lower halves of the core, respectively, and qt + qb is the total THERMAL POWER in percent RTP. As specified in the COLR.* BRAIDWOOD
| |
| -UNITS 1 &2 3.3.1 Amendment 3.3.1 RTS Instrumentation Table 3.3.1-1 (page 6 of Reactor Trip System Note 2: Overpower The Overpower Function Allowable Value shall not exceed the following Trip Setpoint by more than 3.60% of span. T (l+TI s) [_1_] :::; To {K4 -K5 [_l_J T-K6 [T _1_ -TII]-f2 I)}(1+T2 s) 1+T7 s 1+T6 s 1+T6 s is measured RCS of. is the indicated at RTP, OF. sis the Lapl ace transform operator, sec-I. T is the measured RCS average temperature, OF. Til is the nominal Tav9 at RTP, 5 *. I<s =
| |
| * for -increas-jng Tav9 I\; =
| |
| * when T > Til
| |
| * for decreas-j ng
| |
| * when T 5 1" TI --* T2 --T6 5
| |
| * T 7 --As specified in the COLR.* BRAIDWOOD
| |
| -LIN ITS 1 & 2 3.3.1 -Amendment 171 ESFAS Instrumentation 3.3.2 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.2 Engineered====
| |
| | |
| Safety Feature Actuation System (ESFAS) Instrumentation LCO 3.3.2 APPLICABILITY:
| |
| The ESFAS instrumentation for each Function in Table 3.3.2-1 shall be OPERABLE.According to Table 3.3.2-1.ACTIONS Separate Condition entry is allowed--------------
| |
| _ _ _ ___ _ ____ _ ________INU I _for each Function.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in required channels or Table 3.3.2-1 for the trains inoperable.
| |
| channel(s) or train(s).B. One channel B.1 Restore channel to 48 hours inoperable.
| |
| OPERABLE status.OR B.2.1 Be in MODE 3. 54 hours AND B.2.2 Be in MODE 5. 84 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.2 -1 Amendment 98
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION C.1 -------NOTE-
| |
| -----C. One train inoperable.
| |
| One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE.
| |
| Restore train to 24 hours OPERABLE status. OR C.2.1 Be in MODE 3. 30 hours AND C.2.2 Be in MODE 5. 60 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.2 2 Amendment 169 ACTIONS (continued)
| |
| CONDITION D. One channel inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 D.1 OR ESFAS Instrumentation
| |
| | |
| ====3.3.2 REQUIRED====
| |
| ACTION One channel may be bypassed for up to 12 hours for surveillance testing. Place channel in trip. COMPLETION TIME 72 hours D.2.1 Be in MODE 3. 78 hours AND D.2.2 Be in MODE 4. 84 hours (continued) 3.3.2 -3 Amendment No. 180
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation ACTIONS (continued)
| |
| CONDITION REQU I RED ACTI COMPLETION TIlvlE E. One Containment Pressure channel -inoperable.
| |
| E.1 OR E.2.1 AND E.2.2 One additional channel may be bypassed for up to 12 hours for surveillance testing.
| |
| Place channel in bypass. Be in MODE 3. Be in MODE 4. 72 hours 78 hours 84 hours F. One channel inoperable.
| |
| or trai n F.1 OR F.2.1 AND F.2.2 Restore channel or train to OPERABLE status. Be i n
| |
| : 3. Be in MODE 4. 48 hours 54 hours 60 hours (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -4 Amendment 169
| |
| | |
| ====3.3.2 Instrumentation====
| |
| | |
| ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME G. One train inoperable.
| |
| G.I NOTE One train may be bypassed for up to 4 hours for surveillance testing provided the other train is OPERABLE.
| |
| Restore train to OPERABLE status. OR 24 hours G.2.I Be in MODE 3. AND 30 hours G.2.2 Be in MODE 4. 36 hours H. One channel i noperab 1 e. H.I One channel may be bypassed for up to 2 hours for surveillance testing provided the other channel is OPERABLE.
| |
| Place channel in tr-j p. OR 1 hour H.2.1 Be in MODE 3. AND 7 hours H.2.2 Be in MODE 4. 13 hours (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -5 Amendment 169
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION TIME 1. One channel inoperable.
| |
| 1.1 The inoperable channel may be bypassed for up to 12 hours for surveillance testing of other channels.
| |
| OR Place channel in tr-ip. 72 hours 1.2 in MODE 3. 78 hours J. One or more trains inoperable.
| |
| J.1 Declare associated auxiliary feedwater pump inoperable.
| |
| Irrrnediately (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -6 Amendment 169 ACTIONS (continued)
| |
| CONDITION K. One channel i noperab 1 e. BRAIDWOOD
| |
| -UNITS 1 & 2 K.1 OR ESFAS Instrumentation
| |
| | |
| ====3.3.2 REQUIRED====
| |
| ACTION One channel may be bypassed for up to 12 hours for surveillance testing. Place channel in trip. COMPLETION TIME 72 hours K.2.1 Be in MODE 3. 78 hours AND K.2.2 Be in MODE 5. 108 hours (continued) 3.3.2 -7 ArnendmenLNo.
| |
| 180
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation ACTIONS (continued)
| |
| REQU I RED ACTI ON TIlvlE L. One or more channels inoperable.
| |
| L.1 OR Verify "interlock is in required state for existing unit condition.
| |
| L.2.1 Be in MODE 3. AND L.2.2 Be "in
| |
| : 4. 1 hour 7 hours 13 hours SURVEILLANCE REQUIREMENTS Refer to Table 3.3.2-1 to determine which SRs apply for each ESFAS Function.
| |
| SR 3.3.2.1 SURVEILLANCE Perform CHANNEL CHECK. FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.3.2.2 Perform COT. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UN ITS 1 & 2 3.3.2 -8 Amendment 169
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.3.2.3
| |
| -
| |
| Verification of relay setpoints not requ-j red. Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.4 Perform ACTUATION LOGIC TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.5 Perform MASTER RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.6 The SSPS input relays are excluded from this Surveillance for the Functions with installed bypass test capability.
| |
| Perform COT. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.3.2 -9 Amendment
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.3.2.7 SURVEI LLANCE Verification of relay setpoints not required.
| |
| FREQUENCY Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.8 Perform SLAVE RELAY TEST. In accordance with the Surveillance Frequency Control Program SR 3.3.2.9 Verification of setpoint not required.
| |
| Perform TADOT. In accordance with the Surveillance Frequency Control Program SR 3.3.2.10 This Surveillance shall include verification that the time constants are adjusted to the prescribed values. Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program (cont -j nued) BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -10 Amendment 171
| |
| | |
| ====3.3.2 ESFAS====
| |
| Instrumentation SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.3.2.11 Verify ESFAS RESPONSE are with-in l imi t. In accordance with the Surveillance Frequency Contro l Program SR 3.3.2.12 Verify ESFAS RESPONSE TIMES are within limit . In accordance with the Surveillance Frequency Contra l Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.2 11 Amendment ESFAS Instrumentation 3.3.2 1 of 6) Engineered Safety System Instrwentati on APPLICABLE MODES OR FUNCTION OTHER SPECjI'I ED CONDITIONS REQUIRED CHI\NNELS CONDITIONS SURVEI LLANCE REQUI REMENTS ALLOWABLE VALUE 1. Safety Injection
| |
| : a. Manua 1 Ini ti aU on 1,2,3,4 2 B SR 3.3.2.9 NA b. Automatic Actuat ion Logi c Actuation ays 1.2,3,4 2 trains C SR SR SR 3.3.2.4 3.3.2.5 3.3,2,8 NA c. Containrrent Pressure-High 1 1,2,3 3 D SR SR SR SR 3,3.2.1 3.3,2,6 3.3,2.10 3.3,2.12 4,6 psig d. Pressurizer Pressure-Low 1,2,3(') 4 D SR Sf!. Sil. S.il. 3.3.2.1 3.3,2,6 3,3,2,10 3,3,2,12 ;?: 1817 psig e. Steam .ine Pressure-Low 1,2,J" 3 steam ine D Sf!. Sf!. SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 ;?: 614 psi g:O) 2. Containment Spray a, Manual Initi ati on 1,2,3,4 2 B SR 3,3.2.9 NA b. Automatic Actuation Logi c and Actuation Relays 1,2,3,4 2 trai ns C SR SR SR 3,3,2.4 3.3.2.5 3.3.2.8 NA c. Containment Pressure High-3 1,2,3 4 E SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 21.2 psig (cont i nued ) (a) Above the poll (Pressurizer Pressure) interlock, (b) Time constants used in the lead/lag controller are tJ;?: 50 seconds and t2 5 seconds. BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 Amendment ESFAS Instrumentation
| |
| | |
| ====3.3.2 Table====
| |
| 3.3.2*} (page 2 of 6)Engineered Safety Feature Actuation Instrurrentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREJ.IENTS VALUE 3. Contairr.El1t Isolation Phase A Isolation Mmual 1.2.3,4 2 B SR 3.3.2.9 NA Initiation Autaretic 1.2.3,4 2 trains C SR 3.3.2.4 NA Actuation SR 3.3.2.5 Logic and SR 3.3.2.8 Act-.ation Relays Safety Refer to Function 1 (Safety Injection) for all initiation functions and requirEllllnts.
| |
| Injection Phase B Iso 1 ati on t'anual 1.2,3,4 2 B SR 3.3.2.9 NA Initiation Autaretic 1,2,3,4 2 trains C SR NA Actuation SR Logic and SR Actuation Relays ContaimEnt 1,2,3 4 E SR s 21.2 psig Pressure SR High-3 SR SR (contmuea)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 Amendment 171 ESFAS Instrumentation
| |
| | |
| ====3.3.2 Table====
| |
| 3.3.2-1 (page 3 of 6)Engi neered Safety Feature Actuati on System Instrurrentati on FUNCTION APPLICABLE MODES OR OTHER SPECI FI ED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEI LLANCE REQUIREMENTS ALLOWABLE VALUE 4. Steam Line Isolation
| |
| : a. Manual Initiation 1 ,2 Ic ) ,3 Ic ) 2 F SR 3.3.2.9 NA b. Automatic Actuation Logic and Actuation Rel ays 1 ,2 Ig ) ,3 Ig ) 2 trai ns G SR SR SR 3.3.2.4 3.3.2.5 3.3.2.8 NA c. Contai nment Pressure-High 2 1 ,2 Ig ) ,3 Ig ) 3 o SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 9.4 pSig d. Steam Line Pressure (1) Low 1,2 Ig ),Jla)lfJlg) 3 per steam line o SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 614 psig lb) (2) Negative Rate-High 3 ldll g) 3 per steam 1 ine o SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 165.3 psi Ie) (contl nUed) (a) Above the P-11 (Pressurizer Pressure) interlock. (b) Time constants used in the lead/lag controller are tl 50 seconds and t2 5 seconds. (c) Except when all Main Steam Isolation Valves (MSIVs) are closed. (d) Below the P-11 (Pressurizer Pressure) interlock with Function 4.d.1 blocked. (e) Time constant utilized in the rate/lag controller is 50 seconds. (f) Below the P-11 (Pressurizer Pressure) interlock with Function 4.d.2 not enabled. (g) Except when all Main Steam Isolation Valves (MSIVs) and MSIV bypass valves are closed. BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -14 Amendment 171 ESFAS Instrumentation 3.3.2 4 of 6)Engineered Safety System InstrlJJlentation APPLICABLE MODES OR FUNCTION OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS CONDITIONS SURVEI LLANCE REQUI REMENTS ALLOWABLE VALUE Turbine Trip and Feedwater Isolation Automatic Actuation Logic and Actuation Relays Steam Generator (SG) Water Level-High High (P-14l Unit 1 Unit 2 Safety Injection 1,2 Ih),3!hl 2 trains SR 3.3.2.4 NA SR 3.3.2.5 SR 3.3.2.8 1 ,2 Ih) ,3"') 4 per SG SR 3.3.2.1 S; 89,9% of SR 3.3.2.4 SR 3.3.2.5 SR 3.3.2,6 span SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12 1 ,2,h) .3 1hl 4 per SG SR 3.3.2.1 s; 81.5% of SR 3.3.2.4 narrow range SR 3.3.2.5 instrtFent SR 3.3.2.6 span SR 3.3.2.8 SR 3.3.2.10 SR 3.3.2.12 Refer to Function 1 (Safety I'ljection) for all initiation functions and requirements. ( conti nuec!l Except when all Feedwater Isolation Valves are closed or isolated by a closed manua: valve. BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 Amendment ESFAS Instrumentation
| |
| | |
| ====3.3.2 Table====
| |
| 3.3.2-1 (page 5 of 6)Engineered Safety Feature Actuation System Instrumentation APPLICABLE MODES OR OTHER SPEC! FI ED REQUIRED SURVE I L LANCE ALLOWABLE FUNCTION CONDITIONS CHANNELS CONDITIONS REQUIREMENTS VALUE 6. Auxi 1 i ary Feedwater
| |
| : a. Automatic Actuation Logic and Acbation Relays 1.2,3 2 trains G SR SR SR NA b. SG Water Level-Low LOW 1) Unit 1 1.2,3 4 per SG D SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 16.1% of narrow range instrwent span 2) Unit 2 1,2,3 4 per SG D SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 34.8% of narrow range instrument span c. Safety Injection Refer to Functi on 1 (Safety Injection) for ali i ni ti ati on functions and requi rements. d. Loss of Offsite Power \Undervo ltage on Bus 141( 241)) 1,2.3 2 H SR SR SR " 2730 V e. Undervo 1 tage Reactor Coo 1 ant Purrp (per train) 1,2 4 SR SR SR 4920 V f. Auxiliary Feedwater Purrp Suction Transfer on Suction Pressure-Low 1,2,3 1 per train J SR SR SR " 17.4 psia 7. Switchover to Containment Sump a. Automatic Actuation Logic and Actuation R,elays 1,2,3,4 2 trains C SR SR SR 3.3.2.4 3.3.2.5 3.3.2.8 NA b. Refueling Water Storage Tank (RWSTl Level-Low Low 1,2,3.4 4 K SR SR SR SR 3.3.2.1 3.3.2.6 3.3.2.10 3.3.2.12 44.7% of instrument span Coincident with Safety Injection Refer to Function 1 (Safety Injection) for all initiation functions and requirements.
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 16 Amendment ESFAS Instrumentation
| |
| | |
| ====3.3.2 Table====
| |
| 3.3.2-1 (page 6 of 6) Engineered Safety Feature Actuation System lnstrumentation REQUIRED SURVEI LLANCE ALLOWABLE FUNCTION CHANNELS CONDITIONS REQU I REMENTS VALUE ESFAS Interlocks a, Reactor Trip, P-4 1,2,3 2 per train SR 3.3.2.9 NA Pressuri zer Pr'essure, 1,2,3 2 SR 3.3.2.6 <; 1936 psig P-l1 SR 3.3.2.10 T'.!J-LO<i LO<i. P-12 1,2,3 3 L Sf{ 3.3.2.6 548.O'F Sil. 3.3.2.10 BRAIDWOOD
| |
| -UNITS 1 &2 3.3.2 -Amendment PAM Instrumentation 3.3.3 3.3 INSTRUMENTATION 3.3.3 Post Accident Monitoring (PAM) Instrumentation LCO 3.3.3 APPLICABILITY:
| |
| The PAM instrumentation for each Function in Table 3.3.3-1 shall be OPERABLE.According to Table 3.3.3-1.ACTIONS-------------------NOTE-------------------------------------I Separate Condition entry is allowed for each Function.
| |
| I CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A.1 Enter the Condition Immediately with one or more referenced in required channels Table 3.3.3-1 for the inoperable.
| |
| channel.B. As required by B.1 Restore required 30 days Required Action A.1 channel to OPERABLE and referenced in status.Table 3.3.3-1.C. Required Action and C.1 Initiate action in Imrmediately associated Completion accordance with Time of Condition B Specification 5.6.7.not met.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.3 -1 Amendment 134 PAM Instrumentation
| |
| | |
| ====3.3.3 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. As required by D.1 Restore one required 7 days Required Action A.1 channel. to OPERABLE and referenced in status.Table 3.3.3-1.E. One or more Functions E.1 Restore all but one 7 days with two or more required channel to required channels OPERABLE status.inoperable.
| |
| F. ---------NOTE---------
| |
| F.1 Be in MODE 3. 6 hours Not applicable to Functions 11, 12, and AND 14.F.2 Be in MODE 4. 12 hours Required Action and associated Completion Time of Condition D or E not met.(continued)
| |
| I I I BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.3 -2 Amendment 137 PAM Instrumentation
| |
| | |
| ====3.3.3 ACTIONS====
| |
| (continued)
| |
| CONDITION REQU I RED ACT I ON COMPLETION TIME G. ---------NOTE -------Only applicable to Functions 11, 12, and 14. Required Action and associated Completion Time of Condition D or E not met. G. 1 Initiate action in accordance with Specification
| |
| | |
| ====5.6.7. IrTTTlediately====
| |
| | |
| SURVEILLANCE REQUIREMENTS SR 3.3.3.1 SR 3.3.3.2 apply to each PAM instrumentation Function in Table 3.3.3-1. SURVEI LLANCE FREQUENCY In accordance instrumentation channel that is normally SR Perform CHANNEL CHECK for each required with the energized.
| |
| Surveillance Frequency Control Program SR -------------------
| |
| NOT E-------------------
| |
| Radiation detectors for Function 11, Containment Area Radiation, are excluded.
| |
| In accordance with the Perform CHANNEL CALIBRATION.
| |
| Surveillance Frequency Control Program BRAIDWOOD
| |
| -UN ITS 1 & 2 3.3.3 -Amendment 165/165 PAM Instrumentation
| |
| | |
| ====3.3.3 Table====
| |
| 3.3.3-1 (page 1 of 1)Post Accident Ionitoring Instrurentation
| |
| -nU UIc 1. Reactor Coolant System (RCS) Pressure (Wide Range)2. RES Hot Leg Temperature (Wide Range)3. RCS Cold Leg Teaperature (Wide Range)4. Steam Generator (SG) Water Level (Wide Range)(per SG)5. SG Water Level (Narrow Range)(per SG)6. Pressurizer Water Level (Narrow Range)7. Containment Pressure (Wide Rangej 8. Steam Line Pressure (per SG)9. Refueling Water Storage Tank Water Level 10. Contairment Floor Water Level (Wide Range)11. Containment Area Radiation (High Range)12. Main Steam Line Radiation (per steam line)13. Core Exit Teaperature (per core quadrant)14. Reactor Vessel Water Level APFLIULMLt rPULt OR UOHER SPECIFIED COITIOtS _1,2,3 1.2,3 1,2.3 1,2.3 1,2.3 1,2,3 1,2.3 1,2,3 1.2.3 1,2,3 1,2,3 1,2,3 1.2,3 1,2.3 REWIRED 0'AGMELS 2 2 2 1 1 2 2 2 2 2 1 1 4 2 MIDITIRY6 B B B D D B B B B B D D B B BRAIDWOOD
| |
| -UNITS 1 & 2 3;3.3 -4 Amendment 137 Remote Shutdown System 3.3.4 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.4 Remote====
| |
| Shutdown System LCO 3.3.4 APPLICABILITY:
| |
| The Remote Shutdown System Functions in Table 3.3.4-1 shall be OPERABLE.MODES 1, 2, and 3.ACTIONS--- ------------------
| |
| NOTE------------------------------------
| |
| Separate Condition entry is allowed for each Function.
| |
| I CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Restore required 30 days Functions inoperable.
| |
| Function to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.4 -1 Amendment 134 Remote Shutdown System 3.3.4 SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR SR 3.3.4.1 Perform CHANNEL CHECK for each required instrumentation channel that is normally energized.
| |
| In accordance with the Surveillance Frequency Control Program 3.3.4.2 ---Neutron detectors are excluded from CHANNEL CALIBRATION.
| |
| Perform CHANNEL CALIBRATION for each required instrumentation channel. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.3.4 2 Amendment Remote Shutdown System 3.3.4 Table 3.3.4-1 (Page 1 of 1)Remote Shutdown Monitoring Instrumentation l REQUIRED FUNCTION/INSTRUMENT PARAMETER i NUMBER OF CHANNELS 1. Intermediate Range Neutron Flux 1 2. Source Range Neutron Flux 1 3. Reactor Coolant Temperature
| |
| -Wide Range a. Hot Leg (per loop) 1 b. Cold Leg (per loop) 1 4. Pressurizer Pressure 1 5. Pressurizer Level 1 6. Steam Generator Pressure (per SG) 1 7. Steam Generator Level (per SG) 1 8. Residual Heat Removal Temperature 1 9. Auxiliary Feedwater Flow Rate (per SG) 1 BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.4 -3 Amendment 98
| |
| | |
| ===3.3 INSTRUMENTATION===
| |
| | |
| LOP DG Start Instrumentation 3.3.5 3.3.5 Loss of Power CLOP) Diesel Generator COG) Start Instrumentation LCO 3.3.5 Two channels per bus of the loss of voltage Function, two channels per bus of the degraded voltage Function and two channels per bus of the low degraded voltage Function shall be OPERABLE.
| |
| APPLICABILITY:
| |
| MODES 1, 2, 3, and 4; When associated DG is required to be OPERABLE by LCO 3.8.2, "AC Sources-Shutdown." ACTIONS -------------------------------------NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each Function.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or more Functions A. l --------NOTE---------
| |
| with one channel on For loss of voltage one or more buses Function, the inoperable.
| |
| inoperable channel may be bypassed for up to 2 hours for surveillance testing of the other channel. ---------------------
| |
| Pl ace channel in 1 hour trip. B. One or more Functions B.l Restore one channel 1 hour with two channels on for the Function on one or more buses the affected bus to inoperable.
| |
| OPERABLE status. (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.5 -1 Amendment 188 LOP DG Start Instrumentation
| |
| | |
| ====3.3.5 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.l Enter applicable Immediately associated Completion Condition(s) and Ti me not met. Required Action(s) for the associated DG made inoperable by LOP DG start instrumentation.
| |
| SURVEILLANCE REQUIREMENTS SR 3.3.5.1 SR 3.3.5.2 SURVEILLANCE
| |
| -------------------NOTE--------------------
| |
| Verification of relay setpoints not required.
| |
| Perform TADOT. Perform CHANNEL CALIBRATION with setpoint Allowable Value as follows: a. Loss of voltage Allowable Value 2730 V with a time delay of ::::; 1.9 seconds. b. Degraded voltage Allowable Value 3930 V with a time delay of 310 +/- 30 seconds. c. Low degraded voltage Allowable Value 3196.4 V with a time delay of ::::; 3.5 seconds. FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.5 -2 Amendment 188 Containment Ventilation Isolation Instrumentation 3 3 f 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.6 Containment====
| |
| | |
| Ventilation Isolation Instrumentation LCO 3.3.6 The Containment Ventilation Isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.
| |
| APPLICABILITY:
| |
| According to Table 3.3.6-1. ACTIONS -------------------------------------NOTE-------------------------------------
| |
| Separate Condition entry is allowed for each Function.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One radiation A.1 Restore the affected 4 hours monitoring channel channel to OPERABLE inoperable.
| |
| status. B. One or more automatic B.1 Enter applicable Immediately actuation trains Conditions and inoperable.
| |
| Required Actions of LCD 3.6.3, OR "Containment Isolation Valves," Two radiation for containment purge monitoring channels valves made inoperable.
| |
| inoperable by isolation OR instrumentation.
| |
| Required Action and associated Completion Time of Condition A not met. BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.6-1 Amendment 1 7 8 Containment Ventilation Isolation Instrumentation
| |
| -3.3.6 SURVEILLANCE REQUIREMENTS
| |
| -------------------------------------NOTE-------------------------------------
| |
| Refer to Table 3.3.6-1 to determine which SRs apply for each Containment Ventilation Isolation Function.
| |
| SR 3.3.6.1 SR 3.3.6.2 SR 3.3.6.3 SURVEILLANCE Perform CHANNEL CHECK. --------------NOTE-------------------------
| |
| This Surveillance is only applicable to the actuation logic of the ESFAS Instrumentation.
| |
| Perform ACTUATION LOGIC TEST.
| |
| This Surveillance is only applicable to the master relays of the ESFAS Instrumentation.
| |
| Perform MASTER RELAY TEST. BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.6 -2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
| |
| Amendment 1 7 8 Containment Ventilation Isolation Instrumentation
| |
| | |
| ====3.3.6 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.3.6.4 Perform COT. SR 3.3.6.5 Perform SLAVE RELAY TEST. SR 3.3.6.6 Perform CHANNEL CALIBRATION.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.6-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 1 7 8 FUNCTION 1. Manual Initiation
| |
| -Phase A 2. Manual Initiation
| |
| -Phase B 3. Automatic Actuation Logic and Actuation Relays 4. Containment Radiation-High
| |
| : 5. Safety Injection Containment Ventilation Isolation Instrumentation 3.3.6 Table 3.3.6*1 (page 1 of 1) Containrrent Ventilation Isolation Instrurrentation APPLI 1\BLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS SURVEILLANCE REQUIREMENTS TRIP SETPOINT Refer to LCD 3.3.2, "ESFAS Instrumentation," Function 3.a.1, for all initiation functions and requirerrents.
| |
| Refer to LCD 3.3.2, "ESFAS Instrurrentation," Function 3.b.1, for all i niti ati on functions and requi rerrents.
| |
| 1,2,3,4 2 trains SR 3.3.6.2 SR 3.3.6.3 SR 3.3.6.5 1,2,3,4 2 SR 3.3.6.1 SR 3.3.6.4 SR 3.3.6.6 NA (a) Refer to LCD 3.3.2, "ESFAS Instrurrentation," Function 1, for all initiation functions and requi rements. (a) Trip setpoint shall be established 2 x background in the Containment Building at RTP. BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.6-4 Amendment 1 7 8 VC Filtration System Actuation Instrumentation 3.3.7 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.7 Control====
| |
| Room Ventilation (VC) Filtration System Actuation Instrumentation LCO 3.3.7 APPLICABILITY:
| |
| The VC Filtration System actuation instrumentation for each Function in Table 3.3.7-1 shall be OPERABLE.According to Table 3.3.7-1.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place the redundant 1 hour on one train VC Filtration System inoperable.
| |
| train in normal mode.OR A.2 Place one VC 1 hour Filtration System train in emergency mode.B. One or more channels B.1 Place one VC 1 hour on both trains Filtration System inoperable.
| |
| train in emergency mode.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND or B not met in MODE 1, 2. 3. or 4. C.2 Be in MODE 5. 36 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.7 Amendment 98 VC Filtration System Actuation Instrumentation
| |
| | |
| ====3.3.7 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Condition A or B not met during movement of irradiated fuel assemblies.
| |
| | |
| ===0.1 Suspend===
| |
| movement of i rradi ated fuel assemblies.
| |
| Immediately E. Required Action and associated Completion Time of Condition A or B not met in MODE 5 or 6. E.1 Initiate action to restore one VC Filtration System train to OPERABLE status. Immediately SURVEILLANCE REQUIREMENTS
| |
| ------------
| |
| -----------NOTE----
| |
| Refer to Table 3.3.7 1 to determine which SRs apply for each VC Filtration System Actuation Function.
| |
| SURVEILLANCE FREQUENCY SR 3.3.7.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.7.2 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.7.3 Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 & 2 3.3.7 -2 Amendment ViC Fi L tr,;;ti r-n Sysztent Acatct iWIn Strumm-Ytta t-Icen Table 3.3.7-1 (page I of I*-11C Fil1tration S/staT Actuation lnsAt~rn'aticii APPLICABLE 14Ubt.FUICTION I. Control Rccm Padi ation-C-aseons
| |
| : 2. Sifety Injection OR OTHER SU)RVEI LLANCE T SPECIFIED REOUIRED CHSIMELS REGUIRiErrrS TRIP -EFF CONlDITIONS 1.2,3.4,5,6,(a) 2 per train SR 3.3.7-4l 2 riaI-SR 3.3.7.2 SR 3.3.7.3" Pefer to LCO 3.3.2, "ESFAS lnstrtentaticn," Function 1, for all iniftatioil functions and require-ents.
| |
| 'IT (a) During noverrant of irradiated fuel asseTblies.
| |
| BRAIDWOOD
| |
| -UNITS I & 2 3, 3. 7-3 AT1=nrlm=nf-1 1. t-%1-11ý Lýtv FHB Ventilation System Actuation Instrumentation 3.3.8 3.3 INSTRUMENTATION 3.3.8 Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System Actuation Instrumentation LCO 3.3.8 The FHB Ventilation System actuation each Function in Table 3.3.8-1 shall instrumentation for be OPERABLE.APPLICABILITY:
| |
| According to Table 3.3.8-1.ACTIONS s enYr-- ---nil[ ii I- -----
| |
| II %J I L-LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One channel A.1 Restore channel to 7 days inoperable.
| |
| OPERABLE status.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.3.8 -.1 Amendment 98 FHI V'entilat-ion System A"t- i- "iru 3.3,.ACTIONS (cnrlL I e CONDITION REQUIRED ACTION COMPLETION TIME.B, Required Action and B.1 Place in emergency Ihninediately associated Completion mode one FHB Time not met. Ventilation System train capable of OR being powered by an OPERABLE emergency Two channels power source.inoperabl e.OR B.2.1 Suspend movement of IrmTediately RECENTLY IRRADIATED FUEL assemblies in the fuel handling building.AND B.2.2 ---------
| |
| NOTE-----Only required with equipment hatch not intact.Suspend movement of Irnemdiately RECENTLY IRRADIATED FUEL assemblies in the containment.
| |
| B1\n1.nOD
| |
| -UNITS I & 2 31).3.8 -2 Amendment 14 0 FHB Vent"ilation System Actuation Instrumentation
| |
| | |
| ====3.3.8 SURVEILLANCE====
| |
| | |
| REQUIREMENTS
| |
| ----------
| |
| ------------
| |
| -------NOTE-----------
| |
| ------
| |
| Refer to Table 3.3.8-1 to determine which SRs apply for each FHB Ventilation System Actuation Function.
| |
| SURVEI LLANCE FREQUENCY SR 3.3.8.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.8.2 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.8.3 Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.3.8 3 Amendment FHE 'V Fti 11 -a t '--, % t -em ý ctL18ti on I i r utImic-rl-at!
| |
| Ixn 3.3.8 Table 3.35.81 (page i of 1)FI-EVenti l5ticn Sy:tarn Actuaticn.
| |
| tnstrutentatic-n AP P-E 1-8LL I'IDDCTlr~i NOES OR OTHER fELD rIip STSURVEILLPIICE SPECIFIED P2JIREM REQUIRIEMT5 TRIP SETPOINT CONDITIONS
| |
| : 1. Fuel Handling Building (a),(b) 2 SR 3.3.8.1 _ 5 nP~ir Radiation SR 3.3.8.2 SR 3.3.8.3 2. Safety Injection Refer to LCO 3.3.2, "ESFAS InmtruTmntation," Funmtion I, fcr all initiation functicns and requirements.(a) During mnverrznt of RECENTLY IRRADIATED FUEL assemlies in the fuel handling building.(b) During friveircnt of RECENTLY IRPADIATED FUEL asseffblies in the containmEnt with the cquiprmnt hatch not intact.I I I BPAIDWOOD
| |
| -UNITS 1 0 .. iAedrn 4 3. 3.-8 -4 A -AillEnd-ment T.40 BDPS 3.3.9 3.3 INSTRUMENTATION
| |
| | |
| ====3.3.9 Boron====
| |
| Dilution Protection System (BDPS)LCO 3.3.9 BDPS shall be OPERABLE with: a. One or more reactor coolant pump(s) in operation;
| |
| : b. Each Reactor Coolant System (RCS) loop isolation valve open: and c. The BDPS instrumentation in Table 3.3.9-1 OPERABLE.
| |
| -----------------------
| |
| NOTE --------------------
| |
| The Boron Dilution Alert Alarm may be bypassed in MODE 3 during reactor startup.
| |
| ------------------------------------------
| |
| APPLICABILITY:
| |
| MODES 3, 4, and 5.ACTIONS Unborated water source isolation administrative controls.-----NOTE------
| |
| valves may be unisolated intermittently under CONDITION REQUIRED ACTION COMPLETION TIME A. One Boron Dilution A.1 Restore channel to 72 hours Alert channel OPERABLE status. inoperable. (continued)
| |
| BPRAIDWOOD
| |
| -UNITS I & 2 I 3.3.9-1 Amnendment 111 BDPS 3.3.9 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Close unborated water 1 hour associated Completion source isolation Time of Condition A valves. not met. AND B.2 Verify unborated Once per 31 days water source isolation valves closed. C. Two Boron Dilution C.1 Close unborated water 1 hour Alert channels source isolation inoperable, valves. OR AND No reactor coolant C.2 Perform SR 3.1.1.1. 1 hour pump in operation.
| |
| AND OR Once per One or more RCS loop 12 hours isolation valve(s) not thereafter open. AND C.3 Verify unborated Once per water source 12 hours isolation valves closed.BRAIDWOOD
| |
| -UNITS 1 & 2 I 3.3.9-2 Amendment 111 BOPS 3.3.9 SURVEILLANCE REQUIREMENTS SR 3.3.9.1 SURVEI LLANCE Verify one or more reactor coolant pump(s) -j n operat ion. FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.3.9.2 Verify each RCS loop isolation valve is open. In accordance with the Surveillance Frequency Control Program SR 3.3.9.3 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.3.9.4 Verify each Boron Dilution Alert channel selector switch is in the Normal position.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.3.9.5 Verify each manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
| |
| In accordance with the Surveillance Frequency Control Program (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.3.9 -3 Amendment 165/165 BOPS 3.3.9 SURVEILLANCE (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.3.9.6 Perform COT. In accordance with the Surveillance Frequency Control Program SR 3.3.9.7 The CHANNEL CALIBRATION is only required to include that portion of the channel associated with the Boron Dilution Alert function.
| |
| Perform CHANNEL CALIBRATION.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 & 2 3.3.9 -4 Amendment BOPS 3.3.9 FUNCTION Table 3.3.9-1 Boron Dilution Protection 1 of 1)lnstrurrentation REQUIRED CHANNELS SURVElLLANCE REQUIREMENTS ALLOWABLE VALUE Dilution Alert Channels Volurre Control Tank Level High 2 SR 3.3.9.3 s; 71.15% SR 3.3.9.6 SR 3.3.9.7 BRAIDWOOD UNITS 1 & 2 3.3.9 -Amendment RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 REACTOR COOLANT SYSTEM CRCS) 3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling CDNB) Limits LCO 3.4.1 RCS DNB parameters for pressurizer pressure, RCS average temperature CTavg_) , and RCS total flow rate shall be within the limits spec1fied below: a. Pressurizer pressure within the limit specified in the COLR; b. RCS average temperature within the limit specified in the COLR; and c. RCS total flow 386,000 gpm and within the limit specified in the COLR. ----------------------------NOTE----------------------------
| |
| Pressurizer pressure limit does not apply during: a. THERMAL POWER ramp> 5% RTP per minute; or b. THERMAL POWER step> 10% RTP. APPLICABILITY:
| |
| MODE 1. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more RCS DNB A.1 Restore RCS DNB 2 hours not within imits. parameter(s) to within limit. B. Required Action and associated Completion B.1 Be in MODE 2. 6 hours Time not met. BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.1-1 Amendment No. 17 4 RCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SR 3.4.1.1 SR 3.4.1.2 SR 3.4.1.3 SR 3.4.1.4 SURVEILLANCE Verify pressurizer pressure is within the limit specified in the COLR. Verify RCS average temperature is within the limit specified in the LOLR. Verify RCS total flow rate 386,000 gpm and within the limit specified in the COLR. -------------------NOTE--------------------
| |
| Not required to be performed until 7 days after 90% RTP. Verify by precision heat balance that RCS total flow rate is 386,000 gpm and within the limit specified in the COLR. BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.1-2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 174 RCS Minimum Temperature for Criticality 3.4.2 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.2 RCS Min-imum Temperature for LCO 3.4.2 Each RCS loop average temperature shall be MODE 1, MODE 2 with keff 1. 0 . ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Tavg in one or more loops not within 1 i mi t. ReS A.l Be in MODE 2 with keff < 1.0. 30 minutes SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.4.2.1 Veri fy RCS in each 1 oop 550°F. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.4.2 Amendment RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.3 RCS Pressure and Temperature (P/T) Limits LCO 3.4.3 APPLICABILITY:
| |
| RCS pressure.
| |
| RCS temperature, and RCS heatup and cooldown rates shall be maintained within the limits specified in the PTLR.At all times.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. ----NOTE--- A.1 Restore parameter(s) 30 minutes Required Action A.2 to within limits.shall be completed whenever this AND Condition is entered._ A.2 Determine RCS is 72 hours acceptable for Requirements of LCO continued operation.
| |
| not met in MODE 1. 2.3, or 4.B.. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 5. 36 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.3 -.1 Amendment 98 RCS PIT Limits 3.4.3 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. -----NOTE --Required Action C.2 shall be completed whenever this Condition is entered. C. 1 AND Initiate action to restore parameter(s) to within limits. Immediately Requirements of LCO not met any time other than in MODE 1, 2, 3, or 4. C.2 Determine RCS is acceptable for continued operation.
| |
| Prior to entering MODE 4 SURVEILLANCE SR 3.4.3.1 -----------------NOTE---
| |
| ---
| |
| Only requ"i red to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing. Verify RCS pressure, RCS temperature, and RCS heatup and cool down rates are within the limits specified in the PTLR.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.4.3 -2 Amendment RCS Loops-MODES 1 and 2 3.4.4 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.4 RCS Loops-MODES 1 and LCO 3.4.4 Four RCS loops shall be OPERABLE and in APPLICABILITY:
| |
| MODES 1 and 2. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of LCD not met. A.1 Be in MODE 3. 6 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.4.1 Verify each RCS loop is in operation.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.4 1 Amendment RCS Loops- MODE 3 3.4.5 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.5 RCS Loops- MODE 3 LCO 3.4.5 Two RCS loops shall be OPERABLE, and either: a. Two OPERABLE RCS loops shall be in operation when the Rod Control System is capable of rod withdrawal; or b. One OPERABLE RCS loop shall be in operation when the Rod Control System is not capable of rod withdrawal.
| |
| ~~- ---NOTE----
| |
| --------------
| |
| All reactor coolant pumps may be removed from operation for< 1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration:
| |
| and b. Core outlet temperature is maintained 2 10 0 F below saturation temperature.
| |
| APPLICABILITY:
| |
| MODE 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required RCS loop A.1 Place the Rod Control 1 hour not in operation with System in a condition Rod Control System incapable of rod capable of rod withdrawal.
| |
| withdrawal.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.5 -.1 Amendment 98 RCS Loops -MODE 3 3.4.5 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. No required RCS loop B.1 Suspend all Immediately in operation with Rod operations involving Control System not a reduction of RCS capable of rod boron concentration.
| |
| withdrawal.
| |
| AND B.2 Initiate action to Immediately restore one RCS loop to operation.
| |
| C. Two required RCS loops C.1 Initiate action to Immediately not in operation with place the Rod Control Rod Control System System in a condition capable of rod incapable of rod withdrawal.
| |
| withdrawal.
| |
| OR AND Required Action and C.2 Suspend all Immediately associated Completion operations involving Time of Condition A a reduction of RCS not met. boron concentration.
| |
| AND C.3 Initiate action to Immediately restore RCS loop(s)to operation.
| |
| D. One required RCS loop D.1 Restore required RCS 72 hours inoperable.
| |
| loop to OPERABLE status.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.5 -2 Amendment
| |
| : 98.
| |
| RCS Loops-MODE 3 3.4.5 ACTIONS (continued)
| |
| CONDITION REQU I RED ACT ION COMPLETION TIME E. Required Action and associated Completion Time of Condition D not met. E.1 Be in MODE 4. 12 hours F. Two required RCS loops inoperable.
| |
| F.1 AND F.2 AND F.3 Initiate action to place the Rod Control System in a condition incapable of rod withdrawal.
| |
| Suspend all operations involving a reduction of RCS boron concentration.
| |
| Initiate action to restore one RCS loop to OPERABLE status. Imnediately Imnediately Imnediately SURVEILLANCE SR 3.4.5.1 Verify each required RCS loop is in operation.
| |
| In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.5 -3 Amendment RCS Loops-MODE 3 3.4.5 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.4.5.2 Verify steam generator secondary side narrow range water level is 18% for each required ReS loop. In accordance with the Surveillance Frequency Control Program SR 3.4.5.3 Verify correct breaker alignment and indicated power are available to each required pump that is not in operation.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.5-4 Amendment RCS Loops- MODE 4 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.6 RCS Loops -MODE 4 LCO 3.4.6 Two loops consisting of any combination of RCS loops and Residual Heat Removal (RHR) loops shall be OPERABLE, and one OPERABLE loop shall be in operation.
| |
| --- -NOTES- --- --------1. All Reactor Coolant Pumps (RCPs) and RHR pumps may be removed from operation for s 1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration; and b. Core outlet temperature is maintained
| |
| ; 10OF below saturation temperature.
| |
| : 2. No RCP shall be started with any RCS cold leg temperature
| |
| < 350 0 F unless the secondary side water temperature of each Steam Generator (SG) is < 50 0 F above each of the RCS cold leg temperatures.
| |
| APPLICABILITY:
| |
| MODE 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No required loop in A.1 Suspend all Immediately operation.
| |
| operations involving a reduction in RCS boron concentration.
| |
| AND A.2 Initiate action to Immediately restore one loop to operation.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.6-.1 Amendment
| |
| : 98.
| |
| RCS Loops MODE 4 3.4.6 ACTIONS (continued)
| |
| CONDITION REQUI RED ACTI ON COMPLETION TIME B. One required loop inoperable.
| |
| B.1 AND B.2 Initiate action to restore a second loop to OPERABLE status.
| |
| Only required if RHR loop is OPERABLE.
| |
| ---Be in MODE 5. Irrmediately 24 hours C. Two required loops inoperable.
| |
| C.1 AND C.2 Suspend all operations involving a reduction of RCS boron concentration.
| |
| Initiate action to restore one loop to OPERABLE status. Irrmediately Ilmedi ately SURVEI LLANCE SR 3.4.6.1 SURVEILLANCE Verify required RHR or operation.
| |
| RCS loop is in FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.4.6.2 Verify SG secondary side narrow range water level is 18% for each required RCS loop. In accordance with the Survei 11 ance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.4.6 -2 Amendment SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.4.6.3 SR 3.4.6.4 SURVEILLANCE Verify correct breaker alignment and indicated power are available to each required pump that is not in operation.
| |
| -------------------NOTE--------------------
| |
| Not required to be performed until 12 hours after entering MODE 4. Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water. RCS Loops-MODE 4 3.4.6 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.6 -3 Amendment No. 183 RCS Loops- MODE 5. Loops Filled 3.4.7 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.7 RCS Loops -MODE 5, Loops Filled LCO 3.4.7 One Residual Heat Removal (RHR) loop shall be OPERABLE and in operation, and either: a. One additional RHR loop shall be OPERABLE:
| |
| or b. The secondary side water level of at least two Steam Generators MSGs) shall be > 18%.-- --NOTES-- -------------
| |
| : 1. The RHR pump may be removed from operation for 5 1 hour per 8 hour period provided: a. No operations are permitted that would cause reduction of the RCS boron concentration:
| |
| and b. Core outlet temperature is maintained 2 10 0 F below saturation temperature.
| |
| : 2. One required RHR loop may be inoperable for s 2 hours for surveillance testing provided that the other RHR loop is OPERABLE and in operation.
| |
| : 3. No reactor coolant pump shall be started with any RCS cold leg temperature s 350 0 F unless the secondary side water temperature of each SG is < 50 0 F above each of the RCS cold leg temperatures.
| |
| : 4. All RHR loops may be removed from operation during.planned heatup to MODE 4 when at least one RCS loop is in operation.
| |
| APPLICABILITY:
| |
| MODE 5 with RCS loops filled.BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.7 -1 Amendment 98 RCS Loops -MODE 5. Loops Filled 3.4.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No required RHR loop A.1 Suspend all Immediately in operation.
| |
| operations involving a reduction in RCS boron concentration.
| |
| AND A.2 Initiate action to Immediately restore one RHR loop to operation.
| |
| B. One required RHR loop B.1 Initiate action to Immediately inoperable.
| |
| restore required RHR loop to OPERABLE status.C. One or both required C.1 Initiate action to Immediately SG secondary side restore required SG water level(s) not secondary side water within limits. level(s) to within limits.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.7 -2 Amendment 98 RCS Loops-MODE 5, Loops Filled 3.4. 7 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION D. Two required RHR loops D.1 Suspend all inoperable.
| |
| operations involving a reduction of RCS OR boron concentration.
| |
| Required RHR loop AND inoperable and one or both required SG D.2.1 Initiate action to secondary side water restore one RHR loop level Cs) not within to OPERABLE status. limits. OR D.2.2 Initiate action to restore required SG secondary side water level Cs) to within limits. SURVEILLANCE REQUIREMENTS SR 3.4.7.1 SR 3.4. 7 .2 SR 3.4.7.3 SURVEILLANCE Verify required RHR loop is in operation.
| |
| Verify SG secondary side narrow range water level is 18% in required SGs. Verify correct breaker alignment and indicated power are available to each required RHR pump that is not in operation.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.7 -3 COMPLETION TIME Immediately Immediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
| |
| Amendment No. 183 RCS Loops-MODE 5, Loops Filled 3.4.7 SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.4.7.4 SURVEILLANCE Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water. BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.7 -4 FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment No. 183 RCS Loops- MODE 5. Loops Not Filled 3.4.8 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.8 RCS Loops -MODE 5. Loops Not Filled LCO 3.4.8 Two Residual Heat Removal one OPERABLE RHR loop shal (RHR) loops shall be OPERABLE and 1 be in operation.
| |
| l I^T=tv_slrl l_- * .n -.----_ _ _ _ _ _ _ _ _-1. All RHR pumps may be removed from operation for < 1 provided: hour a. No operations are permitted that would cause a reduction of the RCS boron concentration:
| |
| : b. The core outlet temperature is maintained 2 10OF below saturation temperature:
| |
| and c. No draining operations are permitted that would further reduce the RCS water volume.2. One RHR loop surveillance OPERABLE and may be inoperable for 5 2 hours for testing provided that the other RHR loop is in operation.
| |
| APPLICABILITY:
| |
| MODE 5 with RCS loops not filled.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. No required RHR loop A.1 Suspend all Immediately in operation.
| |
| operations involving a reduction in RCS boron concentration.
| |
| AND A.2 Initiate action to Immediately restore one RHR loop to operation.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.8- 1 Amendment 98 RCS Loops-MODE 5, Loops Not Filled 3.4.8 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. One required RHR loop inoperable.
| |
| C. Two required RHR loops inoperable.
| |
| B.1 C.1 AND C.2 Initiate action to RHR loop to OPERABLE status. Suspend all operations involving reduction in RCS boron concentration.
| |
| Initiate action to restore one RHR loop to OPERABLE status. IfllTlediately IfllTlediately IfllTlediately SURVET LLANCE REQUI SURVEILLANCE FREQUENCY SR 3.4.8.1 Verify required RHR loop is in operation.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.4.8.2 Verify correct breaker alignillent and indicated power are available to each required RHR pump that is not in operation.
| |
| In accordance with the Survei 11 ance Frequency Control Program BRAIDWOOD 1 & 2 3.4.8 -2 Amendment 165/165 Pressurizer 3.4.9 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.9 Pressurizer LCO 3.4.9 The pressurizer shall be OPERABLE with: a. Pressurizer water level < 92%: and b. Two groups of pressurizer heaters OPERABLE with the capacity of each group 2 150 kW and capable of being powered from redundant Engineered Safety Features (ESF)power supplied buses.APPLICABILITY:
| |
| MODES 1, 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Pressurizer water A.1 Be in MODE 3. 6 hours level not within limit. AND A.2 Fully insert all 6 hours rods.AND A.3 Place Rod Control 6 hours System in a condition incapable of rod withdrawal.
| |
| AND A.4 Be in MODE 4. 12 hours B. One or more required B.1 Restore required 72 hours groups of pressurizer groups of pressurizer heaters inoperable.
| |
| heaters to OPERABLE status.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.9 -1 Amendment 98 Pressurizer
| |
| | |
| ====3.4.9 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and associated Completion Time of Condition B not met. C.1 AND C.2 Be in MODE 3. Be in MODE 4. 6 hours 12 hours SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.4.9.1 Verify pressurizer water level is 92%. In accordance*
| |
| with the Surveillance Frequency Control Program SR 3.4.9.2 Verify capacity of each required group of pressurizer heaters is 2 150 kW. In accordance with the Surveillance Frequency Control Program SR 3.4.9.3 Veri fy requ"j red pressuri zer heaters are capable of being powered from an ESF power supply. In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.9 2 Amendment Pressurizer Safety Valves 3.4.10 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.10 Pressurizer Safety Valves LCO 3.4.10 Three pressurizer safety valves shall be OPERABLE with lift settings 2 2411 psig and < 2509 psig.I----------------------
| |
| NOTE----------------------
| |
| The lift settings are not required to be within the LCO limits during MODE 3 for the purpose of setting the pressurizer safety valves under ambient (hot) conditions.
| |
| This exception is allowed for 54 hours following entry into MODE 3 provided a preliminary cold setting was made prior to heatup.APPLICABILITY:
| |
| MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One pressurizer safety A.1 Restore valve to 15 minutes valve inoperable.
| |
| OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND OR B.2 Be in MODE 4. 12 hours Two or more pressurizer safety valves inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.10 -I Amendment 131 Pressurizer Safety Valves 3.4.10 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.10.1 Verify each pressurizer safety valve is In accordance OPERABLE in accordance with the Inservice with the Testing Program. Following testing. lift Inservice settings shall be within +/- 1%. Testing Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.10 -2 Amendment 98 Pressurizer PORVs 3.4.11 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.11 Pressurizer Power Operated Relief Valves (PORVs)LCO 3.4.11 Each PORV and associated block valve shall be OPERABLE.APPLICABILITY:
| |
| MODES 1, 2, and 3.ACTIONS-------------------------------------
| |
| NOTE------------------------------------
| |
| Separate Condition entry is allowed for each PORV and each block valve.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more PORVs A.1 Close and maintain 1 hour inoperable and capable. Power to associated of being manually block valve.cycled.B. One PORV inoperable B.1 Close associated 1 hour and not capable of block valve.being manually cycled. AND B.2 Remove power from 1 hour associated block valve.AND B.3 Restore PORV to 72 hours OPERABLE status.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.11 -1 Amendment 134 Pressurizer PORVs 3.4.11 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. One block valve C.1 Place associated PORV 1 hour inoperable.
| |
| in manual control.AND C.2 Restore block valve 72 hours to OPERABLE status.D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time of Condition A. AND B. or C not met.D.2 Be in MODE 4. 12 hours E. Two PORVs inoperable E.1 Be in MODE 3. 6 hours and not capable of being manually cycled. AND E.2 Be in MODE 4. 12 hours F. Two block valves F.1 Restore one block 2 hours inoperable.
| |
| valve to OPERABLE status.G. Required Action and G.1 Be in MODE 3. 6 hours associated Completion Time of Condition F AND not met.G.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.11 -2 Amendment 98 Pressurizer PORVs 3.4.11 SURVEILLANCE REQUIREMENTS SLiRVEI LLANCE FREQUENCY SR 3.4.11.1 Not required to be met with block valve closed in accordance with the Required Action of Condition B or E. Perform a complete cycle of each block valve. In accordance with the Surveillance Frequency Control Program SR 3.4.11.2 Only required to be performed in MODES 1 and 2. Perform a complete cycle of each PORV. In accordance with the Surveillance Frequency Control Program SR 3.4.11.3 Perform a complete cycle of each solenoid air control valve and check valve on the air accumulators in PORV control systems. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.4.11 3 Amendment LTOP System 3.4.12 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.12 Low Temperature Overpressure Protection (LTOP) System LCO 3.4.12 An LTOP System shall be OPERABLE with: a. A maximum of one charging pump (centrifugal) capable of injecting into the RCS; b. No Safety Injection (S1) pumps capable of inject-ing into the RCS; c. Each SI accumulator isolated, whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the PIT limit curves provided in the PTLR; and d. One of the following pressure relief capabilities:
| |
| : 1. Two Power Operated Relief Valves (PORVs) with lift settings within the limits specified in the PTLR, 2. Two Residual Heat Removal (RHR) suction relief valves with setpoints 450 psig, 3. One PORV with a lift setting within the limits specified in the PTLR and one RHR suction relief valve with a setpoint 450 psig, or 4. The RCS depressurized and an RCS vent of 2.0 square inches. ----------------------------NOTES------------------1. Operation in MODE 4 with all SI pumps and charging pumps capable of injecting into the RCS is allowed when all RCS cold legs exceed 330°F. 2. For the purpose of protecting the decay heat removal function, one or more SI pumps may be capable of injecting into the RCS in MODE 5 and MODE 6 when the reactor vessel head is on provided pressurizer level is 5 percent. APPLICABILITY:
| |
| MODES 4 and 5, MODE 6 when the reactor vessel head is on. BRAIDWOOD
| |
| -UNITS 1 &2 3.4.12 -1 Amendment 167 LTOP System 3.4.12 ACTIONS LCO 3.0.4.b is not applicable when entering MODE 4.I CONDITION REQUIRED ACTION COMPLETION TIME A. Two charging pumps A.1 ---------NOTE--------(centrifugal) capable Two charging pumps of injecting into the may be capable of RCS. injecting into the RCS during pump swap OR operation for< 15 minutes.One charging pump (positive displacement) capable Initiate action to Immediately of injecting into the verify a maximum of RCS. one charging pump (centrifugal) is capable of injecting into the RCS.B. One or more SI pumps B.1 Initiate action to Immediately capable of injecting verify no SI pumps into the RCS. are capable of injecting into the RCS.C. An accumulator not C.1 Isolate affected 1 hour isolated when the accumulator.
| |
| accumulator pressure is greater than or equal to the maximum RCS pressure for existing cold leg temperature allowed in the PTLR.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.12 -2 Amendment 134 LTOP System 3.4.12 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.1 Depressurize affected 12 hours associated Completion accumulator to less Time of Condition C than the maximum RCS not met. pressure for existing cold leg temperature allowed in the PTLR.E. One required RCS E.1 Restore required RCS 7 days relief valve relief valve to inoperable in MODE 4. OPERABLE status.F. One required RCS F.1 Restore required RCS 24 hours relief valve relief valve to inoperable in MODE 5 OPERABLE status.or MODE 6 when the reactor vessel head is on.G. Two required RCS G.1 Depressurize RCS and 8 hours relief valves establish RCS vent of inoperable.
| |
| 2 2.0 square inches.OR Required Action and associated Completion Time of Condition D.E, or F not met.OR LTOP System inoperable for any reason other than Condition A. B.C. D, E. or F.BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.12 -3 Amendment 98 LTOP System 3.4 .12 SURVEI LLANCE REQUI REMENTS SR 3.4.12.1 SURVEILLANCE Verify no SI pump is capable of injecting into the RCS. FREQUENCY In accordance with the Surveil 1 ance Frequency Control Program SR 3.4.12.2 Verify a maximum of one charging pump (centrifugal) is capable of injecting into the RCS. In accordance with the Surveillance Frequency Control Program SR 3.4.12.3 Only required to be met for accumulator whose pressure is greater than or equal to the maximum RCS pressure for the existing RCS cold leg temperature allowed by the PIT limit curves provided in the PTLR. Verify each accumulator is isolated.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.4.12.4 Verify required RCS vent? 2.0 square inches open. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.4.12-4 Amendment LTOP System 3.4.12 SURVEI LLANC E REOU IREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.4.12.5 Verify RHR suction valves are open for each In accordance required RHR suction relief valve. with the Surveillance Frequency Control Program SR 3.4.12.6 Verify PORV block valve is open for each In accordance requi red PORV. with the Survei 11 ance Frequency Control Program SR 3.4.12.7 ---------------NOTE--------------Not required to be performed until 12 hours after decreasing RCS cold leg temperature to 350°F. Perform a COT on each required PORV, In accordance excluding actuation.
| |
| with the Surveillance Frequency Control Program SR 3.4.12.8 Perform CHANNEL CALIBRATION for each In accordance required PORV actuation channel. with the Survei 11 ance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.12-5 Amendment RCS Operational LEAKAGE 3.4.13 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.13 RCS Operational LEAKAGE LCO 3.4.13 RCS operational LEAKAGE shall be limited to: a. No pressure boundary LEAKAGE;b. 1 gpm unidentified LEAKAGE;c. 10 gpm identified LEAKAGE; and d. 150 gallons per day primary to secondary LEAKAGE through any one steam generator (SG).I APPLICABILITY:
| |
| MODES 1, 2, 3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RCS operational A.1 Reduce LEAKAGE to 4 hours LEAKAGE not within within limits.limits for reasons other than pressure boundary LEAKAGE or primary to secondary LEAKAGE.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 5. 36 hours OR Pressure boundary LEAKAGE exists.OR Primary to secondary LEAKAGE not within limit.BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.13 -1 Amendment144 RCS Operational LEAKAGE 3.4.13 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.13.1 ----------------
| |
| : 1. Not requi red to be performed Lint i 1 12 hours after establishment of steady state operation.
| |
| : 2. Not applicable to primary to secondary LEAKAGE. Verify RCS operational LEAKAGE is within In accordance limits by performance of RCS water with the inventory balance. Surveillance Frequency Control Program SR 3.4.13.2 -------------NOTE----------Not required to be performed until 12 hours after establishment of steady state Verify primary to secondary LEAKAGE In accordance 150 gallons per day through anyone SG. with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.13 -2 Amendment RCS PIV Leakage 3.4.14 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.14 RCS Pressure Isolation Valve (PIV) Leakage LCO 3.4.14 APPLICABILITY:
| |
| Leakage from each RCS PIV shall be within limits.MODES 1. 2. 3. and 4.ACTIONS-- NOTES--- ------ ----------
| |
| -1. Separate Condition entry is allowed for each flow path.2. Enter applicable Conditions and Required Actions for systems made inoperable by an inoperable PIV.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more flow paths --NOTE with leakage from one Each valve used to satisfy or more RCS PIVs not Required Action A.1 and within limit. Required Action A.2 must have been verified to meet SR 3.4.14.1 and be in the reactor coolant pressure boundary or the high pressure portion of the system.A.1 Isolate the high 4 hours pressure portion of the affected system from the low pressure portion by use of one closed manual.de-energized power operated.de-activated automatic.
| |
| or check valve.AND (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.14- 1 Amendment 98 RCS PIV Leakage 3.4.14 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2 Isolate the high 72 hours pressure portion of the affected system from the low pressure portion by use of a second closed manual.de-energized power operated.de-activated automatic, or check valve.B. Residual Heat Removal B.1 Isolate the affected 4 hours (RHR) System suction flow path by use of isolation valve one de-energized interlock function power operated valve.inoperable.
| |
| C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.14 -2 Amendment 98 SURVEILLANCE SR 3.4.14.1
| |
| : 1. Only required to be performed in MODES 1 and 2. 2. RCS PIVs actuated during the performance of this Surveillance are not required to be tested more than once if a repetitive testing loop cannot be avoided. 3. Not required to be performed for RH8701A and Band RH8702A and B on the Frequency required following valve actuation or flow through the valve. Verify leakage from each RCS PIV is equivalent to 0.5 gpm per nominal inch of valve size up to a maximum of 5 gpm at an RCS pressure 2215 psig and 2255 psig. RCS PIV Leakage 3.4.14 In accordance with the Inservice Testing Program, and in accordance with the Surveillance Frequency Control Program AND Prior to entering MODE 2 whenever the unit has been in MODE 5 for 7 days, if leakage testing has not been performed once within the previous 9 months (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.4.14 -3 Amendment RCS PIV Leakage 3.4 .14 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.14.1 (continued)
| |
| Within 24 hours following valve actuation due to automatic or manual action or flow through the valve SR 3.4.14.2 Verify RHR System suction isolation valve interlock prevents the valves from being opened with a simulated or actual RCS pressure signal 360 psig. In accordance with the Surveil 1 ance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.4.14-4 Amendment RCS Leakage Detection Instrumentation 3.4.15 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.15 RCS Leakage Detection Instrumentation LCO 3.4.15 The following RCS leakage detection instrumentation shall be OPERABLE:
| |
| : a. One containment sump monitor; and b. One containment atmosphere radioactivity monitor (gaseous or particulate).
| |
| APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION A. Required containment sump monitor inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 A.1 AND A.2 REQU I RED ACTION Not required to be performed until 12 hours after establishment of steady state operation.
| |
| Perform SR 3.4.13.1.
| |
| Restore required containment sump monitor to OPERABLE status. 3.4.15-1 COMPLETION TIME Once per 24 hours 30 days (continued)
| |
| Amendment No. 179 ACTIONS (continued)
| |
| CONDITION B. Required containment atmosphere radioactivity monitor inoperable.
| |
| C. ---------NOTE--------
| |
| Only applicable when the containment atmosphere gaseous radioactivity monitor is the only OPERABLE monitor. ---------------------
| |
| Required containment sump monitor inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 B.l.1 OR B.l.2 AND B.2 C.1 AND C.2 RCS Leakage Detection Instrumentation 3.4.15 REQUIRED ACTION COMPLETION TIME Analyze grab samples Once per 24 of the containment hours atmosphere.
| |
| ---------NOTE--------
| |
| Not required to be performed until 12 hours after establishment of steady state operation.
| |
| ---------------------
| |
| Perform SR 3.4.13.1.
| |
| Once per 24 hours Restore required 30 days containment atmosphere radioactivity monitor to OPERABLE status. Analyze grab samples Once per 12 of the containment hours atmosphere.
| |
| Restore required 7 days containment sump monitor to OPERABLE status. (contlnued) 3.4.15-2 Amendment No. 179 RCS Leakage Detection Instrumentation 3.4 .15 ACTIONS (continued)
| |
| D. Required Action and D.1 Be in MODE 3. associated Completion Time not met. AND D.2 Be in MODE 5. E. All required monitors E.1 Enter LCD 3.0.3. inoperable.
| |
| SURVEILLANCE REQUIREMENTS SR 3.4.15.1 SR 3.4.15.2 SR 3.4.15.3 SR 3.4.15.4 SURVEILLANCE Perform CHANNEL CHECK of the required containment atmosphere radioactivity monitor. Perform COT of the required containment atmosphere radioactivity monitor. Perform CHANNEL CALIBRATION of the required containment sump monitor. Perform CHANNEL CALIBRATION of the required containment atmosphere radioactivity monitor. BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.15-3 6 hours 36 hours Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 179 RCS Specific Activity 3.4 .16 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.16 RCS Specific Activity LCO 3.4.16 RCS DOSE EQUIVALENT 1-131 and DOSE EQUIVALENT XE-133 specific activity shall be within limits. APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. CONDITION REQU I RED ACTI ON COMPLETION TIME A. DOSE EQUIVALENT 1-131 not within limit.
| |
| LCO 3.0.4.c is applicable.
| |
| A.1 Verify DOSE EQUIVALENT 1-131 60 J.tCi/gm.
| |
| AND A.2 Restore DOSE EQUIVALENT 1-131 specific activity to withi n 1 imit. Once per 4 hours 48 hours B. DOSE EQUIVALENT XE-133 not within limit.
| |
| LCO 3.0.4.c is applicable.
| |
| | |
| ===8.1 Restore===
| |
| DOSE EQUIVALENT XE-133 to within 1 imit. 48 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.16 -1 Amendment RCS Specific Activity 3.4.16 ACTI ONS (cont i nued ) CONDITION REQUI RED ACTION COMPLETIDN TIME C. Required Action and associated Completion Time of Condition A or B not met. OR DOSE EQUIVALENT I 131 > 60 ),tCi/gm.
| |
| C.1 AND C.2 Be in MODE 3. Be in MODE 5. 6 hours 36 hours SURVEILLANCE SR SR 3.4.16.1 3.4.16.2 SURVEILLANCE Verify reactor coolant DOSE EQUIVALENT XE-133 specific activity 603 ).tCi/gm.
| |
| Verify reactor coolant DOSE EQUIVALENT 1-131 specific activity 1.0 ),tCi/gm.
| |
| FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Between 2 and 6 hours after a THERMAL POWER change of 15% RTP withi n a 1 hour period BRAIDWOOD UNITS 1 &2 3.4.16 -2 Amendment RCS Loop Isolation Valves 3.4.17 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.17 RCS Loop Isolation Valves LCO 3.4.17 APPLICABILITY:
| |
| Each RCS hot and cold leg loop isolation valve shall be open with power removed from each isolation valve operator.MODES 1. 2. 3. and 4.ACTIONS Separate Condition entry is allowed-NOTE- --for each RCS loop isolation valve.CONDITION REQUIRED ACTION COMPLETION TIME A. Power available to one A.1 Remove power from 30 minutes or more loop isolation loop isolation valve valve operators.
| |
| operators.
| |
| B. ---NOTE B.1 Maintain valve(s) Immediately All Required Actions closed.shall be completed whenever this AND Condition is entered.B.2 Be in MODE 3. 6 hours One or more RCS loop AND isolation valves closed. B.3 Be in MODE 5. 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.17 -1 Amendment 98 RCS Loop Isolation Valves 3,4,17 SURVEI LLANCE SURVEI SR 3.4,17.1 Verify each RCS loop isolation valve is open and power is removed from each loop isolation valve operator.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3,4,17 -2 Amendment RCS Loops-Isolated 3.4.18 3.4 REACTOR COOLANT SYSTEM (RCS)3.4.18 RCS Loops-Isolated LCO 3.4.18 Each RCS isolated loop shall remain isolated with: a. The hot and cold leg loop stop isolation valves closed if boron concentration of the isolated loop is less than the required SDM boron concentration of the unisolated portion of the RCS: and b. The cold leg loop stop isolation valve closed if the cold leg temperature of the isolated loop is > 20 0 F below the highest cold leg temperature of the unisolated portion of the RCS.APPLICABILITY:
| |
| MODES 5 and 6.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Isolated loop hot or A.1 Close hot and cold Immediately cold leg isolation leg isolation valves.valve open with boron concentration requirement not met.B. Isolated loop cold leg B.1 Close cold leg Immediately isolation valve open isolation valve.with temperature requirement not met.BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.18 -1 Amendment 98 RCS Loops-Isolated 3.4.18 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.18.1 Verify cold leg temperature of isolated Within loop is.s 20 0 F below the highest cold leg 30 minutes temperature of the unisolated portion of prior to the RCS. opening the cold leg isolation valve in the isolated loop SR 3.4.18.2 Verify boron concentration of isolated loop Within 4 hours is greater than or equal to the required prior to SDM boron concentration of the unisolated opening the hot portion of the RCS. or cold leg isolation valve in the isolated loop BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.18 -2 Amendment 98 SG Tube Integrity 3.4 .19 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.19 Steam Generator (SG) Tube Integrity LCO SG tube integrity shall be maintained.
| |
| AND All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with the Steam Generator Program.
| |
| MODES 1, 2, 3, and 4. ACTIONS ----------------
| |
| ---------------NOTE---------------------------------Separate Condition entry is allowed for each SG tube. CONDITION REQUIRED ACTION COMPLETION TIME A. One or more SG tubes satisfying the tube plugging criteria and not plugged in accordance with the Steam Generator Program. A.1 AND Verify tube integrity of the affected tube(s) is maintained until the next refueling outage or SG tube inspection.
| |
| 7 days A.2 Plug the affected tube(s) in accordance with the Steam Generator Program. Prior to entering MODE 4 following the next refueling outage or SG tube inspection B. Required Action and associated Completion Time of Condition A not met. B.1 AND Be in MODE 3. 6 hours OR B.2 Be in MODE 5. 36 hours SG tube integrity not maintained.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.4.19 Amendment 172/172 SG Tube Integrity 3.4.19 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.19.1 Verify SG tube integrity in accordance with the Steam Generator Program. In accordance with the Steam Generator Program SR 3.4.19.2 Verify that each inspected SG tube that satisfies the tube plugging criteria is plugged in accordance with the Steam Generator Program. Prior to entering MODE 4 following a SG tube inspection BRAIDWOOD
| |
| -UNITS 1 &2 3.4.19 -2 Amendment 172/172 Accumulators 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.1 Accumulators LCO 3.5.1 Four ECCS accumulators shall be OPERABLE.APPLICABILITY:
| |
| MODES 1 and MODE 3 with> 1000 2., Reactor Coolant System (RCS) pressure psig.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One accumulator A.1 Restore boron 72 hours inoperable due to concentration to boron concentration within limits.not within limits.B. One accumulator B.1 Restore accumulator 1 hour inoperable for reasons to OPERABLE status.other than Condition A.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND or B not met.C.2 Reduce RCS pressure 12 hours to 5 1000 psig.D. Two or more D.1 Enter LCO 3.0:.3. Immediately accumulators inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.1 -1 Amendment 98 Accumulators
| |
| | |
| ====3.5.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.1.1 Verify each accumulator isolation valve is fully open. In accordance with the Surveillance Frequency Contro 1 Program SR 3.5.1.2 Verify borated water level in each accumulator is 31% and 63%. In accordance with the Surveillance Frequency Control Program SR 3.5.1.3 Verify nitrogen cover pressure in each accumulator is 602 psig and 647 psig. In accordance with the Surveillance Frequency Control Program SR 3.5.1.4 Verify boron concentration -i n each accumulator is 2200 ppm and 2400 ppm. In accordance with the Surveillance Frequency Contro 1 Program SR 3.5.1.5 -Only required to be performed for affected accumulators after each solution volume increase of 10% of indicated level that is not the result of addition from the refueling water storage tank containing a boron concentration 2200 ppm and 2400 ppm. -----Verify boron concentration in each accumulator is 2200 ppm and 2400 ppm. Once within 6 hours SR 3.5.1.6 Verify power is removed from each accumulator isolation valve operator.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.5.1-2 Amendment ECCS- Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.2 ECCS -Operating LCO 3.5.2 Two ECCS trains shall be OPERABLE.-- NOTES -------- ----1. In MODE 3. both Safety Injection (SI) pump flow paths and a portion of both Residual Heat Removal (RHR) pump flow paths may be isolated by closing the isolation valves for up to 2 hours to perform pressure isolation valve testing per SR 3.4.14.1.2. In MODE 3. a portion of both Residual Heat Removal (RHR)pump flow paths may be isolated by closing the isolation valves for up to 2 hours to perform pressure isolation valve testing per SR 3.4.14.1.
| |
| provided an alternate means of cold leg injection is available for each isolated flow path.APPLICABILITY:
| |
| MODES 1. 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One train inoperable.
| |
| A.1 Restore train to 7 days OPERABLE status.B. Two trains inoperable.
| |
| B.1 Restore one train to 72 hours OPERABLE status.AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2.3.5.2 -1 Amendment 98 ECCS -Operating
| |
| | |
| ====3.5.2 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.2 -2 Amendment 98 SURVEILLANCE REQUIREMENTS SR 3.5.2.1 SR 3.5.2.2 SURVEILLANCE Verify the following valves are in the listed position with power to the valve operator removed: Number Position Function MDV SI8806 Open Suction to SI Pumps MOV SI8835 Open SI Pump Discharge to Reactor Coolant System CRCS) Cold Legs MDV SI8813 Open SI Pump Recirculation to the Refueling Water Storage Tank MDV SI8809A Open RHR Pump Discharge to RCS Cold Legs MDV SI8809B Open RHR Pump Discharge to RCS Cold Legs MDV SI8840 Closed RHR Pump Discharge to RCS Hot Legs MDV SI8802A Closed SI Pump Discharge to RCS Hot Legs MDV SI8802B Closed SI Pump Discharge to RCS Hot Legs --------------------NOTE-------------------
| |
| Not required to be met for system vent flow paths opened under administrative control. Verify each ECCS 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.
| |
| ECCS-Operating
| |
| | |
| ====3.5.2 FREQUENCY====
| |
| | |
| In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.2 -3 Amendment No. 183 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.5.2.3 Verify ECCS locations susceptible to gas accumulation are sufficiently filled with water. < SR 3.5.2.4 Verify each ECCS pump's developed head at the test flow point is greater than or equal to the required developed head. SR 3.5.2.5 Verify each ECCS automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. SR 3.5.2.6 Verify each ECCS pump starts automatically on an actual or simulated actuation signal. SR 3.5.2.7 Verify, for each ECCS throttle valve listed below, each position stop is in the correct position:
| |
| Valve Number Valve Function SI8810 A,B,C,D Centrifugal Charging System SI8816 A,B,C,D SI System CHot Leg) SI8822 A,B,C,D SI System (Cold Leg) SR 3.5.2.8 Verify, by visual inspection, each ECCS train containment sump suction inlet is not restricted by debris and the suction inlet screens show no evidence of structural distress or abnormal corrosion.
| |
| ECCS-Operating
| |
| | |
| ====3.5.2 FREQUENCY====
| |
| | |
| In accordance with the Surveillance Frequency Control Program In accordance with the Inservice Testing Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.2 -4 Amendment No. 183
| |
| | |
| ===3.5 EMERGENCY===
| |
| | |
| CORE COOLING SYSTEMS CECCS) 3.5.3 ECCS-Shutdown LCO 3.5.3 One ECCS train shall be OPERABLE.
| |
| APPLICABILITY:
| |
| MODE 4. ACTIONS ECCS-Shutdown 3.5.3 ----------------------------------NOTE---------------------------------
| |
| LCO 3.0.4.b is not applicable to ECCS high head subsystem.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. Required ECCS RHR A.1 Initiate action to Immediately subsystem inoperable.
| |
| restore required ECCS RHR subsystem to OPERABLE status. B. Required ECCS B.1 Restore required ECCS 1 hour centrifugal charging centrifugal charging subsystem inoperable.
| |
| subsystem to OPERABLE status. c. Required Action and C.1 Be in MODE 5. 24 hours associated Completion Time of Condition B not met. BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.3-1 Amendment . 1 7 6 ECCS -Shutdown 3.5.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.3.1 The following SRs are applicable for all In accordance equipment required to be OPERABLE:
| |
| with applicable SRs SR 3.5.2.1 SR 3.5.2.7 SR 3.5.2.3 SR 3.5.2.8.SR 3.5.2.4 BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.3 -2 Amendment 98 RWST 3.5.4 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.4 Refueling Water Storage Tank (RWST)LCO 3.5.4 APPLICABILITY:
| |
| The RWST shall be OPERABLE.MODES 1. 2. 3. and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RWST boron A.1 Restore RWST to 8 hours concentration not OPERABLE status.within limits.OR RWST borated water temperature not within limits.B. RWST inoperable for B.1 Restore RWST to. 1 hour reasons other than OPERABLE status.Condition A.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.4 -1 Amendment 98 RWST 3.5.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.5.4.1 Only required to be performed when ambient air temperature is < 35°F or > 100°F. Verify RWST borated water temperature is ;::: 35°F and lOO°F. In accordance with the Surveillance Frequency Control Program SR 3.5.4.2 Only required to be performed when ambient air temperature is < 35°F. Verify RWST ;::: 35°F. vent path temperature is In accordance with the Surveillance Frequency Control Program SR 3.5.4.3 Verify RWST borated water level is 89%. In accordance with the Surveillance Frequency Control Program SR 3.5.4.4 Verify RWST boron concentration is ;::: 2300 ppm and 2500 ppm. In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.5.4 -2 Amendment Seal Injection Flow 3.5.5 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS)3.5.5 Seal Injection Flow LCO 3.5.5 APPLICABILITY:
| |
| Reactor coolant pump seal injection flow shall be within the limits of Figure 3.5.5-1.MODES 1. 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Seal injection flow A.1 Adjust manual seal 4 hours not within limit. .injection throttle valves to give a flow within the limits of Figure 3.5.5-1.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.5 -1 Amendment 98 Seal Flow 3.5.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR -------------NOTE-----------Not requ-i red to be performed until 4 hours after the Reactor Coolant System pressure stabilizes at 2215 psig and s 2255 psig. Verify manual seal injection throttle valves are adjusted to give a flow within the limits of Figure 3.5.5 1. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.5.5 -Amendment 165/165 Seal Injection Flow 3.5.5 250 225 200 175 150 125 100 75 50 225).. .. ... .....ACCEPTABLE REGION....* (49.28, 150)(44, 1 .0)63.43) (32, 63.43) UNACCEPTAI-1 200)(24, LE REGION 25 70 0 20 30 40 50 60 SEAL INJECTION FLOW (GPM)Figure 3.5.5-1 (page 1 of 1)Seal Injection Flow Limits BRAIDWOOD
| |
| -UNITS 1 & 2 3.5.5 -3 Amendment 98 Containment 3.6.1 3.6 CONTAINMENT SYSTEMS 3.6.1 Containment LCO 3.6.1 APPLICABILITY:
| |
| Containment shall be OPERABLE.MODES 1, 2. 3. and 4.ACTIONS CONDITION REQUIRED ACTION' COMPLETION TIME A. Containment A.1 Restore containment 1 hour inoperable.
| |
| to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.1 Perform required visual examinations and In accordance leakage rate testing except for containment with the air lock testing, in accordance with the Containment Containment Leakage Rate Testing Program. Leakage Rate Testing Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.1 -1 Amendment 98 Containment
| |
| | |
| ====3.6.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.6.1.2 Verify containment structural integrity in In accordance accordance with the Containment Tendon with the Surveillance Program. Containment Tendon Surveillance Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.1 -2 Amendment 98 Containment Air Locks 3.6.2 3.6 CONTAINMENT SYSTEMS 3.6.2 Containment Air Locks LCO 3.6.2 APPLICABILITY:
| |
| Two containment air locks shall be OPERABLE.MODES 1, 2, 3. and 4.ACTIONS-- -NOTES- ---------------
| |
| ~1. Entry and exit is permissible to perform repairs on 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."Containment." when air lock leakage results in exceeding the overall containment leakage rate.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more NOTES- ---containment air locks 1. Required Actions A.1.with one containment A.2. and A.3 are not air lock door applicable if both doors inoperable.
| |
| 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)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.2 -1 Amendment 98 Containment Air Locks 3.6.2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.1 Verify the OPERABLE 1 hour door is closed in the affected air lock.AND A.2 Lock the OPERABLE 24 hours door closed in the affected air lock.AND A.3 ----NOTE-- --Air lock doors in high radiation areas may be verified locked closed by administrative means.Verify the OPERABLE Once per 31 days door is locked closed in the affected air lock.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.2 -2 Amendment 98 Containment Air Locks 3.6.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. One or more containment air locks with containment air lock interlock mechanism inoperable.
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| ----- -NOTES---------
| |
| : 1. Required Actions B.1.B.2. and B.3 are not applicable if both doors in the same air lock are inoperable and Condition C is entered.2. Entry and exit of containment is permissible under the control of a dedicated individual.
| |
| B.1 Verify an OPERABLE door is closed in the affected air lock.AND B.2 AND B.3 Lock an OPERABLE door closed in the affected air lock.----NOTE---Air lock doors in high radiation areas may be verified locked closed by administrative means.1 hour 24 hours Once per 31 days Verify an OPERABLE door is locked closed in the affected air lock.I &(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.2 -3 Amendment 98 Containment Air Locks 3.6.2 ACTIONS (continued)
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| CONDITION REQUIRED ACTION COMPLETION TIME C. One or more C.1 Initiate action to Immediately containment air locks evaluate overall inoperable for reasons containment leakage other than Condition A rate per LCO 3.6.1.or B.AND C.2 Verify a door is 1 hour closed in the affected air lock.AND C.3 Restore air lock to 24 hours OPERABLE status..D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time not met. AND D.2 Be in MODE 5. 36 hours BRAIDWOOD
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| -UNITS 1 & 2 3.6.2 -4 Amendment 98 Containment Air Locks 3.6.2 SURVEI LLANCE REQUI SURVEILLANCE FREQUENCY SR 3.6.2.1 --------------
| |
| ----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 applicable to SR 3.6.1.1. Perform required air lock leakage rate In accordance testing in accordance with the Containment with the Leakage Rate Testing Program. Containment Leakage Rate Testing Program SR 3.6.2.2 Verify only one door in the air lock can be In accordance with the opened at a time. Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.6.2 -5 Amendment Containment Isolation Valves 3.6.3 3.6 CONTAINMENT SYSTEMS 3.6.3 Containment Isolation Valves LCO 3.6.3 APPLICABILITY:
| |
| Each containment isolation valve shall be OPERABLE.MODES 1. 2. 3, and 4.ACTIONS____- --------NOTES-----------
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| : 1. Penetration flow path(s) except for 48 inch purge valve 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 containment isolation valves.4. Enter applicable Conditions and Required Actions of LCO 3.6.1."Containment." when isolation valve leakage results in exceeding the overall containment leakage rate acceptance criteria.CONDITION REQUIRED ACTION COMPLETION TIME A. -NOTE -A.1 Isolate the affected 4 hours Only applicable to penetration flow path penetration flow paths by use of at least with two containment one closed and isolation valves. de-activated
| |
| _ automatic or remote manual valve. closed One or more manual valve, blind penetration flow paths flange, or check with one containment valve with flow isolation valve through the valve inoperable except for secured.purge valve leak age not within limit. AND (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.3 -.1 Amendment 98 Containment Isolation Valves 3.6.3 ACTIONS CONDITION IREQUIRED ACTION [COMPLETION TIME A. (continued)
| |
| A.2----NOTES ------1. Isolation devices in high radiation areas may be verified by use of administrative means.2. Isolation devices that are locked, sealed. or otherwise secured may be verified by use of administrative means.Verify the affected penetration flow path is isolated.Once per 31 days for isolation 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 A. I (continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.3 -2 Amendment 98 Containment Isolation Valves 3.6.3 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. -------NOTE-- ----- B.1 Isolate the affected 1 hour Only applicable to penetration flow path penetration flow paths by use of at least with two containment one closed and isolation valves. de-activated automatic or remote manual valve, closed One or more manual valve, or penetration flow paths blind flange.with two containment isolation valves inoperable except for purge valve lea kage not within limit.(continued)
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| BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.3 -3 Amendment 98 Containment Isolation Valves 3.6.3 ACTIONS (continued)
| |
| CONDITION I REQUIRED ACTION I COMPLETION TIME C. ------NOTE----Only applicable to penetration flow paths with only one containment isolation valve and a closed system.C. 1 Isolate the affected penetration flow path by use of at least one closed and de-activated automatic or remote manual valve, closed manual valve, or blind flange.72 hours One or more penetration flow paths with one containment isolation valve inoperable.
| |
| AND C.2-NOTES --1. Isolation devices in high radiation areas may be verified by use of administrative means.2. Isolation devices that are locked.sealed. or otherwise secured may be verified by use of administrative means.Verify the affected penetration flow path is isolated.Once per 31 days D. One or more D.1 Restore purge valve 24 hours penetration flow paths leakage to within with one or more limits.containment purge valves not within p urge valve leakage iMits.(continued)
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| BRAIDWOOD
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| -UNITS 1 & 2 3.6.3 -.4 Amendment 98 Containment Isolation Valves 3.6.3 ACTIONS (continued)
| |
| CONDITION REQUIRED E. Required Action and E.1 Be in MODE 3. associated Completion Time not met. AND E.2 Be in MODE 5. SURVEILLANCE COMPLETION 6 36 SR 3.6.3.1 SURVEI LLANCE Verify each 48 inch purge valve is sealed closed. FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.6.3.2 Verify each 8 inch purge valve is closed, except when the 8 inch containment purge valves are open for purging or venting under administrative controls.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.6.3.3 Valves and blind flanges in high radiation areas may be verified by use of administrative controls.
| |
| Verify each containment isolation manual valve, remote manual valve, and blind flange that is located outside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for conta"j nment i so 1 at i on valves that a re open under administrative controls.
| |
| In accordance with the Survei 11 ance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.6.3 -5 Amendment Containment Isolation Valves 3.6.3 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.6.3.4 ---------------
| |
| NOTE ----------------
| |
| Valves and blind flanges in high radiation areas may be verified by use of administrative means. Verify each containment isolation manual valve, remote manual valve, and blind ange that is located inside containment and not locked, sealed, or otherwise secured and required to be closed during accident conditions is closed, except for containment isolation valves that are open under administrative controls.
| |
| Prior to entering MODE 4 from MODE 5 if not performed within the previous 92 days SR 3.6.3.5 Verify the isolation time of each automatic containment isolation valve is within limits. In accordance with the Inservice Testing Program SR 3.6.3.6 Perform leakage rate testing for 8 inch containment purge valves with resilient seals. In accordance with the Survei 11 ance Frequency Control Program SR 3.6.3.7 Perform leakage rate testing for 48 inch containment purge valves with resilient seals. In accordance with the Surveillance Frequency Control Program SR 3.6.3.8 Verify each automatic containment isolation valve that is not locked, sealed or otherwise secured in position, actuates to the isolation position on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.6.3 -6 Amendment Containment Pressure 3.6.4 3.6 CONTAINMENT SYSTEMS 3.6.4 Containment LCD 3.6.4 Containment pressure shall be -0.1 psig and +1.0 APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQU I RED ACTI ON COMPLETION TIME A. Containment pressure not within limits. A.1 Restore containment to within imits. 1 hour B. Required Action and associated Completion Time not met. B.1 AND B.2 Be in MODE 3. Be in MODE 5. 6 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1 Verify containment pressure is within limits. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.6.4 1 Amendment Containment Air Temperature 3.6.5 3.6 CONTAINMENT 3.6.5 Containment A-j r LCO 3.6.5 Containment average air temperature shall be APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Containment average air temperature not within limit. A.l Restore containment average air temperature to within 1 imit. 8 hours B. Required Action and associated Completion Time not met. B.l AND B.2 Be in MODE 3. Be in MODE 5. 6 hours 36 hours SURVEILLANCE REQUIREMENTS SURVEI LLANCE SR 3.6.5.1 Verify containment average air temperature is within limit.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.6.5 -1 Amendment 165/165 Containment Spray and Cooling Systems 3.6.6 3.6 CONTAINMENT SYSTEMS .3.6.6 Containment Spray and Cooling Systems LCO 3.6.6 APPLICABILITY:
| |
| Two containment spray trains and two containment cooling trains shall be OPERABLE.MODES 1. 2. 3. and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment 7 days train inoperable.
| |
| spray train to OPERABLE status. AND 14 days from discovery of failure to meet the LCO B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 5. 84 hours C. One or more C.1 Restore containment 7 days containment cooling cooling train(s) to trains inoperable.
| |
| OPERABLE status. AND 14 days from discovery of failure to meet the LCO (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.6 -1 Amendment 98 Containment Spray and Cooling Systems 3.6.6 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION D. Required Action and D.l Be in MODE 3. associated Completion Time of Condition C AND not met. D.2 Be in MODE 5. E. Two containment spray E.l Enter LCD 3.0.3. trains inoperable.
| |
| OR Any combination of three or more trains inoperable.
| |
| SURVEILLANCE REQUIREMENTS SR 3.6.6.1 SR 3.6.6.2 SR 3.6.6.3 SU RV EI LLANCE --------------------NOTE-------------------
| |
| Not required to be met for system vent flow paths opened under administrative control. Verify each containment spray 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.
| |
| Operate each containment cooling train fan unit for 2 15 minutes. Verify each containment cooling train cooling water flow rate is 2 2660 gpm to each cooler. COMPLETION TIME 6 hours 36 hours Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.6 -2 (continued)
| |
| Amendment No. 183 Containment Spray and Cooling Systems 3.6.6 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.6.6.4 Verify each containment spray pump's In accordance developed head at the flow test point is with the greater than or equal to the required Inservice developed head. Testing Program SR 3.6.6.5 Verify each automatic containment spray In accordance valve in the flow path that is not locked, with the sealed, or otherwise secured in position, Surveillance actuates to the correct position on an Frequency actual or simulated actuation signal. Control Program SR 3.6.6.6 Verify each containment spray pump starts In accordance automatically on an actual or simulated with the actuation signal. Surveillance Frequency Control Program SR 3.6.6.7 Verify each containment cooling train In accordance starts automatically on an actual or with the simulated actuation signal. Surveillance Frequency Control Program SR 3.6.6.8 Verify each spray nozzle is unobstructed.
| |
| Foll owing maintenance that could result in nozzle blockage OR F o 11 owi ng fl u i d fl ow through the nozzles SR 3.6.6.9 Verify containment spray locations In accordance susceptible to gas accumulation are with the sufficiently filled with water. Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.6 -3 Amendment No. 183 Spray Additive System 3.6.7 3.6 CONTAINMENT 3.6.7 Spray Additive LCD 3.6.7 The Spray Additive System shall be APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQU I RED ACTI ON COMPLETION A. Spray Addi t i ve System 7 days A.1 Restore Spray i noperab 1 e. Additive System to OPERABLE status. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 84 hours SURVEILLANCE SR 3.6.7.1 SURVEI Verify each spray additive manual and automatic valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position.
| |
| FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.6.7.2 Verify spray additive tank solution level is 78.6% and 90.3%. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.6.7 -1 Amendment Spray Additive System 3.6.7 SURVEI LLANCE REQUI (conti nued) SURVEILLANCE FREQUENCY SR 3.6.7.3 Verify spray additive tank sodium hydroxide solution concentration is 30% and 36% by weight. In accordance with the Surve"i 11 ance Frequency Control Program SR 3.6.7.4 Verify each spray additive automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.6.7.5 Verify spray additive flow rate from each solution's flow path. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.6.7 2 Amendment 3.6.8 3.6 CONTAINMENT SYSTEMS 3.6.8 (Deleted)BRAIDWOOD
| |
| -UNITS 1 & 2 3.6.8-1 Amendment 137
| |
| * MSSVs 3.7.1 3.7 PLANT SYSTEMS 3.7.1 Main Steam Safety Valves (MSSVs)LCO 3.7.1 APPLICABILITY:
| |
| Five MSSVs per steam generator shall be OPERABLE.MODES 1, 2, and 3.I ACTIONS-------------------------------------
| |
| NOTE----------------
| |
| Separate Condition entry is allowed for each MSSV.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more steam A.1 Reduce THERMAL POWER 4 hours generators with one or to less than or equal more MSSVs inoperable.
| |
| to the Maximum Allowable
| |
| % RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.AND A.2 -------NOTE---Only required in Mode 1.Reduce the Power 36 hours Range Neutron Flux -High reactor trip setpoint to less than or equal to the Maximum Allowable% RTP specified in Table 3.7.1-1 for the number of OPERABLE MSSVs.BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.1 -1 Amendment 128 MSSVs 3.7.1 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND OR B.2 Be in MODE 4. 12 hours One or more steam generators with > 4 MSSVs inoperable.
| |
| SURVEILLANCE REQUIREMENTS
| |
| __.SURVEILLANCE FREQUENCY SR 3.7.1.1 -------------------
| |
| NOTE--------------------
| |
| Only required to be performed in MODES 1 and 2.Verify each required MSSV lift setpoint per In accordance Table 3.7.1-2 in accordance with the with the Inservice Testing Program. Following Inservice testing, lift setting shall be within +/- 1%. Testing Program I BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.1 -2 Amendment 128 MSSVs 3.7.1 Table 3.7.1-1 (page 1 of 1)OPERABLE Main Steam Safety Valves versus Maximum Allowable Power I NUMBER OF OPERABLE MAXIMUM ALLOWABLE MSSVs PER STEAM POWER (% RTP)GENERATOR 4 56 3 < 39 2 < 23 I I I I BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.1 -3 Amendment 128 MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)Main Steam Safety Valve Lift Settings VALVE NUMBER LIFT SETTING STEAM GENERATOR (psig +/- 3%)A B C D MS013A MS013B MS013C MS013D 1235 MS014A MS014B MS014C MS014D 1220 MS015A MS015B MS015C MS015D 1205 MS016A MS016B MS016C MS016D 1190 MS017A MS017B MS017C MS017D 1175 BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.1 -4 Amendment 98
| |
| | |
| ===3.7 PLANT===
| |
| SYSTEMS 3.7.2 Main Steam Isolation Valves (MSIVs) LCD 3.7.2 Four MSIVs and their associated actuator trains shall be OPERABLE.
| |
| APPLICABILITY:
| |
| MODE 1, MODES 2 and 3 except when all MSIVs are closed. ACTIONS MSIVs 3.7.2 CONDITION REQUIRED ACTION COMPLETION TIME A. One MSIV actuator A.1 Restore MSIV actuator 7 days train inoperable.
| |
| train to OPERABLE status. B. Two MSIVs each with B.1 Restore one MSIV 72 hours one actuator train actuator train to inoperable such that OPERABLE status. the inoperable actuator trains are in different ESF Divisions.
| |
| C. Two MSIVs each with C.1 Restore one MSIV 24 hours one actuator train actuator train to inoperable and both OPERABLE status. inoperable actuator trains are in the same ESF Division.
| |
| D. Two MSIV actuator D.1 Declare the affected Immediately trains inoperable on MSIV inoperable.
| |
| the same MSIV. (cont1nued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.2-1 Amendment No. 181 ACTIONS (continued)
| |
| CONDITION E. Three or more MSIV actuator trains inoperable.
| |
| OR Required Action and associated Completion Time of Condition A, B, or C not met. F. One MSIV inoperable in MODE 1. G. Required Action and associated Completion Time of Condition F not met. H. ---------NOTE---------
| |
| Separate Condition entry is allowed for each MSIV. ----------------------
| |
| One or more MSIV inoperable in MODE 2 or 3. I. Required Action and associated Completion Time of Condition H not met. BRAIDWOOD
| |
| -UNITS 1 & 2 E.1 F.1 G.1 H.1 AND H.2 I.1 AND I.2 REQUIRED ACTION Declare each affected MSIV inoperable.
| |
| Restore MSIV to OPERABLE status. Be in MODE 2. Close MSIV. Verify MSIV is closed. Be in MODE 3. Be in MODE 4. MSIVs 3.7.2 COMPLETION TIME Immediately 8 hours 6 hours 8 hours Once per 7 days 6 hours 12 hours 3.7.2-2 Amendment No. 181 I I I I I I I I I SURVEILLANCE REQUIREMENTS SR 3.7.2.1 SR 3.7.2.2 SURVEILLANCE
| |
| -------------------NOTE--------------------
| |
| Only required to be performed in MODES 1 and 2. Verify closure time of each MSIV is s 5 seconds. -------------------NOTE--------------------
| |
| Only required to be performed in MODES 1 and 2. Verify each actuator train actuates the MSIV to the isolation position on an actual or simulated actuation signal. BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.2-3 MSIVs 3.7.2 FREQUENCY In accordance with the Inservice Testing Program In accordance with the Surveillance Frequency Control Program Amendment No. 181 Secondary Specific Activity 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Specific Activity 3.7.3 The specific activity of the secondary coolant shall be 0.1 DOSE EQUIVALENT 1-131. APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Specific activity not within limit. A.l AND Be in MODE 3. 6 hours A.2 Be in MODE 5. 36 hours SURVEI LLANCE SR Verify the specific activity of the secondary coolant is 0.1 DOSE EQUIVALENT 1-131.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.3 -Amendment SG PORVs 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Steam Generator (SG) Power Operated Relief Valves (PORVs)LCO 3.7.4 APPLICABILITY:
| |
| Four SG PORV lines shall be OPERABLE.MODES 1, 2, and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SG PORV line A.1 Restore SG PORV line 30 days inoperable.
| |
| to OPERABLE status.B. Two or more SG PORV B.1 Restore all but one 24 hours lines inoperable.
| |
| SG PORV line to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time not met. AND C.2 Be in MODE 4. 12 hours I BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.4 -I Amendment 134 SG PORVs 3.7.4 SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.7.4.1 Verify one complete cycle of each SG PORV. In accordance with the Surve-i 11 ance Frequency Control Program SR 3.7.4.2 Verify one complete cycle of each SG PORV block valve. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.4-2 Amendment 165/165 AF System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Auxiliary Feedwater (AF) System LCO 3.7.5 Two AF trains shall be OPERABLE.APPLICABILITY:
| |
| MODES 1, 2, and 3.ACTIONS----------------------------------
| |
| NOTE---------------------------------
| |
| LCO 3.0.4.b is not applicable when entering MODE 1.CONDITION REQUIRED ACTION COMPLETION TIME A. One AF train A.1 Restore AF train to 72 hours inoperable.
| |
| OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met.B.2 Be in MODE 4. 12 hours C. Two AF trains C.1 ---------NOTE--------
| |
| inoperable.
| |
| LCO 3.0.3 and all other LCO Required Actions requiring MODE changes are suspended until one AF train is restored to OPERABLE status.Initiate action to Immediately restore one AF train to OPERABLE status.BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.5 -1 Amendment 134 AF System 3.7.5 SURVEI LLANCE REQU TREMENTS SR 3.7.5.1 SURVEI LLANCE Verify each AF manual, power operated, and automatic valve in each water flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
| |
| FREQUENCY In accordance with the Survei 11 ance Frequency Control Program SR 3.7.5.2 Verify day tank contains?
| |
| 420 gal oi l. of fuel In accordance with the Surveillance Frequency Control Program SR 3.7.5.3 Operate the diesel driven AF pump for ? 15 minutes. In accordance with the Surveillance Frequency Control Program SR 3.7.5.4 Verify the developed head of each AF pump at the flow test point is greater than or equal to the required developed head. In accordance with the Inservice Testing Program SR 3.7.5.5 Verify each AF automatic valve that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.7.5.6 Verify each AF pump starts automatically on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program (contlnued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.7.5 -2 Amendment AF System 3.7.5 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.7.5.7 Verify proper alignment of the required AF flow paths by verifying flow from the condensate storage tank to each steam generator.
| |
| Prior to entering MODE 2 whenever unit has been in MODE 5, MODE 6, or defueled for a cumulative period of > 30 days SR 3.7.5.8 Verify fuel oil properti es are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program. In accordance with the Diesel Fuel Oi 1 Testing Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.5 -3 Amendment CST 3.7.6 3.7 PLANT SYSTEMS 3.7.6 Condensate Storage Tank (CST)LCO 3.7.6 APPLICABILITY:
| |
| The CST level shall be a 66%.MODES 1. 2. and 3.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CST level not within A.1 Verify by 4 hours limit. administrative means OPERABILITY of backup AND water supply.Once per 12 hours thereafter AND A.2 Restore CST level to 7 days within limit.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 4. 12 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.6 -1 Amendment 98 CST 3.7.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.6.1 Verify the CST level is 66%. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.6 -2 Amendment CC System 3.7.7 3.7 PLANT SYSTEMS 3.7.7 Component Cooling Water (CC) System LCO 3.7.7 APPLICABILITY:
| |
| The CC System shall be OPERABLE.MODES 1. 2. 3. and 4.ACTIONS~NOTE--- -----------
| |
| Enter applicable Conditions and Required Actions of LCO 3.4.6. "RCS Loops- MODE 4." for Residual Heat Removal loops made inoperable by CC.CONDITION REQUIRED ACTION COMPLETION TIME A. One CC flow path A.1 Restore CC flow path 7 days inoperable.
| |
| to OPERABLE status.B. One required CC pump B.1 Restore required CC 7 days inoperable.
| |
| pump to OPERABLE status.C. Required Action and C.1 Be in MODE 3. 6 hours associated Completion Time of Condition A or- AND B not met.C.2 Be in MODE 5. 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.7 -1 Amendment
| |
| : 98.
| |
| CC System 3.7.7 SURV E T L LANC E REQU I REMENTS SURVEILLANCE FREQUENCY SR 3.7.7.1 Isolation of CC flow to individual components does not render the CC System inoperable.
| |
| Verify each CC manual and power operated valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.7.7.2 Verify each Essential Service Water System manual and power operated valve directly serving the CC heat exchangers that is not locked, sealed, or otherwise in the correct position, is in the correct position, or can be aligned to the correct position.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.7.7.3 Verify each required CC pump starts automatically on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.7 -2 Amendment SX System 3.7.8 3.7 PLANT SYSTEMS 3.7.8 Essential Service Water (SX) System LCD 3.7.8 The following SX trains shall be OPERABLE:
| |
| : a. Two unit-specific SX trains; and b. One opposite-unit SX train for unit-specific support. APPLICABILITY:
| |
| MODES I, 2, 3, and 4. ACTIONS CONDITION REQLI I RED ACTI ON COMPLETION TIME A. One unit-specific SX train inoperable.
| |
| A.l
| |
| : 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Operating," for Emergency Diesel Generator made inoperable by SX. 2. Enter applicable Conditions and Required Actions of LCO 3.4. 6 , "RCS Loops-MODE 4," for Residual Heat Remova 1 loops made inoperable by 5X. Restore unit-specific SX train to OPERABLE status. 72 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1& 2 3.7.8 -1 Amendment 160 SX System 3.7.8 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Opposite-unit SX train inoperable.
| |
| B.1 Restore opposite-unit SX train to OPERABLE status. 7 days C. Required Action and associated Completion Time of Condition A or B not met. C.1 Be in MODE 3. MID C.2 Be in MODE 5. 6 hours 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.8 -2 Amendment 1 60 SX System 3.7.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.8.1
| |
| -
| |
| Isolation of SX flow to individual components does not render the SX System inoperable.
| |
| Verify each uni specific SX manual, power operated, and automatic valve in the flow path servicing safety related equipment, that is not locked, sealed, or otherwise secured in position, is in the correct position.
| |
| In accordance with the Surveillance Frequency Cont ro1 P rog ram SR 3.7.8.2 --Not required when opposi unit is in MODE 1, 2, 3, or 4. Operate the opposite-unit SX 15 minutes. pump for In accordance with the Survei 11 ance Frequency Control Program SR 3.7.8.3 Cycle each opposite-unit SX crosstie valve that is not secured in the open position with power removed. In accordance with the Surveillance Frequency Control Program SR 3.7.8.4 Verify each unit specific SX automatic valve in the flow path that is not locked, sealed, or otherwise secured in position, actuates to the correct position on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.7.8.5 Verify each unit-specific SX pump starts automatically on an actual or simulated actuation signal. In accordance with the Survelllance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.7.8 -3 Amendment 165/165 UHS 3.7.9 3.7 PLANT 3.7.9 Ultimate Heat Sink LCD 3.7.9 The UHS shall be APPLICABILITY:
| |
| MODES 1, 2, 3, and 4. ACTIONS CONDITION REQUIRED ACTION COtv'IPLETION TIME A. UHS inoperable.
| |
| A.l AND A.2 Be in MODE Be in MODE 3. 5. 6 hours 36 hours SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.7.9.1 Verify water level of UHS is 590 ft Mean Sea Level (MSL). In accordance with the Surveillance Frequency Control Program SR 3.7.9.2 Verify average water temperature of UHS is :::; lOO°F. In accordance with the Surveillance Frequency Control Program SR 3.7.9.3 Verify bottom level of UHS is :::; 584 ft MSL. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.9 1 Amendment V1 Filtraiý-or,.7.1 3. 7 PLANT SYSTEMS 3.7.10 Control Room Ventilation (VC) Filtration System LCO 3.7.10 Two VC Filtration System, tr~ainss sha11l be E,,RABLLE.
| |
| -----------------------
| |
| NOTE ------------------------
| |
| The control room envelope (CRE) boundary may be opened intermittently under administrative control.MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.
| |
| APPLICABILITY:
| |
| ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One VC Filtration A.1 Restore VC Filtration 7 days System train System train to inoperable for reasons OPERABLE status.other than Condition B.B. One or more VC B.1 Initiate action to Irrmnediately Filtration System implement mitigating trains inoperable due actions.to inoperable CRE boundary in MODE 1, 2, AND 3, or 4.B.2 Verify mitigating 24 hours actions ensure CRE occupant exrosures to radiologica
| |
| , chemical, and smoke hazards will not exceed limits.AND B.3 Restore CRE boundary 90 days to OPERABLE status.(continued)
| |
| : r. ~ ~ nUN l r .r._iI tTS -I C ')OF"I-i L)v~tuu UU)iC 7 .0 -Am e d Men 146 VC Filtration System 3.7.10 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION JCOMPLETION TIME.Required ction and C.I Be i, MODE 3. 6 hours associated Completion Time of Condition A or AND B not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours D. Required Action and D.i.1 Place OPERABLE VC Inmediately associated Completion Filtration System Time of Condition A train in emergency not met in MODE 5 mode.or 6, or during movement of irradiated AND fuel assemblies.
| |
| D.1.2 Verify OPERABLE VC Immediately Filtration System train is capable of being powered by an OPERABLE emergency power source.OR D.2.1 Suspend movement of Immediately irradiated fuel assemblies.
| |
| AND D.2.2 Suspend positive Immediately reactivity additions.(continued)
| |
| BRAIDWOOD
| |
| -UNITS I & 2 3.7.10 --2 Amendment 146 1 VC Filtration System 3.7 .10 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION E. Two VC Filtration E.l Suspend movement of System trains irradiated fue 1 inoperable in MODE 5 assemblies.
| |
| or 6, or during movement of irradiated ANO fuel assemblies.
| |
| E.2 Suspend positive OR reactivity additions.
| |
| One or more VC Filtration System trains inoperable due to an inoperable CRE boundary in MODE 5 or 6, or during movement of irradiated fuel assemblies.
| |
| F. Two VC Filtration F.l Enter LCO 3.0.3. System trains inoperable in MODE 1, 2, 3, or 4 for reasons other than Condition B. SURVEILLANCE REQUIREMENTS SR 3.7.10.1 SURVEILLANCE Operate each VC Filtration System train with: a. Flow through the makeup system filters for 15 continuous minutes with the heaters operating; and b. Flow through the recirculation charcoal adsorber 15 minutes. BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.10-3 CCJI1PLETION TIME Ill1Tlediately Irrmediately Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
| |
| Amendment 1 7 7 VC Filtration System 3.7.10 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEI LLANCE FREQUENCY SR 3.7.10.2 Perform required VC Filtration System filter testing in accordance with the Ventilation Filter Testing Program (VFTP). In accordance wi th the VFTP SR 3.7.10.3 Verify each VC Fi ltrati on System tra-i n actuates on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.7.10.4 Perform required CRE unfiltered air inleakage testing in accordance with the Control Room Envelope Habitability Program. In accordance with the Control Room Envelope Habitabil ity Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.10 4 Amendment VC Temperature Control System 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Ventilation (VC) Temperature Control System LCO 3.7.11 APPLICABILITY:
| |
| Two VC Temperature Control System trains shall be OPERABLE.MODES 1. 2. 3. 4, 5. and 6.During movement of irradiated fuel assemblies.
| |
| ACTIONS -CONDITION REQUIRED ACTION COMPLETION TIME A. One VC Temperature A.1 Restore VC 30 days Control System train Temperature Control inoperable.
| |
| System train to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met in MODE 1. 2.3. or 4. B.2 Be in MODE 5. 36 hours (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.11 -I Amendment 98 V~ ~ ~~~ " Thp a ur CrP ,] risle ci i j ./ ii ACTIONS (continued)
| |
| CONDITION REQUIRED AiCTION 0COHPLETION TIME C..1 I Place OPERABLE VC imediately Temperature Control C. Required Action and associated Completion Time of Condition A not met in MODE 5 or 6, or during movement of irradiated fuel assemblies.
| |
| System train in AN[C.1.2 OR Verify OPERABLE VC Irmediately Temperature Control System train is capable of being powered by an OPERABLE emergency power source.Suspend movement of Irmiediately irradiated fuel assemblies.
| |
| Suspend positive Immediately reactivity additions.(continued)
| |
| C.2.1 AND C. 2.2 I BPRAIDWOOD
| |
| -UNITS 1 & 2 uFffeYd" 14 0 VC Temperature Control System 3.7.11 ACTIONS (continued)
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME D. Two VC Temperature Control System trains inoperable in MODE 5 or 6, or during movement of irradiated fuel assemblies.
| |
| E. Two VC Temperature Control System trains inoperable in MODE 1, 2, 3, or 4. 0.1 AND 0.2 E.1 Suspend movement of i rrad i ated fuel assemblies.
| |
| Suspend pas it i ve reactivity additions.
| |
| Enter LCO 3.0.3. Immediately Immediately Immediately SURVEILLANCE SURVEILLANCE FREQUENCY SR 3.7.11.1 Verify control room temperature gO°F. In accordance with the Surveil 1 ance Frequency Control Program SR 3.7.11.2 Verify each VC Temperature Control train has the capability to remove required heat load. System the In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UN ITS 1 & 2 3.7.11 -3 Amendment Nonaccessible Area Exhaust Filter Plenum Ventilation System 3.7.12 3.7 PLANT SYSTEMS 3.7.12 Nonaccessible Area Exhaust Filter Plenum Ventilation System LCO 3.7.12 Three Nonaccessible Area Exhaust Filter Plenum Ventilation System trains shall be OPERABLE.
| |
| with two trains aligned for operation and one train aligned in standby.~~~- --NOTE-I-- -------~-~Nonaccessible Area Exhaust Filter Plenum Ventilation System alignment requirement may be suspended intermittently under administrative controls for purposes of train realignment.
| |
| APPLICABILITY:
| |
| MODES 1. 2, 3. and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One Nonaccessible Area A.1 Restore Nonaccessible 7 days Exhaust Filter Plenum Area Exhaust Filter Ventilation System Plenum Ventilation train inoperable.
| |
| System train to OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.12 -1 Amendment 98 Nonaccessible Area Exhaust Filter Plenum Ventilation System 3.7.12 SURVEILLANCE REQUIREMENTS SR 3.7.12.1 SURVEI LLANCE Operate each Nonaccessible Area Exhaust Filter Plenum Ventilation System train for ;;:: 15 minutes. FREQUENCY In accordance with the Surveillance Frequency Control Program SR SR 3.7.12.2 3.7.12.3 Perform required Nonaccessible Area Exhaust lter Pl enum Vent il at; on System fi lter testing in accordance with the Ventilation Filter Test-jng Program (VFTP). I Verify each Nbnaccessible Area Exhaust Filter Plenum Ventilation System train actuates on a manual, an actual, or a simulated actuation signal. In accordance with the VFTP In accordance with the Surveillance Frequency Control Program SR 3.7.12.4 Verify two Nonaccessible Area Exhaust Filter Plenum Ventilation System trains can maintain a pressure -0.25 inches water gauge relative to atmospheric pressure dur-j ng the emergency mode of operat i on at a flow rate of 73,590 cfm per tra-j n. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.12-2 Amendment FHB Venltilation tem 3.7.13.7. PLu-I iT BYS S E 3.7 .13 Fuel Handling Buildi ng E-xhatist Filter Plenium (FHB), Ventilation Sy'st.e-m, LCO 3.7.13 APPLICABI LITY: Two FHB Ventilation System trains shall be OPERABLE.During movement of RECENTLY .IRRADIATED FUEL assemblies in the fuel building, During movement of RECENTLY 1PF'DIATED FUEL assemblies in the containment with the equipment hatch not intact.I I i ACTIONS-------------------------------------
| |
| NOTE -------------------------------------
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION jCOMPLETION TIME A,. One FHB Ventilation A.1 Restore FHB 7 days System train Ventilation System inoperable, train to OPERABLE status.B. Required Action and B.1.1 Place OPERABLE FHB Immediately associated Completion Ventilation System Time not met. train in emergency.
| |
| mode.AND B.1.2 Verify OPERABLE FHB Immediately Ventilation System train is capable of being powered by an OPERABLE emergency power source.OR I _(continued)
| |
| BRAIDWOOD-,UNITS 1 & 2 11. 1 I L1 1 7. , I An-re-Indrieent 140 FFIB Venti I ation y m 3.7.13 A ,CTIOrlS _4__ __CONDITION ) REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| B.2.1 SLispend movement of Imediately RECENTLY I RRADIATED FUEL assemblies in the fuel handling building.AND B.2.2 -------- NOTE ---------Only required with equipment hatch not intact.Suspend movement of Immediately RECENTLY I RRADIATED FUEL assemblies in the containment.(continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3ý.7.13 -: 2 A--r,4111=1 11 '4'_" e I-I'L- 14 0
| |
| ------------------
| |
| --FHB Ventilation System 3.7.13 ACTIONS (continued)
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME C. FHB Ventilation C.l Suspend movement of Immediately System trai ns RECENTLY IRRADIATED inoperable.
| |
| FUEL assemblies in the fuel handling buil di ng. AND ------NOTE ------Only required with equipment hatch not intact.
| |
| movement of Immediately REC NTLY IRRADIATED FUEL assemblies in the containment.
| |
| SURVEILLANCE SR 3.7.13.1 Operate each FHB Ventilation System train for 15 minutes.
| |
| In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.7.13 -Amendment FHB Ventilation System 3.7.13 SURVEILLANCE REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.7.13.2 Perform required FHB Ventilation System filter testing in accordance with the Ventilation Filter Testing Program (VFTP). In accordance with the VFTP SR 3.7.13.3 Only required during movement of RECENTLY IRRADIATED FUEL assemblies with the equipment hatch not intact. Verify one FHB Ventilation System train can maintain a pressure S -0.25 inches water gauge relative to atmospheric pressure during the emergency mode of operation.
| |
| In accordance with the Surveillance Frequency Control Program SR 3.7.13.4 Verify each FHB Ventilation System train actuates on an actual or simulated actuation signal. In accordance with the Surveillance Frequency Control Program SR 3.7.13.5 -Only required during movement of RECENTLY IRRADIATED FUEL assemblies in the fuel handl i ng buil di ng with the equi pment hatch intact. Verify one FHB Ventilation System train can maintain a pressure $ 0.25 inches water gauge relative to atmospheric pressure during the emergency mode of operation at a flow rate $ 23,100 cfm. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.7.13 4 Amendment Spent Fuel Pool Water Level 3.7.14 3.7 PLANT SYSTEMS 3.7.14 Spent Fuel Pool Water Level LCO 3.7.14 The spent fuel pool water level shall be 23 ft over the top of irradiated fuel assemblies seated in the storage racks. APPLICABILITY:
| |
| During movement of irradiated fuel assemblies in the spent fuel pool. ACTIONS LCO 3.0.3 is not applicable.
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME A. Spent fuel pool water 1 evel not withi n 1 i mit. A.l Suspend movement of i rradi ated fuel assemblies in the spent fuel pool. Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.7.14.1 Verify the spent fuel pool water level is 23 ft above the top of the irradiated fuel assemblies seated in the storage racks.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.7.14 -1 Amendment Spent Fuel Pool Boron Concentration 3.7.15 3.7 PLANT 3.7.15 Spent Fuel Pool Boron LCD 3.7.15 The spent fuel pool boron concentration shall be ;;:: 300 APPLICABILITY:
| |
| Whenever fuel assemblies are stored in the spent fuel LCD 3.0.3 is not applicable.
| |
| CONDITION REQU I RED ACTI ON COMPLETION TIME A. Spent fuel pool boron concentration not wi thi n 1 imit. A.l Suspend movement of fuel assemblies in the spent fuel pool. Immediately AND A.2 Initiate action to restore spent fuel pool boron concentration to withi n 1 imit. Imllediately SURVEILLANCE SR 3.7.15.1 Verify the spent fuel pool boron concentration is within limit.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.7.15 -1 Amendment Spent Fuel Assembly Storage 3.7.16 3.7 PLANT1 SYSTEMS 3.7.16 Spent Fuel Assembly Storage LCO 3. 7.16 Each spent fuel assembly stored in the spent fuel pool shall, as applicable:
| |
| : a. Region 1 of Holtec spent fuel, pool storage racks Have an initial nominal enrichment of ý 5..0 weight percent U->235 to permit storage in any cell locatIon.b. Region 2 of Holtec spent fuel pool storage racks Have a combination of initial enrichment and burnup within the Acceptable Burnup Domain of Figure 3.7.16-1.Whenever fuel assemblies are stored in the spent fuel pool.APPLICABILITY:
| |
| -----CT----------
| |
| ONS-- NOTE---------------------------------
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A. 1 Initiate action to Immediately LCO not met. move the noncomplying fuel assembly into a location which restores compliance.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 371 mnmn 4 3.7.16 -1 Amendment 145 Spent Fuel Assembly Storage 3.7.16 SURVEILLANCE REQUIREMENTS
| |
| *SURVEILLANCE FREQUENCY SR 3.1.16.1 Verify by administrative means the initial Prior to*nominal enrichment of the fuel assembly is storing the:5 5.0 weight percent U-235. fuel assembly in Region 1 SR 3.7.16.2 Verify by administraLi~e means the Prior to combination of initial enrichment, burnup, storing the and decay time, as applicable, of the fuel fuel assemblyv assembly is within the Acceptable Burnup in Region2 Domain of Figure 3 .7.16-1.BRAIDWOOD
| |
| -UNITS 1 & 2 371 mnmn 4 3.7.16 -2 Amendment 145 Spent Fuel Assembly Storage 3.7.16 45000.40000-35000 2 S30000 7-9500O>. 20000 S15000 S10000 5000, 0 F -4I--+)___ACCEPTABLE
| |
| ~ ~ 1_BURNUP DOMAIN I~ I-I A NACETAL-~ __f-TIBURNUP DOMAIN 9 4-2.5 33.5 4 INITIAL U-235, ENRICHMENT (w/o)4.5 5 Figure 3.7.16-1 (page 1 of 1)Region 2 Fuel Assembly Burnup Requirements (Holtec Spent Fuel Pool Storage Racks)I BRAIDWOOD
| |
| -UNITS 1 & 2 371 mnmn 4 3.7.16 -3 Amendment 145 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 sources shall be OPERABLE: a. Two qualified circuits per bus between the offsite transmission network and the onsite Class 1E AC Electrical Power Distribution System; and b. Two Diesel Generators MOGs) capable of supplying the onsite Class 1E AC Electrical Power Distribution System.APPLICABILITY:
| |
| MODES 1, 2, 3, and 4.ACTIONS-------------------
| |
| NOTE---------------------------------
| |
| LCO 3.0.4.b is not applicable to DGs.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more buses with A.1 Perform SR 3.8.1.1 1 hour one required qualified for the required circuit inoperable.
| |
| OPERABLE qualified AND circuits.Once per 8 hours thereafter AND A.2 Restore required 72 hours qualified circuit(s) to OPERABLE status. AND 17 days from discovery of failure to meet LCO (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1 -I Amendment 134 AC Sources- Operating 3.8.1 ACTIONS (continued)
| |
| CONDITION I REQUIRED ACTION COMPLETION TIME I B. One required DG inoperable.
| |
| B.1 1 hour Verify both opposite-unit DGs OPERABLE.It AND B.2 AND B.3 Perform SR 3.8.1.1 for the required qualified circuits.Declare required feature(s) supported by the inoperable DG inoperable when its required redundant feature(s) is inoperable.
| |
| AND Once per 24 hours thereafter 1 hour AND Once per 8 hours thereafter 4 hours from discovery of Condition 8 concurrent with inoperability of redundant required feature(s) 24 hours 24 hours (continued)
| |
| AD B.4.1 Determine OPERABLE DG is not inoperable due to common cause failure.OR B.4.2 Perform SR 3.8.1.2 for OPERABLE DG.AND BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1 -2 Amendment 108 SEP O 1 2/O
| |
| -AC Sources -Operating
| |
| | |
| ====3.8.1 ACTIONS====
| |
| I CONDITION J REQUIRED ACTION COMPLETION TIME B. (continued)
| |
| I B.5 Restore DG to 14 days OPERABLE status.AND 17 days from discovery of failure to meet LCO C. Required Action and C.1 Restore DG to 72 hours associated Completion OPERABLE status.Time of Required Action B.1 not met.D. One or more buses with D.1 Restore one required 24 hours two required qualified qualified circuit per circuits inoperable.
| |
| bus to OPERABLE status.I I E. One DG inoperable and one or more buses with one required qualified circuit inoperable.
| |
| I OR One DG inoperable and one bus with two required qualified circuits inoperable.
| |
| ----NOTE --- ---------Enter applicable Conditions and Required Actions of LCO 3.8.9. "Distribution Systems -Operating." when Condition E is entered with no AC power source to a division._ _ _ __ _ -_ _ -----_ _ _ _ __-- -E.1 Restore required qualified circuit(s) to OPERABLE status.12 hours OR I E.2 Restore DG to OPERABLE status.12 hours______________
| |
| £ _________________________
| |
| J.(continued)
| |
| Amendment 108 20 1 G00 BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1 -3 AC Sources -Operating 3.8.1 I ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME F. Two DGs inoperable.
| |
| F.1 Restore one DG to 2 hours OPERABLE status.G. Required Action and G.1 Be in MODE 3. 6 hours associated Completion Time of Condition A. AND C. D. E, or F not met.G.2 Be in MODE 5. 36 hours OR Required Action and associated Completion Time of Required Action B.2. B.3.B.4.1. B.4.2. or B.5 not met.H. Two DGs inoperable.
| |
| H.1 Enter LCO 3.0.3. Immediately and one or more buses with one or more required qualified circuits inoperable.
| |
| OR One DG inoperable.
| |
| one bus with two required qualified circuits inoperable, and the second bus with one or more required qualified circuits inoperable.
| |
| I BRAIDWOOD
| |
| -UNITS I & 2 3.8.1 -4 Amendment 108 SEP 0 1 2S0, AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.1 Verify correct breaker alignment and indicated power availability for each required qualified circuit. In accordance with the Surveillance Frequency , Control Program SR 3.8.1.2 ---A modified DG start involving idling and gradual acceleration to synchronous speed may be used for this SR. When modified start procedures are not used, the time, voltage, and frequency tolerances of SR 3.8.1.7 must be met. Performance of SR 3.8.1.7 satisfies this SR. Verify each DG starts from standby condition and achieves steady state voltage 3950 V and $ 4580 V and frequency 58.8 Hz and $ 61.2 Hz. In accordance with the Surveillance Frequency Control Program SR 3.8.1.3 I. DG loadings may include gradual 1 oad-j ng 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 Surveillance 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 operates for 60 minutes at a load 4950 kW and $ 5500 kW. In accordance with the Survei 11 ance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.8.1 -5 Amendment 165/165 AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SR 3.8.1.4 SURVEILLANCE Verify each day tank conta-ins fue 1 oi 1 . 450 gal of FREQUENCY In accordance with the Surveillance Frequency Control Program SR 3.8.1.5 Check for and remove each day tank. accumulated water from In accordance with the Surveillance Frequency Control Program SR 3.8.1.6 Verify the fuel oil transfer system operates to automatically transfer fuel from storage tank(s) to the day tank. oil In accordance with the Surveillance Frequency Control Program SR 3.8.1. 7 Verify each DG starts from normal standby condition and achieves:
| |
| : a. In $ 10 seconds, voltage 3950 V and frequency 58.8 Hz; and b. Steady state voltage 3950 V and $ 4580 V, and frequency 58.8 Hz and $ 61. 2 Hz. In accordance with the Surveillance Frequency Control Program SR 3.8.1.8 Verify manual transfer of AC power from the required normal qualified circuit(s) to the reserve required qualified circuit(s).
| |
| sources In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1-6 Amendment 165/165 AC Sources-Operating 3.8. l SURVEILLANCE REQUIREMENTS (continued)
| |
| SR 3.8.1.9 SURVEILLANCE
| |
| -------------------NOTE--------------------
| |
| This Surveillance shall not be performed in MODE 1 or 2. Verify each DG rejects a load greater than or equal to its associated single largest post-accident load, and: a. Following load rejection, the frequency is s 64.5 Hz; b. Following load rejection, the steady state voltage is 3950 V and s 4580 V; and c. Following load rejection, the steady state frequency is maintained 58.8 Hz and s 61.2 Hz. SR 3.8.1.10 -------------------NOTES-------------------
| |
| : 1. Momentary transients above the voltage limit immediately following a load rejection do not invalidate this test. 2. This Surveillance shall not be performed in MODE 1 or 2. 3. If performed with DG synchronized with offsite power, it shall be performed at a power factors 0.89. However, if grid conditions do not permit, the power factor limit is not required to be met. Under this condition the power factor shall be maintained as close to the limit as practicable.
| |
| Verify each DG does not trip and voltage is maintained s 5600 V during and following a load rejection 4950 kW and s 5500 kW. BRAIDWOOD UNITS 1 & 2 3.8.l 7 FREQUENCY In accordance with the Surveillance Frequency Contra l Program In accordance with the Surveillance Frequency Control Program (continued)
| |
| Amendment 187 AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.8.1.11 ----------
| |
| This Surveillance shall not be performed in MODE 1, 2, 3, or 4. Verify on an actual or simulated loss of offsite power signal: De energization of ESF buses; Load sheddi ng from ESF buses; and DG auto-starts from standby condition and: energizes permanently connected loads in 10 seconds, energizes auto-connected shutdown loads through the shutdown load sequence timers, maintains steady state voltage 3950 V and 4580 V, maintains steady state frequency 58.8 Hz and 61.2 Hz, and supplies permanently connected and auto-connected shutdown loads for 5 minutes.
| |
| In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.1 -Amendment 165/165 AC Sources Operating 3.8.1 SURVEI LLANCE REOUIREMENTS (conti nued) SR 3.8.1.12 SURVE I LLANCE Verify on an actual or simulated Engineered Safety Feature (ESF) actuation signal each DG auto-starts from standby condition and: a. In 10 seconds achieves voltage 3950 V and frequency 58.8 Hz; b. Achieves steady state voltage 3950 V and 4580 V and frequency 58.8 Hz and 61.2 Hz; and c. Operates for 5 minutes. FREQUENCY In accordance with the Surve-j 11 ance Frequency Control Program SR 3.8.1.13 Verify each DG's automatic trips are bypassed on actual or simulated loss of voltage signal on the emergency bus concurrent with an actual or simulated ESF actuation signal except: a. Engine overspeed; and b. Generator differential current. In accordance with the Surveillance Frequency Control Program SR 3.8.1.14 Momentary transients outside the load range do not invalidate this test. Verify each DG operates for 24 hours: a. For 2 hours loaded 5775 kWand 6050 kW; and b. For the remaining hours of the test loaded 4950 kW and 5500 kW. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 3.8.1 -9 Amendment AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR
| |
| ---NOTES-This Surveillance shall be performed within 5 minutes of shutting down the DG after the DG has operated 2 hours loaded 4950 kW and 5500 kW or until operating temperature has stabilized. Momentary transients outside of load range do not invalidate this test. Verify each DG starts and achieves:
| |
| In accordance the In 10 seconds, voltage 3950 V Surveillance Frequency and frequency 58.8 Hz; and Control ProgramSteady state voltage 3950 V and 4580 V, and frequency 58.8 Hz and 61.2 Hz. SR 3.8.1.16 ----Surveillance shall not be performed in 1, 2, 3, or 4. Verify each DG: In accordance the a. Synchronizes with offsite power source Surveillance while loaded with emergency loads upon Frequency a simulated restoration of offsite Control Program power; Transfers loads to offsite power source; and Returns to ready-to-load operation. (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 &2 Amendment AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SR 3.8.1.17 SURVEILLANCE ------NOTE ---------This Surveillance shall not be performed in MODE 1, 2, 3, or 4. FREQUENCY Verify, with a DG operating in test mode and connected to its bus, an actual or simulated ESF actuation signal overrides the test mode by: a. Returning DG to ready-to-load operation; and b. Automatically energizing the emergency load from offsite power. In accordance with the Surveillance Frequency Control Program SR 3.8.1.18 This Surveillance shall not be performed in MODE I, 2, 3, or 4. Verify interval between each sequenced load block is within +/- 10% of design interval for each safeguards and shutdown sequence timer. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.8.1 -11 Amendment AC Sources-Operating
| |
| | |
| ====3.8.1 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE FREQUENCY SR 3.8.1.19 -----------------NOTE----------
| |
| ----Surveillance shall not be performed in 1, 2, 3, or 4. Verify on an actual or s-imulated loss of In accordance offsite power signal in conjunction with an the actual or simulated ESF actuation signal: Surveillance Frequency De-energization of ESF buses; Control Program Load shedding from ESF buses; and DG auto-starts from standby condition and: energizes permanently connected loads in 10 seconds, energizes auto-connected emergency loads through the safeguards sequence timers, achieves steady state voltage 3950 V and 4580 V, achieves steady state frequency 58.8 Hz and 61.2 Hz, and supplies permanently connected and auto-connected emergency loads for 5 minutes. In accordance standby condition, each DG achieves:
| |
| SR 3.8.1.20 Verify when started simultaneously from the Surveillance Frequency and frequency 58.8 Hz; and In 10 seconds, voltage 3950 V Control Program Steady state voltage 3950 V and 4580 V, and frequency 58.8 Hz and 61.2 Hz. BRAIDWOOD
| |
| -UNITS 1 &2 3.8.1 -Amendment 165/165 AC Sources -Shutdown 3.8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources- Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE: a. One qualified circuit between the offsite transmission network and the onsite Class lE AC electrical power distribution subsystem(s) required by LCO 3.8.10."Distribution Systems -Shutdown":
| |
| and b. One Diesel Generator (DG) capable of supplying one division of the onsite Class lE AC electrical power distribution subsystem(s) required by LCO 3.8.10.APPLICABILITY:
| |
| MODES 5 and 6.During movement of irradiated fuel assemblies.
| |
| ACTIONS-NOTE LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. Required qualified NOTE --circuit inoperable.
| |
| Enter applicable Conditions and Required Actions of LCO 3.8.10. with one required division de-energized as a result of Condition A.A.1 Declare affected Immediately required feature(s) with no offsite power available inoperable.
| |
| OR (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.2 -1 Amendment 98 AC Sources -Shutdown 3.8.2 ACTIONS CONDITION E REQUIRED ACTION I COMPLETION TIME A. (continued)
| |
| A.2.1 Suspend CORE ALTERATIONS.
| |
| AND A.2.2 Suspend movement of irradiated fuel assemblies.
| |
| AND A.2.3 Initiate action to suspend operations involving positive reactivity additions.
| |
| AND A.2.4 Initiate action to restore required qualified circuit to OPERABLE status.AND A.2.5 Declare affected Low Temperature Overpressure Protection (LTOP)feature(s) inoperable.
| |
| Immediately Immediately Immediately Immediately Immediately (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.2 -2 Amendment 98 AC Sources -Shutdown 3.8.2 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. Required DG B.1 Suspend CORE Immediately inoperable.
| |
| ALTERATIONS.
| |
| AND B.2 Suspend movement of Immediately irradiated fuel assemblies.
| |
| AND B.3 Initiate action to Immediately suspend operations involving positive reactivity additions.
| |
| AND B.4 Initiate action to Immediately restore required DG to OPERABLE status.AND B.5 Declare affected LTOP Immediately feature(s) inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.2 -3 Amendment 98 AC Sources -Shutdown 3.8.2 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.2.1 -------------
| |
| --NOTE-----
| |
| -The following SRs are not required to be performed:
| |
| SR 3.8.1.3 SR 3.8.1.14 SR 3.8.1.9 SR 3.8.1.15 SR 3.8.1.10 SR 3.8.1.16 SR 3.8.1.11 SR 3.8.1.18 SR 3.8.1.13 SR 3.8.1.19.For AC sources required to be OPERABLE, the In accordance following SRs are applicable:
| |
| with applicable SRs SR 3.8.1.1 SR 3.8.1.11 SR 3.8.1.2 SR 3.8.1.12 SR 3.8.1.3 SR 3.8.1.13 SR 3.8.1.4 SR 3.8.1.14 SR 3.8.1.5 SR 3.8.1.15 SR 3.8.1.6 SR 3.8.1.16 SR 3.8.1.7 SR 3.8.1.18 SR 3.8.1.9 SR 3.8.1.19.SR 3.8.1.10 BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.2- 4 Amendment 98 Diesel Fuel Oil 3.8.3 3.8 ELECTRICAL POWER SYSTEMS 3.8.3 Diesel Fuel Oil LCO 3.8.3 The stored diesel fuel oil required Diesel Generator shall (DG).be within limits for each APPLICABILITY:
| |
| When associated DG is required to be OPERABLE.ACTIONS I 1n rr Separate Condition entry is allowed 11MU I I-for each DG.CONDITION REQUIRED ACTION COMPLETION TIME A. One or more DGs with A.1 Restore stored fuel 48 hours stored fuel volume oil volume to within< 44,000 gal and limits.> 41,138 gal in storage tank(s).B. One or more DGs with B.1 Restore fuel oil 7 days stored fuel oil total total particulates particulates not within limit.within limit.C. One or more DGs with C.1 Restore stored fuel 30 days new fuel oil. oil properties to properties not within within limits.( tmits.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.3 -1 Amendment 98 Diesel Fuel on 3.8.3 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time of Conditions A, B, or C not met. OR One or more DGs with diesel fuel oil not within limits for reasons other than Condition A, B, or C. D.1 Declare associated DG inoperable.
| |
| Immediately SURVEILLANCE SURVE I LLANCE FREQUENCY SR 3.8.3.1 Verify each DG fuel oil storage tank(s) contains 44,000 gal of fuel. In accordance with the Surveillance Frequency Control Program SR 3.8.3.2 Verify fuel oil properties of new and stored fuel oil are tested in accordance with, and maintained within the limits of, the Diesel Fuel Oil Testing Program. In accordance with the Diesel Fuel Oil Testing Program SR 3.8.3.3 Check for and each fuel oil remove accumulated water from storage tank. In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.8.3 -2 Amendment DC Sources-Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources-Operating LCO 3.8.4 APPLICABILITY:
| |
| Division 11(21) and Division 12(22) DC electrical power subsystems shall be OPERABLE and not crosstied to the opposite unit.MODES 1, 2, 3, and 4.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One battery charger A.1 Crosstie 2 hours.-inoperable.
| |
| opposite-unit bus with associated OPERABLE battery charger to the affected division.AND A.2 Restore battery 2 hours terminal voltage to greater than or equal to the minimum established float voltage.AND A.3 Verify battery float Once per 12 current < 3 amps. hours AND A.4 Restore battery 7 days charger to OPERABLE status.(continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.4 -1 Amendment SEP 1 9 124 202 DC Sources-Operating
| |
| | |
| ====3.8.4 ACTIONS====
| |
| (continued)
| |
| B. One DC electrical B.1 Open at least one 204 hours power division crosstie breaker crosstied to between the crosstied opposite-unit DC divisions.
| |
| electrical power subsystem that has an inoperable battery charger, while opposite unit is in MODE 1, 2, 3, or 4.C. One DC electrical C.1 ---------NOTE--------
| |
| power division Only required when crosstied to opposite unit has an opposite-unit DC inoperable battery.electrical power subsystem with an inoperable source, Verify opposite-unit Once per whi -opsosite unit is DC bus load 12 hours in MODE , 6, or < 200 amps.defueled.AND C.2 Open at least one 7 days crosstie breaker between the crosstied divisions.
| |
| D. One DC electrical D.1 Restore DC electrical 2 hours power subsystem power subsystem to inoperable for reasons OPERABLE status.other than Condition A, B, or C.E. Required Action and E.1 Be in MODE 3. 6 hours Associated Completion Time not met. AND E.2 Be in MODE 5. 36 hours I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.4 -2 Amendment 124 CEP 1 9 2002 DC Sources-Operating
| |
| | |
| ====3.8.4 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is greater In accordance than or equal to the minimum established with the float voltage. Surveillance Frequency Control Program SR 3.8.4.2 Verify each battery charger supplies a load In accordance equal to the manufacturer's rating at with the greater than or equal to the minimum Surveillance established float voltage for 8 hours. Frequency Control Program OR Verify each battery charger can recharge the battery to the fully charged state within 24 hours while supplying the largest coincident demands of the various continuous steady state loads, after a battery discharge to the bounding design basis event discharge state. SR 3.8.4.3 ----------NOTES-------1. The modified performance discharge test in SR 3.8.6.6 may be performed in lieu of the service test in SR 3.8.4.3. 2. This Surveillance shall not be performed in MODE 1, 2, 3, or 4. In accordance Verify battery capacity is adequate to supply, and maintain OPERABLE status, the with the Surveillance required emergency loads for the design Frequency duty cycle when subjected to a battery Control Program servi ce test. BRAIDWOOD
| |
| -UN ITS 1 & 2 3.8.4 -3 Amendment 165/165 DC Sources-Shutdown 3.8.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 -DC Sources-Shutdown LCO 3.8.5 One DC electrical power subsystem shall be OPERABLE.I--------------
| |
| :----NOTE----------------------------
| |
| The required DC electrical power subsystem may be crosstied to the opposite unit, when the opposite unit is in MODE 1, 2, 3, or 4 with an inoperable battery charger.I I APPLICABILITY:
| |
| MODES 5 and 6, During movement of irradiated fuel assemblies.
| |
| ACTIONS-------------------
| |
| NOTE-------------------------------------
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One required DC A.1 Declare affected Immediately electrical power required feature(s) subsystem inoperable inoperable.
| |
| for reasons other than Condition B. OR (continued)
| |
| I I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.5 -1 Amendment 124 SEP 19 29 O DC Sources-Shutdown
| |
| | |
| ====3.8.5 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2.1 Suspend CORE Immediately ALTERATIONS.
| |
| AND A.2.2 Suspend movement of Immediately irradiated fuel assemblies.
| |
| AND A.2.3 Initiate action to Immediately suspend operations involving positive reactivity additions.
| |
| AND A.2.4 Initiate action to Immediately restore required DC electrical power subsystem to OPERABLE status.AND A.2.5 Declare affected Low Immediately Temperature Overpressure Protection feature(s) inoperable.(continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.5 -2 Amendment 124 SEP 19 2M2 DC Sources-Shutdown
| |
| | |
| ====3.8.5 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME B. One required DC B.1 ---------NOTE--------
| |
| electrical power Only required when subsystem crosstied to opposite unit has an opposite-unit DC inoperable battery.electrical power subsystem with an inoperable source, Verify opposite-unit Once per while opposite unit is DC bus load is 12 hours in MODE 5, 6, or < 200 amps.defueled.AND B.2 Open at least one 7 days crosstie breaker between the crosstied divisions.
| |
| SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.5.1 -------------------
| |
| NOTE--------------------
| |
| The following SRs are not required to be performed:
| |
| SR 3.8.4.2 and SR 3.8.4.3.For DC sources required to be OPERABLE, the In accordance following SRs are applicable:
| |
| with applicable SRs SR 3.8.4.1 SR 3.8.4.2 SR 3.8.4.3 BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.5 -3 Amendment 124 SEP 1 q Mt Battery Parameters 3.8.6 3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Parameters I LCO 3.8.6 APPLICABILITY:
| |
| Battery parameters for Division 11(21) and Division 12(22)batteries shall be within limits.When associated DC electrical power subsystems are required to be OPERABLE.I ACTIONS------------------------------------
| |
| NOTE------------------------------------
| |
| Separate Condition entry is allowed for each battery.CONDITION REQUIRED ACTION COMPLETION TIME A. One battery with one A.1 Perform SR 3.8.4.1. 2 hours or more cells with float voltage AND< 2.07 V.A.2 Perform SR 3.8.6.1 2 hours AND A.3 Restore affected cell 24 hours float voltage to> 2.07 V.B. One battery with float B.1 Perform SR 3.8.4.1 2 hours current > 3 amps.AND B.2 Restore battery float 12 hours current to < 3 amps.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.6 -1 Amendment 124 SEP 19 2 Battery Parameters
| |
| | |
| ====3.8.6 ACTIONS====
| |
| (continued)
| |
| C. -------NOTE---------
| |
| Required Action C.2 must be completed if electrolyte level was below the top of plates.------------
| |
| NOTE-------------
| |
| Required Actions C.1 and C.2 are only applicable if electrolyte level was below the top of plates.One battery with one or more cells with electrolyte level less than minimum established design limits.C.1 AND C.2 AND C.3 Restore affected cell electrolyte level to above the top of plates.8 hours 12 hours 31 days Verify no leakage.evidence of Restore affected cell electrolyte level to greater than or equal to minimum established design limits.D. One battery with D.1 Restore pilot cell 12 hours pilot cell electrolyte electrolyte temperature to temperature less than greater than or equal minimum established to minimum design limits. established design limits.E. Two batteries with E.1 Restore battery 2 hours battery parameters parameters for one not within limits. battery to within limits.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.6 -2 Amendment 124 SEP 19 2X02 Battery Parameters
| |
| | |
| ====3.8.6 ACTIONS====
| |
| (continued)
| |
| CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and associated Completion Time of Condition A, B, C, D or E not met. One battery with one or more cells with float voltage < 2.07 V and float current > 3 amps. F.1 Declare associated battery inoperable.
| |
| Immediately SURVEILLANCE SURVEI LLANCE FREQUENCY SR 3.8.6.1 --------NOTE Not required to be met when battery terminal voltage is less than the minimum established float voltage of SR 3.8.4.1. Verify each battery float current is S 3 amps. In accordance with the Surveillance Frequency Control Program SR 3.8.6.2 Verify each battery pilot cell float voltage is 2.07 V. In accordance with the Surveillance Frequency Control Program SR 3.8.6.3 Verify each battery cell electrolyte level is greater than or equal to minimum established design limits. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD UNITS 1 &2 3.8.6 3 Amendment 165/165 Battery Parameters
| |
| | |
| ====3.8.6 SURVEILLANCE====
| |
| | |
| REQUIREIVIEIHS (cont-inued)
| |
| SURVEI LLANCE FREQUENCY SR 3.8.6.4 Verify each battery pilot cell electrolyte temperature is greater than or equal to minimum established design limits. In accordance with the Surveillance Frequency Control Program SR 3.8.6.5 Verify each battery cell float voltage is ?: 2.07 V. In accordance with the Surveillance Frequency Control Program (continued)
| |
| BRAIDWOOD
| |
| -LIN ITS 1 & 2 3.8.6 -4 Amendment 165/165 Battery Parameters
| |
| | |
| ====3.8.6 SURVEILLANCE====
| |
| | |
| REQUIREMENTS (continued)
| |
| SURVEILLANCE SR 3.8.6.6 --------NOTE--This Surveillance shall not be performed in MODE 1, 2, 3, or Verify battery capacity is 80% of manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
| |
| In accordance with the Surveillance Frequency Control Program AND 12 months when battery shows degradation or has reached 85% of the expected 1 i fe with capacity < 100% of manufacturer's rating 24 months when battery has reached 85% of the expected life with capaci ty 100% of manufacturer's rating BRAIDWOOD
| |
| -UNITS 1 &2 3.8.6 -5 Amendment 165/165
| |
| -Inverters-Operating 3.8.7 3.8 ELECTRICAL POWER SYSTEMS 3.8.7 Inverters-Operating LCO 3.8.7 APPLICABILITY:
| |
| Four instrument bus inverters shall be OPERABLE.MODES 1, 2, 3, and 4.ACTIONS ._ ._ = _ _CONDITION REQUIRED ACTION COMPLETION TIME A. One instrument bus A.1 --------NOTE-inverter inoperable.
| |
| Enter applicable Conditions and Required Actions of LCO 3.8.9,"Distribution Systems-Operating" with any instrument bus de-energized.
| |
| Restore inverter to 7 days OPERABLE status.B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.7 -1 Amendment 129 Inverters-Operating
| |
| | |
| ====3.8.7 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE SR 3.8.7.1 Verify correct inverter voltage and breaker alignment to AC instrument buses.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.8.7 -2 Amendment Inverters-Shutdown 3.8.8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Inverters-Shutdown LCO .3.8.8 Two inverters shall be OPERABLE.I I APPLICABILITY:
| |
| MODES 5 and 6, During movement of irradiated fuel assemblies.
| |
| ACTIONS-------------------
| |
| NOTE-------------------------------------
| |
| LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One -or more required A.1 Declare affected -Immediately inverters inoperable.
| |
| required feature(s) inoperable.
| |
| OR__ (continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.8 -1 Amendment 124 SEP 19 2S2 ACTIONS CONDITION REQU I RED ACTI A. (continued)
| |
| A.2.1 Suspend CORE ALTERATIONS.
| |
| AND A.2.2 Suspend movement of i rradi ated fuel assemblies.
| |
| AND A.2.3 Initiate action to suspend operations involving positive reactivity additions.
| |
| AND A.2.4 Initiate action to restore required inverters to OPERABLE status. AND A.2.5 Declare affected Low Temperature Overpressure Protection feature(s) inoperable.
| |
| Inverters-Shutdown
| |
| | |
| ====3.8.8 COMPLETION====
| |
| Irrmediately Irrmediately Irrmediately Irrmediately Irrmediately SURVEILLANCE SR 3.8.8.1 Verify correct inverter voltage and breaker alignment to required AC instrument buses.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.8.8 -2 Amendment 165/165 Distribution Systems -Operating 3.8.9 3.8 ELECTRICAL POWER SYSTEMS 3.8.9 Distribution Systems -Operating LCO 3.8.9 The following AC. DC. and AC instrument bus electrical power distribution subsystems shall be OPERABLE for the applicable unit: Unit 1 Unit 2 A. Division 11 AC Subsystem 4.16 kV Bus 141 480 volt Bus 131X Division 11 AC Instrument Bus Subsystem A. Division 21 AC Subsystem 4.16 kV Bus 241 480 volt Bus 231X Division 21 AC Instrument Bus Subsystem=Instrument Bus 111 Instrument Bus 113 Division 11 DC Subsystem Instrument Bus 211 Instrument Bus 213 Division 21 DC Subsvstem 125 VDC Bus 111 B. Division 12 AC Subsystem 4.16 kV Bus 142 480 volt Bus 132X Division 12 AC Instrument Bus Subsystem 125 VDC Bus 211 B. Division 22 AC.Subsystem 4.16 kV Bus 242 480 volt Bus 232X Division 22 AC Instrument Bus Subsvstem Instrument Bus 112 Instrument Bus 114 Division 12 DC Subsystem Instrument Bus 212 Instrument Bus 214 Division 22 DC Subsystem 125 VDC Bus 112 125 VDC Bus 212 APPLICABILITY:
| |
| MODES 1. 2. 3. and 4.S 1 & 2 3.8.9.-1 BRAIDWOOD
| |
| -UNIT!Amendment 98 Distribution Systems -Operating 3.8.9 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One AC electrical A.1 Restore AC electrical 8 hours power distribution power distribution subsystem inoperable.
| |
| subsystem to OPERABLE AND status.16 hours from discovery of failure to meet LCO B. One AC instrument bus B.1 Restore AC instrument 2 hours electrical power bus electrical power distribution subsystem distribution AND inoperable.
| |
| subsystem to OPERABLE status. 16 hours from discovery of failure to meet LCO C. One DC electrical C.1 Restore DC electrical 2 hours power distribution power distribution subsystem inoperable.
| |
| subsystem to OPERABLE AND status.16 hours from discovery of failure to meet LCO D. Required Action and D.1 Be in MODE 3. 6 hours associated Completion Time of Condition A. AND B. or C not met.D.2 Be in MODE 5. 36 hours (continued)
| |
| I BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.9 -2 Amendment 104 & 104*OCT 1 3 %399 Di stri buti on Systems-Operat-j ng 3.8.9 ACTI (INS ( cant in ued ) CONDITION REQUIRED ACTION COMPLETION TIME E. Two electrical power distribution subsystems inoperable that result in a loss of safety function.
| |
| E.1 Enter LCD 3.0.3. Immediately SURVEILLANCE REQUIREMENTS SURVEI LLANCE SR 3.8.9.1 Verify correct breaker alignments and voltage to AC, DC, and AC instrument bus electrical power distribution subsystems.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.8.9 3 Amendment 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 following AC. DC, and AC instrument bus electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE for the applicable unit.Unit 1 Unit 2 A. Division 11 AC Subsystem 4.16 kV Bus 141 480 volt Bus 131X Division 11 AC Instrument Bus Subsystem A. Division 21 AC Subsystem 4.16 kV Bus 241 480 volt Bus 231X Division 21 AC Instrument Bus Subsystem Instrument Bus 111 Instrument Bus 113 Division 11 DC Subsystem Instrument Bus 211 Instrument Bus 213 Division 21 DC Subsystem 125 VDC Bus 111 B. Division 12 AC Subsystem 4.16 kV Bus 142 480 volt Bus .132X Division 12 AC Instrument Bus Subsystem 125 VDC Bus 211 B. Division 22 AC Subsystem 4.16 kV Bus 242 480 volt Bus 232X Division 22 AC Instrument Bus Subsystem Instrument Bus 112 Instrument Bus 114 Division 12 DC Subsystem Instrument Bus 212 Instrument Bus 214 Division 22 DC Subsystem 125 VDC Bus 112 125 VDC Bus 212 APPLICABILITY:
| |
| MODES 5 and 6.During movement of irradiated fuel assemblies.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.10 -1 Amendment 98 Distribution Systems -Shutdown 3.8.10 ACTIONS-NOTE LCO 3.0.3 is not applicable.
| |
| CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A.1 Declare associated Immediately AC, DC. or AC supported required instrument bus feature(s) electrical power inoperable.
| |
| distribution subsystems OR inoperable.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.10 -2 Amendment 98 Distribution Systems -Shutdown 3.8.10 ACTIONS CONDITION
| |
| -- REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.2.1 Suspend CORE ALTERATIONS.
| |
| AND A.2.2 Suspend movement of irradiated fuel assemblies.
| |
| AND A.2.3 Initiate action to suspend operations involving positive reactivity additions.
| |
| AND A.2.4 AND A.2.5 Initiate actions to restore required AC.DC, and AC instrument bus electrical power distribution subsystem(s) to OPERABLE status.Declare associated required residual heat removal train(s)inoperable and not in operation.
| |
| Immediately Immediately Immediately Immediately Immediately Immediately AND A.2.6 Declare affected Low Temperature Overpressure Protection feature(s) inoperable.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.10 -3 Amendment 98 Distribution SU RV ElL LANC E REQU I SR 3.8.10.1 Verify correct breaker alignments and voltage to required AC, DC, and AC -j nst rument bus elect ri ca 1 powe r distribution subsystems.
| |
| In accordance with the Surve-Ill ance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.8.10-4 Amendment Boron Concentration 3.9.1 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.1 Boron====
| |
| Concentration LCO 3.9.1 Boron concentrations of the Reactor Coolant System, the refueling canal, and the refueling cavity shall be maintained within the limit specified in the COLR. APPLICABILITY:
| |
| MODE 6. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Boron concentration not within limit. A.l Suspend CORE ALTERATIONS.
| |
| Immediately AND A.2 Suspend positive reactivity additions.
| |
| Immediately AND A.3 Initiate action to restore boron concentration to within limit. Immediately SURVEILLANCE SURVEI LLANC SR 3.9.1.1 Verify boron concentration is within the limit specified in the COLR.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.9.1 -1 Amendment Unborated Water Source Isolation Valves 3.9.2 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.2 Unborated====
| |
| | |
| Water Source Isolation Valves LCO 3.9.2 Each valve secured in used to isolate unborated water sources shall be the closed position.APPLICABILITY:
| |
| ACTIONS MODE 6.NOTEa -for each unborated water Separate valve.Condition entry is allowed source isolation CONDITION REQUIRED ACTION COMPLETION TIME A. -- NOTE- -- A.1 Suspend CORE Immediately Required Action A.3 ALTERATIONS.
| |
| must be completed whenever Condition A AND is entered.__ A.2 Initiate actions to Immediately secure valve in One or more valves not closed position.secured in closed position.
| |
| AND A.3 Perform SR 3.9.1.1. 4 hours BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.2-.1 Amendment 98 Unborated Water Source Isolation Valves 3.9.2 SURVEILLANCE REQUIREMENTS SURVEI SR 3.9.2.1 Verify each valve that isolates unborated water sources is secured in the closed position.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.9.2 2 Amendment Nuclear Instrumentation 3.9.3 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.3 Nuclear====
| |
| Instrumentation LCO 3.9.3 APPLICABILITY:
| |
| Two source range neutron flux monitors shall be OPERABLE.MODE 6.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required source A.1 Suspend CORE Immediately range neutron flux ALTERATIONS.
| |
| monitor inoperable.
| |
| A.2 Suspend positive Immediately reactivity additions.
| |
| B. Two required source B.1 Initiate action to Immediately range neutron flux restore one source monitors inoperable.
| |
| range neutron flux monitor to OPERABLE status.AND B.2 Perform SR 3.9.1.1. Once per 12 hours I I BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.3 -1 Amendment 102 & 102 JUN 0 2 1999 Nuclear Instrumentation
| |
| | |
| ====3.9.3 SURVEILLANCE====
| |
| | |
| REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Perform CHANNEL CHECK. In accordance with the Surveillance Frequency Control Program SR 3.9.3.2 Neutron detectors are excluded from CHANNEL CALIBRATION.
| |
| Perform CHANNEL CALIBRATION.
| |
| In accordance with the Survei 11 ance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 &2 3.9.3 2 Amendment Containment Penetrations 3.9.4 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.4 Containment====
| |
| | |
| Penetrations LCD 3.9.4 The containment penetrations shall be in the following status: a. One door in the personnel air lock closed and the equipment hatch held in place 4 bolts; b. One door in the emergency air lock closed; and c. Each penetration providing direct access from the containment atmosphere to the outside atmosphere closed by a manual or automatic isolation valve, blind flange, or equivalent.
| |
| ----------------------------NOTE----------------------------
| |
| LCD 3.9.4.a is not required to be met when in compliance with LCD 3.7.13, "Fuel Handling Building Exhaust Filter Plenum (FHB) Ventilation System," or its associated Conditions and Required Actions. APPLICABILITY:
| |
| During movement of RECENTLY IRRADIATED FUEL assemblies within containment.
| |
| ACTIONS CONDITION A. One or more containment penetrations not in required status. BRAIDWOOD
| |
| -UNITS 1 & 2 A.l REQUIRED ACTION Suspend movement of RECENTLY IRRADIATED FUEL assemblies within containment.
| |
| 3.9.4-1 COMPLETION TIME Immediately Amendment 1 7 8 SURVEILLANCE REQUIREMENTS SR 3.9.4.1 SURVEILLANCE Verify each required containment penetration is in the required status. BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.4-2 Containment Penetrations
| |
| | |
| ====3.9.4 FREQUENCY====
| |
| | |
| In accordance with the Surveillance Frequency Control Program Amendment 1 7 8 RHR and Coolant Circulation-High Water Level 3.9.5 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.5 Residual====
| |
| Heat Removal MRHR) and Coolant Circulation-High Water Level LCO 3.9.5 One RHR loop shall be OPERABLE and in operation.
| |
| ---NOTE----, The required RHR loop may be removed s 1 hour per 8 hour period, provided permitted that would cause reduction System boron concentration.
| |
| from operation for no operations are of the Reactor Coolant APPLICABILITY:
| |
| MODE 6 with the water level 2 23 ft above the top of reactor vessel flange.ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. RHR loop requirements A.1 Suspend operations Immediately not met. involving a reduction in reactor coolant boron concentration.
| |
| AND A.2 Suspend loading Immediately irradiated fuel assemblies in the core.AND A.3 Initiate action to Immediately satisfy RHR loop requirements.
| |
| AND (continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.5 -1 Amendment 98 ACTIONS RHR and Coolant Circulation-High Water Level 3.9.5 CONDITION REQUIRED ACTION COMPLETION TIME A. (continued)
| |
| A.4 Close all containment 4 hours penetrations providing direct access from containment atmosphere to outside atmosphere.
| |
| SURVEILLANCE REQUIREMENTS SR 3.9.5.1 SR 3.9.5.2 SURVEILLANCE Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of 1000 gpm. Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water. FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.5 -2 Amendment No. 183 RHR and Coolant Circulation
| |
| -Low Water Level 3.9.6 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.6 Residual====
| |
| Heat Removal (RHR) and Coolant Circulation-Low Water Level LCO 3.9.6 Two RHR loops shall be OPERABLE.
| |
| and one RHR loop shall be in operation.
| |
| ~~- --NOTE -------One required RHR loop may be removed from operation and considered OPERABLE: a. To support filling and draining the reactor cavity when aligned to. or during transitioning to or from, the refueling water storage tank provided the required RHR loop is capable of being realigned to the Reactor Coolant System (RCS): or b. To support required testing provided the required RHR loop is capable of being realigned to the RCS.APPLICABILITY:
| |
| MODE 6 with the water level < 23 ft above vessel flange.the top of reactor ACTIONS CONDITION
| |
| .REQUIRED ACTION COMPLETION TIME A. One or more RHR loops A.1 Initiate action to Immediately inoperable.
| |
| restore RHR loop(s)to OPERABLE status.OR A.2 Initiate action to Immediately establish 2 23 ft of water above the top of reactor vessel flange.(continued)
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.6 -1 Amendment 98 RHR and Coolant Circulation-Low Water Level 3.9.6 ACTIONS (continued)
| |
| CONDITION REQUIRED ACTION B. No RHR loop in operation.
| |
| B.l Suspend operations involving a reduction in reactor coolant boron concentration.
| |
| AND B.2 Initiate action to restore one RHR loop to operation.
| |
| AND B.3 Close all containment penetrations providing direct access from containment atmosphere to outside atmosphere.
| |
| SURVEILLANCE REQUIREMENTS SR 3.9.6.1 SR 3.9.6.2 SR 3.9.6.3 SURVEILLANCE Verify one RHR loop is in operation and circulating reactor coolant at a flow rate of 1000 gpm. Verify correct breaker alignment and indicated power available to the required RHR pump that is not in operation.
| |
| Verify RHR loop locations susceptible to gas accumulation are sufficiently filled with water. COMPLETION TIME Immediately Immediately 4 hours FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program BRAIDWOOD
| |
| -UNITS 1 & 2 3.9.6 -2 Amendment No. 183 Refueling Cavity Water Level 3.9.7 3.9 REFUELING OPERATIONS
| |
| | |
| ====3.9.7 Refueling====
| |
| | |
| Cavity Water Level LCO 3.9.7 Refueling cavity water level shall be maintained 23 ft above the top of reactor vessel flange. APPLICABILITY:
| |
| During movement of irradiated fuel assemblies within conta -j nment . ACTIONS CONDITION REQU I RED ACTI ON COMPLETION TIME A. Refueling cavity water level not within 1 imit. A.l Suspend movement of i rradi ated fuel assemblies within containment.
| |
| Immediately SURVEILLANCE REQUIREMENTS SURVEI LLANCE SR 3.9.7.1 Verify refueling cavity water level is 23 ft above the top of reactor vessel flange.
| |
| In accordance with the Surveillance Frequency Control Program BRAIDWOOD UNITS 1 &2 3.9.7 -1 Amendment Design Features 4.0 4.0 DESIGN FEATURES 4.1 Site 4.1.1 Site Location The site is ]ocated in Reed Township, approximately 20 mi (32 kin)south-southwest of the city of Joliet in northern Illinois.4.1.2 Exclusion Area Boundary (EAB)The EAB shall not be less than 1591 ft (485 meters) from the outer containment wall.4.1.3 Low Population Zone (LPZ)The LPZ shall be a 1.125 mi (1811 meter) radius measured from the midpoint between the two reactors.4.2 Reactor Core 4.2.1 Fuel Assemblies The reactor shall contain 193 fuel assemblies.
| |
| Each assembly, with exceptions as noted below, shall consist of a matrix of Zircaloy or ZIRLO cl-ad fuel rods with an initial composition of natural or slihlY'0ce uranium dioxide (UO ) as fuel material.
| |
| Limited substitutions of zirconium alloy or stainless steel filler rods or vacancies 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 fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in nonlimiting core regions.Up to 8 AREVA NP Advanced Mark-BW(A) fuel assemblies containing M5 alloy may be placed in nonlimiting Unit 1 core regions for evaluation during Cycles 15, 16, and 17.*4.2.2 Control Rod Assemblies The reactor core shall contain 53 control rod assemblies.
| |
| The control material shall be silver indium cadmium, hafnium, or a mixture of both types.BRAIDWOOD
| |
| -UNITS 1 & 24. -1Amnet15 4.0 -1 Amendment 145 Design Features 4,0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality The spent fuel storage racks are designed and shall be maintained, as applicable, with: a. Fuel assemblies having a maximum U-235 enrichment of 5.0 weight percent;b. For Holtec spent fuel pooi storage racks, k,,-, 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Holtec International Report flI-982094, "Criticality Analysis for Byron/Braidwood Rack Installation Project," Project No. 80944, 1998;c. For Holtec spent fuel pool storage racks, a nominal 10.888 inch north-south and 10.574 inch east-west center to center distance between fuel assemblies placed in Region 1 racks;and'd. For Holtec spent fuel pool storage racks, a nominal 8.97 inch center to center distance between fuel assemblies placed in Region 2 racks.*4.3.2 Drainage The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation 410 ft, 0 inches.4.3.3 Capacity The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 2984 fuel assemblies.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 240 2Amnet14 4.0 -2 Amendment 145 Responsibility 5.1 5.0 ADMINISTRATIVE CONTROLS 5.1 Responsibility 5.1.1 The station manager shall be responsible for overall facility operation and shall delegate in writing the succession to this responsibility during his absence.5.1.2 A Senior Reactor Operator (SRO) shall be responsible for the control room command function while either unit is in MODE 1. 2, 3. or 4. For each unit., an SRO may be designated as responsible for the control-room command function.
| |
| While both units are in MODE 5 or 6. or defueled, an individual with an active SRO license or Reactor Operator license shall be designated to assume the control room command function.BRAIDWOOD
| |
| -UNITS 1 & 2 5.1- 1 Amendment 98 Organization 5.2 5X 0-ADMINISTRATIVE-CONTROLS 5.2 Organization" 5.2.1 Onsite and Offsite Organizations Onsite and offsite organizations shall be established for facility operation and corporate management, respectively.
| |
| The onsite and offsite, organizations shall include the-positions for activities affecting safety of the nuclear power plant.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 ela a ,ionships, and job descri ptions for key personnel positions, or in equivalent forms of documentation.
| |
| These requirements, including the generic titles of those personnel fulfilling the responsibilities of the positions delineated in these Technical Specifications, shall be documented in the Quality Assurance Program;b. The station manager shall be responsible for overall safe operationof the plant and shall have control over those onsite activities necessary for safe operation and maintenanceof the plant;C. The Chief Nuclear Officer shall be responsible 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, or perform health physics or quality assurance functions, may report to theappropriate onsite manager; however, these individuals
| |
| .shall have sufficient organizational freedom to ensure their independence from operating pressures.
| |
| BRAIWOOD UN ITS 1. & 2.5.2 -1 Amendment 147 Organization 5.2 5.2 Organization Facility Staff The facility staff organization shall include the following:
| |
| : a. A total of three non-licensed operators for the two units is required all conditions.
| |
| At least one of the required non-licensed operators shall be assigned to each unit. b. Shift crew composition may be less than the minimum of 10 CFR 50.54(m)(2)(i) and 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours in order to unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew to within the minimum requirements.
| |
| : c. A radiation protection technician shall be on site when fuel is in the reactor. The position may be vacant for not more than 2 hours, in order to provide for unexpected absence, provided immediate action is taken to fill the required position.
| |
| : d. Del eted. e. The operations manager or the supervisor in charge of the operations shift crews shall hold an SRO license. f. The Shift Technical Advisor (STA) shall provide advisory technical support to the Shift Manager in the areas of thermal hydraulics, reactor engineering, and plant analysis with to the safe operation of the facility.
| |
| In addition, the STA shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shi ft. BRAT DWOOD -UN ITS 1 & 2 5.2 -Amendment 1
| |
| | |
| ===5.0 ADMINISTRATIVE===
| |
| | |
| CONTROLS 5.3 Facility Staff Qualifications Facility Staff Qualifications 5.3 5.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971, with the following exceptions:
| |
| : 1) either the senior health physics supervisor or lead health physicist, shall meet or exceed the qualifications for "Radiation Protection Manager" in Regulatory Guide 1.8, September 1975, and 2) the licensed operators who shall comply only with the requirements of 10 CFR 55. BRAIDWOOD
| |
| -UNITS 1 & 2 5.3-1 Amendment 173 Procedures 5.4 5.0 ADMINISTRATIVE CONTROLS 5.4 Procedures
| |
| | |
| ====5.4.1 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. Section 7.1: c. Fire Protection Program implementation:
| |
| and d. All programs specified in Specification 5.5.BRAIDWOOD
| |
| -UNITS 1 & 2 5.4 -I Amendment
| |
| : 98.
| |
| Programs and Manuals 5.5 5.0 ADMINISTRATIVE CONTROLS 5.5 Programs and Manuals The following programs shall be established, implemented, and maintained.
| |
| | |
| ====5.5.1 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;b. The ODCM shall also contain the radioactive effluent controls and radiological environmental monitoring activities, and descriptions of the information that should be included in the Annual Radiological Environmental Operating, and Radi6active Effluent Release Reports required by Specification 5.6.2 and Specification 5.6.3: and c. Licensee initiated changes to the ODCM: 1. Shall be documented and records of reviews performed shall be retained.
| |
| This documentation shall contain: i. sufficient information to support the change(s)together with the appropriate analyses or evaluations justifying the change(s), and ii. a determination that the change(s) maintain the levels of radioactive effluent control required by 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. pr setpoint calculations:
| |
| : 2. Shall become effective after the approval of the station manager: and BRAIDWOOD
| |
| -UNITS 1 & 2 5.5- 1 Amendment 98 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1 Offsite Dose Calculation Manual (ODCM) (continued)
| |
| : 3. Shall be submitted toW 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 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 recirculation portions of the Containment Spray, Safety Injection, Chemical and Volume Control, and Residual Heat Removal. The program shall include the following:
| |
| : a. Preventive maintenance and periodic visual inspection requirements; and b. Integrated leak test requirements for each system at least once per 18 months.The provisions of SR 3.0.2 are applicable.
| |
| 5.5.3 Deleted.BRAIDW0OD -UNITS 1 & 2 5.5 -2 Amendment I.51 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 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 shall be contained in the ODCM, shall be implemented by procedures, and shall include remedial actions to be taken whenever the program limits are exceeded.
| |
| The programinclude the following elements: 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; Limitations on the concentrations of radioactive material released in liquid effluents to unrestricted areas, conforming to 10 times the concentrations stated in 10 CFR 20, Appendix B, Table 2, Column 2 (to paragraphs 20.1001 -20.2402); Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the ODCM; 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; Determination of cumulative dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the [lDCM at least every 31 days. Determination of projected dose contributions from radioactive effluents in accordance with the methodology in the aDeM at least every 31 days; BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 --Amendment 156 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 Radioactive Effluent Controls Program (continued)
| |
| : 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 re1eases of radioactivity when the projected doses in a period of 31 days would exceed 2% of the guidelines for the annual dose or dose commitment.
| |
| conforming to 10 CFR 50.Appendix I: g. Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the site boundary conforming to the following:
| |
| : 1. For noble gases: 5 a dose rate of 500 mrem/yr to the whole body and 5 a dose rate of 3000 mrem/yr to the skin, and 2. For Iodine-131.
| |
| Iodine-133.
| |
| Tritium. and for all radionuclides in particulate form with half lives> 8 days: 5 a dose rate of 1500 mrem/yr to any organ: 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 190.5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR. Section 3.9.cyclic and transient occurrences to ensure that components are maintained within the design limits.BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -4 Amendment 98 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 Pre-Stressed Concrete Containment Tendon Surveillance Program This program provides controls for monitoring any tendon degradation in pre-stressed concrete containments, including effectiveness of its corrosion protection medium, to ensure containment structural integrity.
| |
| The program shall include baseline measurements prior to initial operations.
| |
| The Tendon Surveillance Program, inspection frequencies, and acceptance criteria shall be in accordance with Section XI, Subsection IWL of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 10 CFR 50.55a, except where an alternative, exemption, or relief has been authorized by the NRC. Determining stressing forces for inspections shall be consistent with the recornendat ions of Regulatory Guide 1.35.1, July 1990. The provisions of SR 3.0.3 are applicable to the Tendon Surveillance Program inspection frequencies.
| |
| | |
| ====5.5.7 Reactor====
| |
| Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel in general conformance with the recommendations of Regulatory Position c.4.b of Regulatory Guide 1.14, Revision 1, August 1975. For reactor coolant pump motor serial numbers 4S88P961 and IS88P961, in lieu of Regulatory Position c.4.bCl) and c.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flyWheel to the circle of one-half the outer radius or a surface examination CMT and/or PT) of exposed surfaces of the removed flywheel may be conducted at approximately 10 year intervals coinciding with the Inservice Inspection schedule as required by ASME Section XI. For all other reactor coolant pump motors, in lieu of Regulatory Position c.4.bCl) and c.4.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheelto the circle of one-half the outer radius or a surface examination CMT and/or PT) of exposed surfaces of the removed flywheel may be conducted at an interval not to exceed 20 years. BRAIDWOOD
| |
| -UNITS 1 &2 5.5 -5 Amendment 163 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.8 Inservice Testing Proqram This program provides controls Class 1, 2, and 3 components.
| |
| following: ,or inservice testing of ASME Code The program shall include the a. Testing frequencies applicable to the ASME Operation and Maintenance of Nuclear Power Code) and applicable Addenda as follows: Code for Plants (ASME OM ASME OM Code and applicable Addenda terminology for inservice testing activities I Requi red Frequencies for performing inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years At At least once per least once per 7 days 31 days.At least once per 92 days At At At least least least once once once per 184 days per 276 days per 366 days At least once per 731 days;b. The provisions of SR 3.0.2 are applicable to the above required ,Frequencies and to other normal and accelerated Frequencies specified.
| |
| as 2 years or less in the Inservice Testing Program 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 the requirements of OM Code shall be construed to supersede any Technical Specification.
| |
| I BPA!DWOOD
| |
| -UNITS I & 2 5,5- 6 Amendment 153 Programs and Manuals 5.5 5.5 Programs and Manuals Steam Generator (SG) Program A Steam Generator Program shall be established and implemented to ensure SG tube integrity is maintained.
| |
| In addition, the Steam Generator Program shall include the following:
| |
| : a. Provisions for condition monitoring assessments.
| |
| Condition assessment means an evaluation of the "as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The "as found" condition refers to the condition of the tubing during an SG inspection outage, as determined from the inservice inspection results or by other means, prior to the plugging of tubes. Condition monitoring assessments shall be conducted during each outage during which the SG tubes are inspected or plugged to confirm that the performance criteria are being met. b. Performance criteria for SG tube integrity.
| |
| SG tube integrity shall be maintained by meeting the performance criteria for tube structural integrity, accident induced leakage, and operational LEAKAGE. 1. Structural integrity performance criterion:
| |
| All service steam generator tubes shall retain structural i ntegr-j ty over the full range of normal operati ng
| |
| ("including startup, operation in the power range, standby, and cool down), all anticipated transients included in the design specification, and design basis accidents.
| |
| This includes retaining a safety factor of 3.0 against burst under normal steady state power operation primary-to-secondary pressure differential and a safety factor of 1.4 against burst applied to the design basis accident primary-to-secondary pressure differentials.
| |
| Apart from the above requirements, additional loading conditions associated with the design basis accidents, or combination of accidents in accordance with the design licensing basis, shall also be evaluated to determine if the associated loads contribute significantly to burst or collapse.
| |
| In the assessment of tube integrity, those loads that do significantly affect burst. or collapse shall be determi ned and assessed combination with the loads due to pressure with a safety factor of 1.2 on the combined primary loads and 1.0 on axial secondary loads. BRAIDWOOD UNITS 1 &2 5.5 --Amendment 172/172 Proqrams and Manuals -5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued)
| |
| : 2. Accident induced leakage performance criterion:
| |
| The primary to secondary accident induced leakage rate for any design basis accident, other than a SG tube rupture, shall not exceed the leakage rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to exceed a total of 1 gpm for all SGs. 3. The operational LEAKAGE performance criteria is specifi ed in LCO 3.4.l3, "Res Operat i ana 1 LEAKAGE." c. Provisions for SG tube plugging criteria.
| |
| Tubes found by inservice inspection to contain flaws with a depth equal to or exceeding 40% of the nominal wall thickness shall be plugged. The following alternate tube plugging criteria shall be applied as an alternative to the 40% depth based criteria:
| |
| For Unit 2, tubes with service-induced flaws located greater than 14.01 inches below the top of the tubesheet do not require plugging.
| |
| Tubes with service-induced flaws located in the portion of the tube from the top of the tubesheet to 14.01 inches below the top of the tubesheet shall be plugged upon detection.
| |
| Amendment 172/172 BRAIDWOOD
| |
| -UNITS 1 &2 5.5 8 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued)
| |
| : d. Provisions for SG tube inspections.
| |
| Periodic SG tube inspections shall be performed.
| |
| The number and portions of the tubes inspected and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws, axial and circumferential cracks) that may be present along the length of the tube, from the tube-to-tubesheet weld at the tube inlet to the tubesheet weld at the tube outlet, and that may satisfy the applicable tube plugging criteria.
| |
| For Unit 2, portions of the tube below 14.01 inches from the top of the tubesheet are excl uded from thi s requ-j rement. The tube-to-tubesheet weld is not part of the tube. In addition to meeting the requirements of d.l, d.2, and d.3 below, the inspection scope, inspection methods, and inspection intervals shall be such as to ensure that SG tube integrity is mainta-ined until the next SG inspection.
| |
| A degradation assessment shall be performed to determine the type and location of flaws to which the tubes may be susceptible and, based on this assessment, to determine which inspection methods need to be employed and at what 1 ocati ons. 1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation.
| |
| : 2. For Unit 1, after the first refueling outage following SG installation, inspect each SG at least every 72 effective full power months or at least every third refueling outage (whichever results in more frequent inspections).
| |
| In addition, the minimum number of tubes inspected at each scheduled inspection shall be the number of tubes in all SGs divided by the number of SG inspection outages scheduled in each inspection peri od as defi ned -j n a, b, c, and d below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated.The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected in the inspection period after the determination that a new form of degradation could BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 9 Amendment 172/1 72 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued) potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage. After the first refueling outage following SG installation, inspect 100% of the tubes during the next 144 effective full power months. This constitutes the first inspection period; During the next 120 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; During the next 96 effective full power months, inspect 100% of the tubes. This constitutes the third inspection period; and During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the fourth and subsequent inspection periods. For Uni t 2, after the fi rst refue l-j ng outage fo 11 owi ng SG installation, inspect each SG at least every 48 effective full power months or at least every other refueling outage (whichever results in more frequent inspections).
| |
| In addition, the minimum number of -j nspected at each schedul ed i nspecti on shall be the number of tubes in all SGs divided by the number of inspection outages scheduled in each inspection period as defined in a, b, and c below. If a degradation assessment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of detecting this type of degradation at this location and that may satisfy the applicable tube plugging criteria, the minimum number of locations inspected with such a capable inspection technique during the remainder of the inspection period may be prorated.The fraction of locations to be inspected for this potential type of degradation at this location at the end of the inspection period shall be no less than the ratio of the number of times the SGis scheduled to be BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -Amendment 172/172 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.9 Steam Generator (SG) Program (continued) inspected in the inspection period after the determ-ination that a new form of degradation could potentially be occurring at this location divided by the total number of times the SG is scheduled to be inspected in the inspection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG inspection outage in an inspection period and the subsequent inspection period begins at the conclusion of the included SG inspection outage. After the first refueling outage following SG installation, inspect 100% of the tubes during the next 120 effective full power months. This constitutes the first inspection period; Dur-ing the next 96 effective full power months, inspect 100% of the tubes. This constitutes the second inspection period; and During the remaining life of the SGs, inspect 100% of the tubes every 72 effective full power months. This constitutes the third and subsequent inspection periods. For Unit 1, if crack indications are found in any SG then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent -inspections).
| |
| For Unit 2, if crack indications are found in any SG tube from 14.01 inches below the top of the tubesheet on the hot leg side to 14.01 inches below the top of the tubesheet on the cold leg side, then the next inspection for each affected and potentially affected SG for the degradation mechanism that caused the crack indication shall not exceed 24 effective full power months or one refueling outage (whichever results in more frequent -i nspecti ons). If definitive information, such as from examination of a pulled tube, diagnostic non-destructive testing, or engineering evaluation indicates that a crack-like indication is not associated with a crack(s), then the indication need not be treated as a crack. Provisions for monitoring operational primary to secondary LEAKAGE. BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 Amendment 172/172 Programs and Manuals 5.5 5.5 Programs andManuals 5.5.10 Secondary Water Chemistry Proqram This program provides controls for monitoring secondary wa~ter chemistry to inhibit SG tube degradation.
| |
| The program shall inc ude: a. Identification of a sampling schedule for the critical variables and control points for these variables;
| |
| : b. Identification of the procedures used to measure the values of the critical variables;, c. Identification of process samplingpoints, which shall include monitoring-the discharge of the condensate pumps for evidence of condenser inleakage;
| |
| : d. Procedures for the recording and management of data;e. Procedures defining corrective actions for all off control point chemistry conditions; and f. A procedure identifying the authority responsible for the interpretation of the data and the sequence and timing of administrative events, which is required to initiate corrective action.BRAIDWOOD
| |
| -UNITS I & 2 5.5 -12 Amendment 150 Programs and.Manuals 5.5, 5..5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP)A program shall be established to implement the following required testing of Enqineered Safety Feature (ESF) filter ventilation systems at the frequencies specified in conformancewith Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR.a. Demonstrate for each of the ESF filter systems that an inplace test of the High Efficiency Particulate Air (HEPA) filters shows a penetration specified below when tested in conformance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR, at the system flow rate specified below. Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.10.4, 3.7.12.4, and 3.7.13.5, as applicable:
| |
| ESF Ventilation System Control Room Ventilation (VC)Filtration System (makeup)Nonaccessibl e Area Exhaust Filter Plenum Ventilation System (after structural maintenance of the HEPA filter housings)Nonaccessi bl e Area Exhaust Filter Plenum Ventilation System (for reasons other than structural maintenance of the HEPA filter housings)Fuel Handling Building Exhaust Filter Plenum (FHB)Ventilation System Flow Rate Penetration
| |
| > 5400 cfm and< 6600 cfm> 60,210 cfm'and< 73,590 cfm per train, and> 20,070 cfm and< 24,530 cfm per bank< 0.05%< 1%< 1%< 1%> 60,210< 73,590 train cfm and cfm per> 18,900 cfm and< 23,100 cfm BRATIDWOOD
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| -UNITS I & 2 5.5 -13 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)
| |
| : b. Demonstrate for each of the ESF filter systems that an inplace test of the charcoal adsorber shows a bypass specified below when tested in conformance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR, at the system flow rate specified below. Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.10.4, 3.7.12.4, and' 3.7.13.5, as applicable:
| |
| ESF Ventilation System Flow Rate Bypass VC Filtration System (makeup)VC Filtration System*(reci rculati on, charcoal bedt after complete or partial replacement)
| |
| VC Filtration System (reci rcul ation for reasons other than complete or partial charcoal bed replacement)
| |
| Nonaccessible Area Exhaust Filter Plenum Venti l ation System (after structural maintenance of the charcoal adsorber housings)Nonaccessi bl e Area Exhaust Filter Plenum Ventilation System (for reasons other than structural maintenance of the charcoal adsorber housings)FHB Ventilation System> 5400 cfm and< 6600 cfm> 44,550 cfm and< 54,450 cfm> 44,550 cfm and< 54,450 cfm> 60,210 cfm and< 73,590 cfm per train, and> 20,070 cfm and< 24,530 cfm per bank< 0.1%< 2%< 1%< 1%< 1%> 60,210< 73,590 train cfm and cfm per> 18,900 cfm and< 23,100 cfm per train BRAiDWOOD
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| -UNITS 1 & 2 5.5 -14 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testinq Program (VFTP) (continued)
| |
| : c. Demonstrate for each of the ESF filter 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 conformance with Regulatory Guide 1.52, Revision-2, ANSI N510-1980, and ASTM D3803-1989, with any exceptions noted in Appendix A of the UFSAR, at a temperature of 30 0 C and a Relative Humidity (RH) specified below: ESF Ventilation System Penetration RH VC Filtration System 2.0% 70%(makeup)VC Filtration System 4% 70%(reci rcul ati on)Nonaccessible Area 4.5% 70%Exhaust Filter Plenum Ventilation System FHB Ventilation System 10% 95%d. Demonstrate for each of the ESF filter systems that the pressure drop across the combined HEPA filters and the charcoal adsorbers is < 6 inches of water gauge when tested in conformance with Regulatory Guide 1.52, Revision 2, and ANSI N510-1980, with any exceptions noted in Appendix A of the UFSAR, at the system flow rate specified below. Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.10.4, 3.7.12.4, and 3.7.13.5, as applicable:
| |
| ESF Ventilation System Flow Rate VC Filtration System > 5400 cfm and _< 6600 cfm (makeup)Nonaccessible Area _ 60,210 cfm and Exhaust Filter Plenum 5 73,590 cfm per train Ventilation System FHB Ventilation System > 18,900 cfm and< 23,100 cfm BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -15 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.11 Ventilation Filter Testing Program (VFTP) (continued)
| |
| : e. Demonstrate for each of the ESF filter systems that a bypass test of the combined HEPA filters and damper leakage shows a total bypass specified below at the system flow rate specified below. Verification of the specified flow rates may be accomplished during the performance of SRs 3.7.12.4 and 3.7.13.5, as applicable:
| |
| ESF Ventilation System Flow Rate Bypass Nonaccessible Area Exhaust Filter Plenum Ventilation System FHB Ventilation Systemt60,210 cfm and! 73,590 cfm per train 18,900 cfm and< 23,100 cfm<1%< 1%f. Demonstrate that the heaters for each of the ESF filter systems dissipate the value specified below when tested in conformance with ANSI N510-1980, with anyexceptions noted in Appendix A of the UFSAR.ESF Ventilation System Wattage VC Filtration System The provisions of SR 3.0.2 test frequencies.
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| _< 29.9 kW and >_ 24.5 kW and SR 3.0.3 are applicable to the VFTP BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -16 Amendment 1.50 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Explosive Gas and' Storage Tank Radioactivity Monitoring Program This program provides controls for potentially explosive gas mi.t_. ur. .otaed in. t.he waste gas system,Ulte quantity of radioactivity contained in gas decay tanks or fed into the off gas treatment system, and the quantity of radioactivity contained in unprotected outdoor liquid storage tanks. 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." The liquid radwaste quantities shall be determined in accordance with the ODCM.The program shall include: a. The limits for concentrations of hydrogen and oxygen in the waste gas system and a surveillance program to ensure the limits are maintained.
| |
| Such limits shall be appropriate to the system's 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 contained in each gas decay tank and fed into the offgas treatment system is less than the amount that would result in a whole body exposure of 0.5 rem to any individual in an unrestricted area, in the event of an uncontrolled release of the tanks' contents; and c. A surveillance program to ensure that the quantity of radioactivity contained in all outdoor liquid radwaste tanks that are not surrounded by liners, dikes, or walls, capable of holding the tanks' contents and that do not have tank overflows and surrounding area drains connected to the liquid radwaste treatment system is less than the amount that would result in concentrations less than the limits of 10 CFR 20, Appendix B, Table 2, Column 2, at the nearest potable water supply and the nearest surface water supply in an unrestricted area, in the event of an uncontrolled release of the tanks'contents.The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Explosive Gas and Storage Tank Radioactivity Monitoring Program surveillance frequencies.
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| BRAIDWOOD
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| -UNITS I & 2 5.5 -17 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Diesel Fuel Oil Testing ProQram A diesel fuel oil testing program to implement required testing of both new fuel oil and stored fuel oil shall be established.
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| 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, and 3. a clear and bright appearance with proper color or a water and sediment content within limits;b. Other properties of new fuel oil are within limits within 30 days following sampling and addition to storage tanks;and c. Total particulate concentration of the fuel oil is 1 10 mg/l when tested every 31 days.The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Diesel Fuel Oil Testing Program test frequencies.
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| BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -18 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Technical Specifications (TS) Bases Control ProQram This program provides a means for processing changes to the Bases of these Technical Specifications.
| |
| : a. Changes to the Bases of the TS shaltl be made under appropriate administrative controls and reviews.b. Licensees may make changes to Bases without prior NRC approval provided the changes do not require either of the following:
| |
| : 1. a change in the TS incorporated in the license; or 2. a change to the UFSAR or Bases that requires NRC approval pursuant to 10 CFR 50.59.c. The Bases Control Program shall contain provisions to ensure that the Bases are maintained consistent with the UFSAR.d. Proposed changes that meet the criteria of Specification 5.5.14.b above shall be reviewed and approved by the NRC prior to implementation.
| |
| Changes to the Bases implemented without prior NRC approval shall be provided to the NRC on a frequency consistent with 10 CFR 50.71(e) as modified by approved exemptions.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -19 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Safety Function Determination Program (SFDP)This program ensures loss of safety function is detected and appropriate actions taken, Upon entry, into LCO 3.0.6, an evaluation shall be made to determine if loss of safety function exi~sts.Additionally, other appropriate actions may 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. The SFDP shall contain the following:
| |
| : a. Provisions for cross train 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 system's Completion Time is not inappropriately extended as a result of multiple support system i noperabil i ties; and d. Other appropriate limitations and remedial or compensatory actions.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 the system(s) supported by the inoperable support system is also inoperable; or b. A required system redundant to the system(s) in turn supported by the inoperable supported system is also inoperable; or c. A required system redundant to the support system(s) for the supported systems (a) and (b) above is also inoperable.
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| BRAIDWOOD
| |
| -UNITS 1 & 2-5.5 -20 Amendment 150 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 5.5.16 Safety Function Determination Program (SFDP) (continued)
| |
| 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 LCD in which the loss of safety function exists are required to be entered. Containment Leakage Rate Testing Program A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option 8, as modified by approved exemptions.
| |
| This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, September 1995 and NEI 94-01, Revision 0, as modified by the following exceptions:
| |
| : 1. NEI 94-01 -1995, Section 9.2.3: The first Unit 1 Type A test performed after the October 5, 1998 Type A test sr1a ll be performed no later than October 5, 2013. 2. NEI 94-01 -1995, Section 9.2.3: In support of the Spring 2014 refueling outage, Unit 2 shall be placed in a MODE of operation where containment is not required to be OPERABLE in accordance with Technical Specification 3.6.1, "Containment," no later than May 4, 2014. The first Unit 2 Type A test performed after the May 4, 1999 Type A test shall be performed prior to entering MODE 4 at the start of Unit 2, Cycle 18. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 42.8 psig for Unit 1 and 38.4 psig for Unit 2 The maximum allowable containment leakage rate, L 3 , at P 0 , shall be 0.20% of containment air weight per day. Leakage Rate acceptance criteria are: a. Containment leakage rate acceptance criterion 1.0 During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type 8 and C tests and< 0.75 La for Type A tests; and BRAIDWOOD
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| -UNITS 1 & 2 5.5-21 Amendment 175 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16 Containment Leakage Rate Testing Program (continued)
| |
| : b. Air lock testing acceptance criteria are: I. Overall air lock leakage rate is 0.05 La when tested at Pa; and 2. For each door, seal leakage rate is: i. < 0.0024 L, when pressurized to 3psig, and ii. < 0.01 La, when pressurized to 1 10 psig.The provisions of SR 3.0.2 do not apply-to the test frequencies specified in the Containment Leakage Rate Testing Program.The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.5.5.17 Battery Monitoring and Maintenance Program This program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries For Stationary-Applications," or of the battery manufacturer of the following:
| |
| : a. Actions to restore battery cells with float voltage< 2.13 V, and b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.5.5.18 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Ventilation (VC) Filtration System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge.
| |
| The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident.
| |
| The program shall include the following elements: BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -22 Amendment iso Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Control Room Envelope Habitability Program (continued)
| |
| : a. The definition of the CRE and CRE boundary.b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
| |
| : c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with. the testing methods and at the Frequencies specified in'Sections C.1 and C.2 of Regulatory Gbide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.d. Measurement of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one train of the VC Filtration System, operating at the flow rate required by the VFTP, at a Frequency of 18 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 18 month assessment of the CRE boundary.e., The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph
| |
| : c. The unfilitered air inleakage limit for radiological challenges is the inleakage flow rate assumend in the licensing basis analyses of DBA consequences.
| |
| Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
| |
| BRAIDWOOD
| |
| -UNITS 1 & 2 5.5 -23 Amendment 150 Programs Manuals 5.5 5.5 Programs and Manuals Surveillance Frequency Control Program This program provides controls for Surveillance Frequencies.
| |
| The program shall ensure that Survei 11 ance Requi rements specifi ed in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met. a. The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program. b. Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with NEI "Risk-Informed Method for Control of Surveillance Frequenci es," Revi si on 1. c. The Provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program. BRAIDWOOD
| |
| -UNITS 1 &2 5.5 -Amendment Reporting Requirements 5.6 5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements The following reports shall be submitted in accordance with 10 CFR 50.4.5.6.1 (Deleted)
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| I BRAIDWOOD
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| -UNITS 1 & 2 5.6 -1 Amendment 136 Reporting Requirements 5.6 5.6 Reporting Requirements
| |
| | |
| ====5.6.2 Annual====
| |
| Radiological Environmental Operating Report-------------------------------
| |
| NOTE-------------------------------
| |
| A single submittal may be made for the facility.
| |
| The submittal should combine sections common to both units.The Annual Radiological Environmental Operating Report covering the operation of the facility 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.5.6.3 Radioactive Effluent Release Report-------------------
| |
| NOTE-------------------------------
| |
| A single submittal may be made for the facility.
| |
| The submittal shall combine sections connon to both units.The Radioactive Effluent Release Report covering the operation of the facility 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 facility.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 Part 50, Appendix I, Section IV.B.1.5.6.4 (Deleted)BRAIDWOOD
| |
| -UNITS I & 2 5.6 -2 Amendment 136 Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 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:
| |
| SL 2.1.1. "Reactor Core SLs": LCO 3.1.1. "SHUTDOWN MARGIN (SDM)": LCO 3.1.3. "Moderator Temperature Coefficient":
| |
| LCO 3.1.5. "Shutdown Bank Insertion Limits": LCO 3.1.6. "Control Bank Insertion Limits";LCO 3.1.8. "PHYSICS TESTS Exceptions
| |
| -MODE 2";LCO 3.2.1. "Heat Flux Hot Channel Factor (Fo(Z))";LCO 3.2.2. "Nuclear Enthalpy Rise Hot Channel Factor (F1H)";LCO 3.2.3. "AXIAL FLUX DIFFERENCE (AFD)";LCO 3.2.5. "Departure from Nucleate Boiling Ratio (DNBR)";LCO 3.4.1. "RCS Pressure, Temperature.
| |
| and Flow Departure from Nucleate Boiling (DNB) Limits"; and LCO 3.9.1. "Boron Concentration":
| |
| I b. The analytical methods used to determine the core operating limits shall be those previously reviewed and a pproved by the NRC. specifically those described in the following documents:
| |
| : 1. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluations Methodology," July 1985.2. WCAP-12472-P-A. "BEACON Core Monitoring and Operations Support System," August 1994.3. NFSR-0016. "Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods." July 1983.4. NFSR-0081, "Commonwealth Edison Company Topical Report on Benchmark of PWR Nuclear Design Methods Using the Phoenix-P and ANC Computer Codes." July 1990.BRAIDWOOD
| |
| -UNITS 1 & 2 5.6- 3 Amedgept 15
| |
| | |
| ===5.6 Reporting===
| |
| | |
| Requirements Reporting Requirements 5.6 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)
| |
| : 5. CornEd letter from D. Saccomando to the Office of Nuclear Reactor Regulation dated December 21, 1994, transmitting an attachment that documents applicable sections of WCAP-11992/11993 and CornEd application of the UET methodology addressed in "Additional Information Regarding Application for Amendment to Facility Operating Licenses-Reactivity Control Systems." 6. WCAP-16009-P-A, Revision 0, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," January 2005. 7. WCAP-10079-P-A, "NOTRUMP, A Nodal Transient Small Break and General Network Code," August 1985. 8. WCAP-10054-P-A, "Westinghouse Small Break ECCS Evaluation Model using NOTRUMP Code," August 1985. 9. WCAP-10216-P-A, Revision 1, "Relaxation of Constant Axial Offset Control -F 0 Surveillance Technical Specification," February 1994. 10. WCAP-8745-P-A, "Design Bases for the Thermal Overpower
| |
| ,1T and Thermal Overtemperature
| |
| ,1T Trip Functions," September 1986. 11. WCAP-14565-P-A, "VIPRE-01 Modeling and Qualification for Pressurized Water Reactor Non-LOCA Hydraulic Safety Analysis," October 1999; 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; and d. The COLR, including any midcycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC. BRAIDWOOD
| |
| -UNITS 1 & 2 5.6-4 Amendment No. 174 Reporti ng Requirements 5.6 5.6 Reporting Requirements
| |
| | |
| ====5.6.6 Reactor====
| |
| Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)a. RCS pressure and temperature limits for heat up, cooldown, low temperature operation, criticality, and hydrostatic testing as well as heatup and cooldown rates, and Power Operated Relief Valve (PORV) lift settings shall be established and documented in the PTLR for the following:
| |
| LCO 3.4.3, "RCS Pressure and Temperature (P/T) Limits," and LCO 3.4.12, "Low Temperature Overpressure Protection (LTOP)System";b. The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the fol lowing documents:
| |
| : 1. NRC letter dated January 21, 1998, "Byron Station Units 1 and 2, and Braidwood Station, Units 1 and 2, Acceptance for Referencing of Pressure Temperature Limits Report," 2. NRC letter dated August 8, 2001, "Issuance of Exemption from the requirements of 10 CFR 50.60 and Appendix G for Byron Station, Units 1 and 2 and Braidwood Station, Units 1 and 2," 3. Westinghouse WCAP-16143, "Reactor Vessel Closure Head/Vessel Flange Requirements Evaluation for Byron/Braidwood Units 1 and 2," and 4. The PTLR will contain the complete identification for each of the TS referenced Topical Reports used to prepare the PTLR (i.e., report number, title, revision, date, and any supplements);
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| and c. The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.5.6.7 Post Accident Monitoring Report When a report is required by Condition C or G of LCO 3.3.3, "Post Accident Monitoring (PAM) Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.BRAIDWOOD
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| -UNITS 1 & 2 5.6-5S Amendment 142 Reporting Requirements 5.6 5.6 Reporting Requirements Tendon Surveillance Report Any abnormal degradation of the containment structure detected during tests required by the Pre Stressed Concrete Containment Tendon Surveillance Program shall be reported in the Inservice Summary Report in accordance with 10 CFR 50.55a and ASME Section XI. Steam Generator (SG) Tube Inspection Report A report shall be submitted within 180 days after the initial entry into MODE following completion of an inspection performed in accordance with Specification 5.5.9, Steam Generator (SG) Program.The report shall include: The scope of inspections performed on each SG, Degradation mechanisms found, Nondestructive examination techniques utilized for each mechanism, d. Location, orientation (if linear), and measured sizes (if available) of service induced indications, Number of tubes plugged during the inspection outage for each degradation mechanism, I The number and percentage of tubes plugged to date, and the I effective plugging percentage in each steam generator, The results of condition monitoring, including the results of tube and in-situ testing, BRAIDWOOD
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| -UNITS 1 &2 5.6 -Amendment 172/172 Reporting Requirements 5.6 5.6 Reporting Requirements
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| ====5.6.9 Steam====
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| Generator (SG) Tube Inspection Report (continued)
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| : h. For Unit 2, the operational primary to secondary leakage ratel observed (greater than three gallons per day) in each steam generator (if it is not practical to assign the leakage to an individual steam generator, the entire primary to secondary leakage should be conservatively assumed to be from one steam generator) during the cycle preceding the inspection which is the subject of the report, i. For Unit 2, the calculated accident induced leakage rate from I the portion of the tubes below 14.01 inches from the top of the tubesheet for the most limiting accident in the most limiting SG. In addition, if the calculated accident induced leakage rate from the most limiting accident is less than 3.11 times the max"imum operational primary to secondary leakage rate, the report should describe how it was determined, and j. For Unit 2, the results of monitoring for tube axial displacement (slippage).
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| If slippage is discovered, the implications of the discovery and corrective action shall be provided.
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| BRAIDWOOD
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| -UNITS 1 &2 5.6 -7 Amendment 172/172 High Radiation Area 5.7 5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area This Specification provides alternate methods for controlling access to high radiation areas and does not apply to very high radiation areas as defined in 10 CFR 20.5.7.1 Pursuant to 10 CFR 20. paragraph 20.1601(c).
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| in lieu of the requirements of 10 CFR 20.1601. each high radiation area, as defined in 10 CFR 20. in which the intensity of radiation is> 100 mnrem/hr but 5 1000 mrem/hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP) or equivalent document that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures.
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| Individuals qualified in radiation protection procedures or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates 5 1000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
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| : a. A radiation monitoring device that continuously indicates the radiation dose rate in the area.b. A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received..
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| Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.BRAIDWOOD
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| -UNITS 1 & 2 5.7 -.1 Amendment 98 High Radiation Area 5.7 5.7 High Radiation Area 5.7.1 (continued)
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| : c. An individual qualified in radiation protection procedures with a radiation dose rate monitoring device. who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified in the RWP or equivalent document.5.7.2 In addition to the requirements of Specification
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| ====5.7.1. areas====
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| accessible to personnel with radiation levels > 1000 mrem/hr at 30 cm (12 inches) from the radiation source or from any surface which the radiation penetrates shall require the following:
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| : a. Doors shall be locked to prevent unauthorized entry and shall not prevent individuals from leaving the area. In place of locking the door, direct or continuous electronic surveillance that is capable of preventing unauthorized entry may be used. The keys shall be maintained under the administrative control of the Shift Manager on duty or health physics supervision:
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| : b. Personnel access and exposure control requirements of activities being performed within these areas shall be specified by an approved RWP or equivalent document that includes specification of radiation dose rates in the immediate work area(s) and other appropriate radiation protection equipment and measures;c. Each person entering the area shall be provided with an alarming radiation monitoring device that continuously integrates the radiation dose rate (such as an electronic dosimeter).
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| Surveillance and radiation monitoring by health physics personnel may be substituted for an alarming dosimeter:
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| BRAIDWOOD
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| -UNITS 1 & 2 5.7 -2 Amendment 98 High Radiation Area 5.7 5.7 High Radiation Area 5.7.2 (continued)
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| : d. For individual high radiation areas accessible to personnel with radiation levels of > 1000 mrem/hr at 30 cm (12 inches)that are located within large areas such as reactor containment, where no enclosure exists for purposes of locking, and where no enclosure can be reasonably constructed around the individual area, that individual area shall be barricaded, conspicuously posted, and a flashing light shall be activated as a warning device: and e. Except for individuals qualified in radiation protection procedures, or personnel escorted by such individuals, entry into such areas shall be made after dose rates in the area have been determined and entry personnel are knowledgeable of them. Individuals escorted will receive a pre-job briefing prior to entry into such areas.BRAIDWOOD
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| -UNITS 1 & 2 5.7 -3 Amendment 98 APPENDIX B TO FACILITY OPERATING LICENSE NOS. NPF-72 & NPF-77 I EXELON GENERATION COMPANY, LLC BRAIDWOOD STATION UNITS 1 & 2 DOCKET NOS. 50-456 AND 50-457 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)
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| I Amendment 138 BRAIDWOOD STATION UNITS 1 and 2 ENVIRONMENTAL PROTECTION PLAN (NON-RADIOLOGICAL)
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| TABLE OF CONTENTS Section 1.0 2.0 2.1 2.2 3.0 3.1 3.2 3.3 4.0 4.1 5.0 5.1 5.2 5.3 5.4 Objectives of the Environmental Protection Plan Environmental Protection Issues Aquatic Issues Terrestrial Issues ...Consistency Requirements.
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| .Plant Design and Operation Reporting Related to the NPDES Permits and State Certification
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| ....Changes Required for Compliance with Other Environmental Regulations
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| .Environmental Conditions Unusual or Important Environmental Events Administrative Procedures
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| .Review and Audit Records Retention
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| .Changes in Environmental Protection Plan.Plant Reporting Requirements Page 1-1 2-1 2-1 2-1 3-1 3-1 3-2 3-2 4-1 4-1 5-1 5-1 5-1 5-1 5-2 Amendment 138
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| ===2.0 Environmental===
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| Protection Issues In the FES-OL dated June, 1984, the staff considered the environmental impacts associated with the operation of the two unit Braidwood Station. No environmental issues were identified which required study or license conditions to resolve environmental concerns and to assure adequate protection of the environment.
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| ===2.1 Aquatic===
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| Issues No specific aquatic issues were raised by the staff in the FES-OL.Aquatic matters are addressed by the effluent limitations, monitoring requirements and the Section 316(b) demonstration requirement contained in the effective NPDES permit issued by the Federal or State permitting authority.
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| The NRC will rely on these agencies for regulation of matters involving water quality and aquatic biota.2.2 Terrestrial Issues No specific terrestrial issues were raised by the staff in the FES-OL.2-1 Amendment 138
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| A proposed change, test or experiment shall be deemed to involve an unreviewed environmental question if it concerns:
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| (1) a matter which may result in a significant increase in any adverse environmental impact previously evaluated in the FES-OL, environmental impact appraisals, or in any decisions of the Atomic Safety and Licensing Board; or (2) a significant change in effluents or power level or (3) a matter, not previously reviewed and evaluated in the documents specified in (1) of this Subsection, which may have a significant adverse environmental impact.The licensee shall maintain records of changes in facility design or operation and of tests and experiments carried out pursuant to this Subsection.
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| These records shall include written evaluations which provide bases for the determination that the change, test or experiment does not involve an unreviewed environmental question or constitute a decrease in the effectiveness of this EPP to meet the objectives specified in Section 1.0.3.2 Reporting Related to the NPDES Permit and State Certification The NRC shall be provided with a copy of the current NPDES permit or State Certification within 30 days of approval.
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| Changes to the NPDES permit or State Certification shall be reported to the NRC within 30 days of the date the change is approved.3.3 Changes Required for Compliance with Other Environmental Regulations Changes in plant design or operation and performance of tests or experiments which are either regulated or mandated by other Federal, State, and local environmental regulations are not subject to the requirements of Section 3.1. However, if any environmental impacts of a change are not evaluated under other Federal, State or local environmental regulations, then those impacts are subject to the requirements of Section 3.1.3-2 Amendment 138
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| ===4.0 Environmental===
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| Conditions
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| ===4.1 Unusual===
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| or Important Environmental Events Any occurrence of an unusual or important event that indicates or could result in significant environmental impact causally related to plant operation shall be recorded and reported to the NRC within 24 hours followed by a written report in accordance with Subsection 5.4.2. If an event is reportable under 10 CFR 50.72, then a duplicate immediate report under this-subsection is not required.
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| However, a follow-up written report is required in accordance with Subsection 5.4.2. The following are examples:
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| excessive bird impaction events, onsite plant or animal disease outbreaks, mortality or unusual occurrence of any species protected by the Endangered Species Act of 1973, fish kills, increase in nuisance organisms or conditions, and unanticipated or emergency discharge of waste water or chemical substances.
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| No routine monitoring programs are required to implement this condition.
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| 4-1 Amendment 138
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| ===5.0 Administrative===
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| Procedures
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| ===5.1 Review===
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| and Audit The licensee shall provide for review and audit of compliance with the EPP. The audits shall be conducted independently of the individual or groups responsible for performing the specific activity.
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| A description of the organization structure utilized to achieve the independent review and audit function and results of the audit activities shall be maintained and made available for inspection.
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| ===5.2 Records===
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| Retention Records associated with this EPP shall be made and retained in a manner convenient for review and inspection.
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| These records shall be made available to NRC on request.Records of modifications to station structures, systems and components determined to potentially affect the continued protection of the environment shall be retained until the date of termination of the operating license. All other records relating to this EPP shall be retained for five years or, where applicable, in accordance with the requirements of other agencies.5.3 Changes in Environmental Protection Plan Requests for changes in the EPP shall include an assessment of the environmental impact of the proposed change and a supporting justification.
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| Implementation of such changes in the EPP shall not commence prior to NRC approval of the proposed changes in the form of a license amendment incorporating the appropriate revision to the EPP.5-1 Amendment 138
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| ===5.4 Plant===
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| Reporting Requirements
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| ====5.4.1 Deleted====
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| 5.4.2 Nonroutine Reports A written report shall be submitted to the NRC within 30 days of an occurrence of an unusual or important environmental event. The report shall (a) describe, analyze, and evaluate the event, including extent and magnitude of the impact, and plant operating characteristics, (b) describe the probable cause of the event, (c) indicate the action taken to correct the reported event, (d) indicate the corrective action taken to preclude repetition of the event and to prevent similar occurrences involving similar components or systems, and (e) indicate the agencies notified and their preliminary responses.
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| Events reportable under this subsection which also require reports to other Federal, State or local agencies shall be reported in accordance with those reporting requirements in lieu of the requirements of this subsection.
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| The NRC shall be provided a copy of such report at the same time it is submitted to the other agency.5-2 Amendment 138 145 ADDITIONAL FACILITY OPERATING LICENSE NO. The licensee shall comply with the following conditions on the schedules noted below: Amendment Number Additional Condition The safety limit equation specified in TS 2.1.1.3 regarding fuel centerline melt temperature (Le., less than 5080 of, decreasing by 58 of per 10,000 MWD/MTU burnup as described in WCAP-12610-P-A, "VANTAGE+
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| Fuel Assembly Reference Core Report," April 1995) is valid for uranium oxide fuel without the presence of poisons mixed homogeneously into the fuel pellets. If fuel pellets incorporating homogeneous poisons are used, the topical report documenting the fuel centerline melt temperature basis must be reviewed and approved by the NRC and referenced in this license condition.
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| TS 2.1.1.3 must be modified to also include the fuel centerline melt temperature limit for the fuel with homogeneous poison. During operation in Cycles 15, 16, and 17, up to eight (8) AREVA NP Advanced BW(A) fuel assemblies containing fuel pellets incorporating homogeneous poisons may be placed in non limiting Unit 1 core locations provided the fuel cycle designs are developed such that the TS 2.1.1.3 Safety Limit equation for Westinghouse fuel is bounding.
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| The design basis for the AREVA NP fuel rod centerline melt follows that given in BAW-10162P-A, "TAC03 -Fuel Pin Thermal Analysis Computer Code," October 1989, and BAW-10184P-A, "GDTACO -Urania Gadolinia Fuel Pin Thermal Analysis Code," February 1995. With mentation of the ment AMENDMENT NO. 160 ADDITIONAL FACILITY OPERATING LICENSE NO. The licensee shall comply with the following conditions 011 Ihe schedules floled Amendment Number Additional Condition Implementation Date 146 Upon implementation of Amendment No. 146 adopting TSTF-448, Revision 3, the determination of control room envelope (CRE) unfiltered air inleakage as required by With menlallon of lhe amendment SR accordance with TS 5.5.18.c.(I), the assessment of CRE habitability as required by Specification 5.5.18.c.(ii), and.the measurement of eRE pressure as required by Speclflcatlon 5.5.18.d, shaH be considered met. Following Implementation: (a) The first performance of SR 3.7.10.4, in accordance with SpecifICation 5.5.18.c.(i), shall be within the specified Frequency of 6 years, plus the 18-month anowance of SR 3.0.2, as measured from November 7.2004, the date of the most recent successful tracer gas test, as stated in the February 7,2005 letter response to Generic letter 2003-01, or within the next 18 months if the time period since the most recent successful tracer gas test Is greater than 6 years. (b) The r"sf performance of the periodic assessment of eRE habitability, Specification 5.5.18.c.(ii).
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| shall be within 3 years, pIus the month allowance 01 SR 3.0.2, as measured from November 7,2004, the date of the most recent successful tracer gas test. as staled In the February 7,2005 reUer response to Generic letter 2003-01, or within the next 9 months if the time period since' the most recent successful tracer gas test is greater than 3 years. (c) The first performance of the periodic measurement of eRE pressure, Specfficatlon 5.5.18.d, shall be INilhin 18 months, plus the 138 days allowed by SR 3.0.2, as measured from the date of the most recen" successful pressure measurement test, or within 138 days if not performed previously.
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| AMENDMENT NO. 160}}
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