ML19150A470
Text
GINNA/UFSAR 7 INSTRUMENTATION AND CONTROLS 1
7.1 INTRODUCTION
2 7.1.1 IDENTIFICATION OF SAFETY-RELATED SYSTEMS 2 7.1.2 IDENTIFICATION OF SAFETY CRITERIA 3 7.1.2.1 General Design Criteria 3 7.1.2.2 Compliance with IEEE 279-1971 3 7.1.2.2.1 Design Basis 3 7.1.2.2.2 Requirements 4 7.1.2.2.2.1 Operability 4 7.1.2.2.2.2 Testability 5 7.1.2.2.2.3 Control of Protective Actions 5 7.2 REACTOR TRIP SYSTEM (RTS) 8 7.2.1 DESIGN BASES 8 7.2.1.1 Design Criteria 8 7.2.1.1.1 Fuel Damage Limits 8 7.2.1.1.2 Reliability and Testability 9 7.2.1.1.3 Redundancy and Independence 10 7.2.1.1.4 Effects of Adverse Conditions 10 7.2.1.1.5 Testing While In Operation 11 7.2.1.1.6 Fail Safe Design 11 7.2.1.1.7 Single Failure Criterion 11 7.2.1.2 Seismic Design 12 7.2.1.3 Operating Environment 12 7.
2.2 DESCRIPTION
13 7.2.2.1 Logic Train 14 7.2.2.1.1 Sensors 14 7.2.2.1.2 Process and Nuclear Instrumentation 15 7.2.2.1.3 Protection Cabinets 15 7.2.2.1.4 Logic Relay Cabinets 15 7.2.2.1.5 Trip Breakers 16 7.2.2.2 Reactor Trips 17 7.2.2.2.1 General 17 7.2.2.2.2 Manual Trip 18 7.2.2.2.3 High-Nuclear-Flux (Power Range) Trip 18 7.2.2.2.4 High-Nuclear-Flux (Intermediate Range) Trip 18 Page 1 of 9 Revision 28 5/2019
GINNA/UFSAR 7.2.2.2.5 High-Nuclear-Flux (Source Range) Trip 18 7.2.2.2.6 Overtemperature Delta T Trip 18 7.2.2.2.7 Overpower Delta T Trip 19 7.2.2.2.8 Low Pressurizer Pressure Trip 19 7.2.2.2.9 High Pressurizer Pressure Trip 19 7.2.2.2.10 High Pressurizer Water Level Trip 19 7.2.2.2.11 Low Reactor Coolant Flow Trip 19 7.2.2.2.12 Safety Injection System Actuation Trip 20 7.2.2.2.13 Turbine Trip/Reactor Trip 20 7.2.2.2.14 Low-Low Steam-Generator Water Level Trip 20 7.2.2.3 Interlocks 21 7.2.2.4 Permissive Circuits 21 7.2.2.4.1 P-1 Permissive 21 7.2.2.4.2 P-2 Permissive 21 7.2.2.4.3 P-3 Permissive 22 7.2.2.4.4 P-4 Permissive 22 7.2.2.4.5 P-6 Permissive 22 7.2.2.4.6 P-7 Permissive 22 7.2.2.4.7 P-8 Permissive 22 7.2.2.4.8 P-9 Permissive 22 7.2.2.4.9 P-10 Permissive 23 7.2.2.5 Alarms 23 7.2.2.6 Design Features 23 7.2.2.6.1 Isolation of Redundant Protection Channels 23 7.2.2.6.1.1 Channelized Design 23 7.2.2.6.1.2 Separation 24 7.2.2.6.2 Channel Bypass or Removal from Operation 24 7.2.2.6.3 Capability for Test and Calibration 25 7.2.2.6.4 Information Readout and Indication of Bypass 25 7.2.2.6.5 Physical Isolation 25 7.2.2.6.6 Sensor Line Separation 26 7.2.2.6.7 Instrument Line Identification 26 7.2.3 ANALYSIS 26 7.2.3.1 Reactor Trip System (RTS) and Departure From Nucleate Boiling 26 7.2.3.2 Core Protection System 26 Page 2 of 9 Revision 28 5/2019
GINNA/UFSAR 7.2.3.2.1 Overpower Protection 27 7.2.3.2.2 Overtemperature Protection 27 7.2.4 REACTOR TRIP SIGNAL TESTING 27 7.2.4.1 Analog Channel Testing 28 7.2.4.2 Logic Channel Testing 29 7.2.4.2.1 Planned Tests 29 7.2.4.2.2 Test Procedure 29 7.2.4.2.3 Logic Channel Test Panels 30 7.2.4.3 Trip Breaker Testing and Preventive Maintenance 30 7.2.5 INTERACTION OF CONTROL AND PROTECTION SYSTEMS 30 7.2.5.1 Introduction 30 7.2.5.2 Specific Control and Protection Interactions 31 7.2.5.2.1 Nuclear Flux 31 7.2.5.2.2 Coolant Temperature 31 7.2.5.2.3 Pressurizer Pressure 33 7.2.5.2.4 Pressurizer Level 33 7.2.6 ANTICIPATED-TRANSIENT-WITHOUT-SCRAM MITIGATION 34 SYSTEM ACTUATION CIRCUITRY Table 7.2-1 Table DELETED 37 Table 7.2-2 PERMISSIVE CIRCUITS 38 Table 7.2-3 REACTOR TRIP FUNCTION SETPOINTS 39 7.3 ENGINEERED SAFETY FEATURES SYSTEMS 41 7.3.1 DESIGN CRITERIA 41 7.3.1.1 Protection Systems 41 7.3.1.2 Redundancy and Independence 42 7.3.1.3 Testing While In Operation 43 7.3.1.4 Fail Safe Design 43 7.3.2 SYSTEM DESCRIPTION 44 7.3.2.1 Initiating Circuitry 44 7.3.2.2 System Functions 45 7.3.2.2.1 Steam Line Isolation 45 7.3.2.2.2 Feedwater Line Isolation 45 7.3.2.3 Sensing and Display Instrumentation 46 7.3.2.3.1 Reactor Vessel Level Indication System 46 7.3.2.3.2 Containment Pressure 46 7.3.2.3.3 Containment Sump Level 47 7.3.2.3.4 Accumulator Level and Pressure 47 7.3.2.3.5 Refueling Water Storage Tank Level (RWST) 47 Page 3 of 9 Revision 28 5/2019
GINNA/UFSAR 7.3.2.3.6 Sodium Hydroxide Tank Level and Flow 47 7.3.2.3.7 Safety Injection Pumps Discharge Pressure and Flow 47 7.3.2.3.8 Residual Heat Removal (Low-Head Safety Injection) Flow 47 7.3.2.3.9 Pump Energization 47 7.3.2.3.10 Valve Position 47 7.3.2.3.11 Residual Heat Exchangers 48 7.3.2.3.12 Alarms 48 7.3.2.3.13 Air Coolers 48 7.3.2.3.14 Local Instrumentation 48 7.3.2.4 Engineered Safety Features Reset Controls 48 7.3.3 DESIGN EVALUATION 49 7.3.3.1 Engineered Safety Features Systems Isolation 49 7.3.3.2 Loss of Voltage or Degraded Voltage on Engineered Safety Features Bus 49 7.3.4 TESTING 49 7.3.4.1 Analog Channel Testing 49 7.3.4.2 Logic Channel Testing 50 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 52 7.
4.1 DESCRIPTION
52 7.4.1.1 Reactor Trip System (RTS) 52 7.4.1.2 Auxiliary Feedwater Systems 53 7.4.1.3 Main Steam System 53 7.4.1.4 Service Water System 54 7.4.1.5 Chemical and Volume Control System 54 7.4.1.6 Component Cooling Water System (CCW) 55 7.4.1.7 Residual Heat Removal System 55 7.4.1.8 Electrical Instrumentation and Power Systems 56 7.4.2 EVALUATION 56 7.4.3 EMERGENCY SHUTDOWN CONTROL 56 7.4.3.1 General 56 7.4.3.2 Residual Heat Removal 57 7.4.3.3 Reactivity Control 58 7.4.3.4 Pressurizer Pressure and Level Control 58 7.4.3.5 Electrical Systems 58 7.4.3.6 Startup of Other Equipment 59 7.4.3.7 Indication and Controls Provided Outside the Control Room 59 7.4.3.7.1 Local Panel Indication 59 7.4.3.7.2 Local Motor Controls 60 7.4.3.7.3 Valve Control 60 7.4.3.7.4 Pressurizer Heater Control 61 Page 4 of 9 Revision 28 5/2019
GINNA/UFSAR 7.4.3.7.5 Lighting 61 7.4.3.7.6 Communications 61 7.4.3.7.7 Electrical Systems 61 7.4.4 Post-fire Safe Shutdown (SSD) Capability 61 7.4.4.1 System Description 61 7.4.4.2 DELETED 7.4.4.2.1 DELETED 7.4.4.2.2 DELETED 7.4.4.2.3 DELETED 7.4.4.2.4 DELETED 7.4.4.2.5 DELETED 7.4.4.2.6 DELETED 7.4.4.2.7 DELETED 7.4.4.2.8 DELETED Table 7.4-1 FUNCTIONS FOR SHUTDOWN AND COOLDOWN 63 Table 7.4-2 SAFE SHUTDOWN INSTRUMENTS 64 Table 7.4-3 SAFE SHUTDOWN SYSTEMS POWER SOURCE AND LOCATION 67 Table 7.4-4 Table DELETED 69 7.5 SAFETY-RELATED DISPLAY INSTRUMENTATION 70 7.5.1 CONTROL ROOM 70 7.5.1.1 Description 70 7.5.1.1.1 General 70 7.5.1.1.2 Main Control Board 70 7.5.1.1.3 Other Control Room Displays 71 7.5.1.2 Design Review 72 7.5.2 SAFETY PARAMETER DISPLAY 72 Table 7.5-1 COMPARISON OF GINNA STATION POSTACCIDENT 74 INSTRUMENTATION TO REGULATORY GUIDE 1.97, REVISION 3, CRITERIA 7.6 OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY 90 7.6.1 OVERPRESSURE PROTECTION DURING LOW POWER OPERATION 90 7.6.2 AUXILIARY FEEDWATER SYSTEM AUTOMATIC INITIATION AND 91 FLOW INDICATION 7.6.3 SUBCOOLING METER 91 7.6.4 DIRECT CURRENT POWER SYSTEM BUS VOLTAGE MONITORING 91 AND ANNUNCIATION Page 5 of 9 Revision 28 5/2019
GINNA/UFSAR 7.6.5 REACTOR VESSEL LEVEL INDICATION SYSTEM 92 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 95 7.
7.1 DESCRIPTION
95 7.7.1.1 General 95 7.7.1.1.1 Reactor Control System 95 7.7.1.1.2 Steam Dump Control System 95 7.7.1.1.3 Reactivity Control 96 7.7.1.1.4 Reactor Control System Operation 96 7.7.1.1.5 Pressurizer Pressure and Water Level Control System 97 7.7.1.1.6 Steam Dump System 97 7.7.1.2 Rod Control System 98 7.7.1.2.1 Control Group Control 98 7.7.1.2.1.1 General 98 7.7.1.2.1.2 Rod Control Input Signals 98 7.7.1.2.1.3 Rod Control Program 99 7.7.1.2.2 Shutdown Group Control 100 7.7.1.2.3 Control Rod Drive Performance 100 7.7.1.2.4 Control Rod Power Supply System 100 7.7.1.2.4.1 General 100 7.7.1.2.4.2 Control Rod Power Supply Connections 101 7.7.1.2.5 Control Rod Power Supply Evaluation 102 7.7.1.2.5.1 Alternating Current Power Connections 102 7.7.1.2.5.2 Direct Current Power Connections 103 7.7.1.2.5.3 Evaluation Summary 104 7.7.1.2.6 Rod Position Indication System 105 7.7.1.2.6.1 Microprocessor System 105 7.7.1.2.6.2 Digital System 106 7.7.1.2.6.3 Actual Position Indication 106 7.7.1.2.6.4 Demand Position Indication 106 7.7.1.2.6.5 Rod Deviation Alarm 106 7.7.1.2.7 Pulse-to-Analog Converter 107 7.7.1.2.8 Interlocks and Rod Stops 107 7.7.1.2.9 Rod Insertion Limit Circuit 108 7.7.1.2.10 Rod Drop Protection 108 7.7.1.2.11 Asymmetric Rod Cluster Control Assembly Withdrawal 109 Page 6 of 9 Revision 28 5/2019
GINNA/UFSAR 7.7.1.2.12 Rod Control Cabinet Cooling 110 7.7.1.3 Pressurizer Pressure and Level Control 110 7.7.1.3.1 Pressure Control 110 7.7.1.3.2 Level Control 111 7.7.1.4 Turbine Bypass 111 7.7.1.5 Steam Generator Level Control 112 7.7.1.6 Steam Generator Overfill Protection 114 7.7.2 CONTROL SYSTEM EVALUATION 114 7.7.2.1 Plant Stability 114 7.7.2.2 Step Load Changes Without Turbine Bypass 115 7.7.2.3 Loading and Unloading 115 7.7.2.4 Loss of Load With Turbine Bypass 116 7.7.2.5 Turbine Trip With Reactor Trip 116 7.7.2.6 Control Rod Misalignment 117 7.7.2.6.1 General 117 7.7.2.6.2 Consequences of Rod Misalignment 117 7.7.2.6.3 Analysis of Control Rod Misalignment 118 7.7.2.6.4 Redundant Checks for Control Rod Malfunction 118 7.7.2.6.4.1 Operator Checks 118 7.7.2.6.4.2 Additional Periodic Tests 119 7.7.2.6.4.3 Details of Instrumentation System 119 7.7.2.6.4.4 Power Range Nuclear Instrumentation 119 7.7.2.6.4.5 Thermocouples 120 7.7.2.6.4.6 In-Core Movable Detectors 120 7.7.2.6.4.7 Summary 121 7.7.2.6.5 Expected Instrument Response to Control Rod Misalignment Ginna Station 121 7.7.2.6.6 Plant Startup Tests 122 7.7.3 NUCLEAR INSTRUMENTATION SYSTEM 122 7.7.3.1 Design Basis 122 7.7.3.2 System Design 123 7.7.3.2.1 Source Range Description 124 7.7.3.2.2 Intermediate Range Description 125 7.7.3.2.3 Power Range Description 126 7.7.3.2.4 Dropped Rod Protection 127 7.7.3.2.5 Audio Count Rate Channel 127 Page 7 of 9 Revision 28 5/2019
GINNA/UFSAR 7.7.3.2.6 Recorders 127 7.7.3.2.7 Power Supply 128 7.7.3.2.8 Equipment Locations 128 7.7.3.3 System Evaluation 128 7.7.4 IN-CORE INSTRUMENTATION 128 7.7.4.1 Design Basis 128 7.7.4.2 System Design 128 7.7.4.2.1 General 128 7.7.4.2.2 Thermocouples 129 7.7.4.2.3 Movable Miniature Neutron Flux Detectors 129 7.7.4.2.4 Control and Readout System 130 7.7.5 REACTOR COOLANT TEMPERATURE INDICATION 131 7.7.6 PLANT PROCESS COMPUTER SYSTEM AND SAFETY ASSESSMENT SYS- 132 TEM 7.7.6.1 General 132 7.7.6.2 Plant Process Computer System 133 7.7.6.3 Safety Parameter Display System 134 Table 7.7-1 OUT-OF-PHASE CURRENTS (AMPS) 136 Table 7.7-2 ROD STOPS 137 Table 7.7-3 EXPECTED MAXIMUM VARIATIONS BETWEEN 138 SYMMETRICALLY LOCATED DETECTORS FIGURES Figure 7.2-1 Reactor Protection Systems Figure 7.2-2 Figure DELETED Figure 7.2-3 Figure DELETED Figure 7.2-4 Figure DELETED Figure 7.2-5 Figure DELETED Figure 7.2-6 Figure DELETED Figure 7.2-7 Figure DELETED Figure 7.2-8 Figure DELETED Figure 7.2-9 Figure DELETED Figure 7.2-10 Figure DELETED Figure 7.2-11 Figure DELETED Figure 7.2-12 Design Philosophy to Achieve Isolation Between Channels Figure 7.2-13 Figure DELETED Figure 7.2-14 Channel Configuration (Channel 1 Typical) T avg / T Control and Protection System Page 8 of 9 Revision 28 5/2019
GINNA/UFSAR Figure 7.2-15 Analog System Symbols Figure 7.2-16 Analog Channel Testing Arrangement Figure 7.2-17 Trip Logic Channels Figure 7.2-18 Analog Channels Figure 7.2-19 Logic Channel Test Panels Figure 7.2-20 Electrical Diagram - Undervoltage Coil and Shunt Trip Assembly Figure 7.3-1 Sheet 1 - Figure DELETED Figure 7.3-1 Sheet 2 - Figure DELETED Figure 7.3-2 Figure DELETED Figure 7.3-3 Figure DELETED Figure 7.3-4 Actuation Circuits of Engineered Safety Features Figure 7.3-5 Figure DELETED Figure 7.3-6 Analog and Logic Channel Testing Figure 7.5-1 Control Room Layout Figure 7.7-1 Reactor Control System Figure 7.7-2 Simplified Block Diagram of Reactor Control Systems Figure 7.7-3 Control Group - Rod Drive System Figure 7.7-4 Power Supply to Rod Control Equipment and Control Rod Drive Mechanisms Figure 7.7-4a Illustration of MRPI Indication Figure 7.7-5 Figure DELETED Figure 7.7-6 Nuclear Protection System Figure 7.7-7 Power Range Nuclear Detector Locations Figure 7.7-8 Location of Control Rods and Instrumentation Figure 7.7-9 Power Range Nuclear Instrumentation System Figure 7.7-10 Neutron Detectors and Range of Operation Figure 7.7-11 In-Core Instrumentation - Assembly Figure 7.7-12 Sheet 1 - In-Core Instrumentation, Details Figure 7.7-12 Sheet 2 - In-Core Instrumentation, Details Figure 7.7-13 Typical Arrangement of Moveable Miniature Neutron Flux Detector System Figure 7.7-14 Advanced Digital Feedwater Control System Input Signal Validation Figure 7.7-15 Advanced Digital Feedwater Control System Flow Controller and Cv Demand Figure 7.7-16 Advanced Digital Feedwater Control System Valve Sequence and Tracking Logic Page 9 of 9 Revision 28 5/2019