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| number = ML19150A470
| number = ML19150A470
| issue date = 05/10/2019
| issue date = 05/10/2019
| title = Revision 28 to Updated Final Safety Analysis Report, Chapter 7, Table of Contents
| title = 8 to Updated Final Safety Analysis Report, Chapter 7, Table of Contents
| author name =  
| author name =  
| author affiliation = Exelon Generation Co, LLC
| author affiliation = Exelon Generation Co, LLC
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:GINNA/UFSAR 7           INSTRUMENTATION AND CONTROLS                                   1
{{#Wiki_filter:GINNA/UFSAR Page 1 of 9 Revision 28 5/2019 7
INSTRUMENTATION AND CONTROLS 1  


==7.1         INTRODUCTION==
==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 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==
==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
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  


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 Page 2 of 9 Revision 28 5/2019 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  


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 Page 3 of 9 Revision 28 5/2019 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 SYSTEM ACTUATION CIRCUITRY 34 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  


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.
GINNA/UFSAR Page 4 of 9 Revision 28 5/2019 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==
==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
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  


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 Page 5 of 9 Revision 28 5/2019 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  


GINNA/UFSAR 7.6.5       REACTOR VESSEL LEVEL INDICATION SYSTEM                                92 7.7         CONTROL SYSTEMS NOT REQUIRED FOR SAFETY                               95 7.
===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 INSTRUMENTATION TO REGULATORY GUIDE 1.97, REVISION 3, CRITERIA 74 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 FLOW INDICATION 91 7.6.3 SUBCOOLING METER 91 7.6.4 DIRECT CURRENT POWER SYSTEM BUS VOLTAGE MONITORING AND ANNUNCIATION 91


==7.1      DESCRIPTION==
GINNA/UFSAR Page 6 of 9 Revision 28 5/2019 7.6.5 REACTOR VESSEL LEVEL INDICATION SYSTEM 92 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 95 7.
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
==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


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 Page 7 of 9 Revision 28 5/2019 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  


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}}
===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
 
GINNA/UFSAR Page 8 of 9 Revision 28 5/2019 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-TEM 132 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 SYMMETRICALLY LOCATED DETECTORS 138 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) Tavg / T Control and Protection System
 
GINNA/UFSAR Page 9 of 9 Revision 28 5/2019 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}}

Latest revision as of 02:16, 5 January 2025

8 to Updated Final Safety Analysis Report, Chapter 7, Table of Contents
ML19150A470
Person / Time
Site: Ginna Constellation icon.png
Issue date: 05/10/2019
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML19150A453 List: ... further results
References
Download: ML19150A470 (9)
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Text

GINNA/UFSAR Page 1 of 9 Revision 28 5/2019 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

GINNA/UFSAR Page 2 of 9 Revision 28 5/2019 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

GINNA/UFSAR Page 3 of 9 Revision 28 5/2019 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 SYSTEM ACTUATION CIRCUITRY 34 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

GINNA/UFSAR Page 4 of 9 Revision 28 5/2019 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

GINNA/UFSAR Page 5 of 9 Revision 28 5/2019 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 INSTRUMENTATION TO REGULATORY GUIDE 1.97, REVISION 3, CRITERIA 74 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 FLOW INDICATION 91 7.6.3 SUBCOOLING METER 91 7.6.4 DIRECT CURRENT POWER SYSTEM BUS VOLTAGE MONITORING AND ANNUNCIATION 91

GINNA/UFSAR Page 6 of 9 Revision 28 5/2019 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

GINNA/UFSAR Page 7 of 9 Revision 28 5/2019 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

GINNA/UFSAR Page 8 of 9 Revision 28 5/2019 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-TEM 132 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 SYMMETRICALLY LOCATED DETECTORS 138 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) Tavg / T Control and Protection System

GINNA/UFSAR Page 9 of 9 Revision 28 5/2019 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

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