ML21278A189
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CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE CALVERT CLIFFS UFSAR 7-i Rev. 51 7.0 INSTRUMENTATION AND CONTROL 7.1-1
7.1 INTRODUCTION
7.1-1 7.2 REACTOR PROTECTIVE SYSTEM 7.2-1 7.2.1 GENERAL 7.2-1 7.2.2 DESIGN BASIS 7.2-1 7.2.3 SYSTEM DESCRIPTION 7.2-3 7.2.3.1 High Rate-of-Change of Power 7.2-3 7.2.3.2 Variable Over Power Level 7.2-3 7.2.3.3 Low Reactor Coolant Flow 7.2-4 7.2.3.4 Low Steam Generator Water Level 7.2-6 7.2.3.5 Low Steam Generator Pressure 7.2-6 7.2.3.6 High Pressurizer Pressure 7.2-7 7.2.3.7 Thermal Margin/Low-Pressure Trip 7.2-7 7.2.3.8 Loss of Load 7.2-9 7.2.3.9 High Containment Pressure 7.2-9 7.2.3.10 Manual Trip 7.2-10 7.2.3.11 Axial Flux Offset Trip 7.2-10 7.2.3.12 Asymmetric Steam Generator Load 7.2-10 7.2.4 SIGNAL GENERATION 7.2-10 7.2.4.1 High Rate-of-Change of Power 7.2-10 7.2.4.2 High Power Level 7.2-10 7.2.4.3 Flow, Water Level, Pressure, and Thermal Margin 7.2-11 7.2.4.4 Axial Flux Offset 7.2-11 7.2.5 LOGIC OPERATION 7.2-11 7.2.6 TESTING 7.2-12 7.2.7 SYSTEM EVALUATION 7.2-13 7.2.8 POWER SUPPLY 7.2-16 7.3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEMS 7.3-1 7.3.1 DESIGN BASIS 7.3-1 7.3.1.1 Conformance to Standards 7.3-1 7.3.1.2 Security and Annunciation 7.3-2 7.3.1.3 Seismic Requirements 7.3-3 7.3.1.4 Environmental Requirements 7.3-3 7.3.2 SYSTEM DESCRIPTION 7.3-3 7.3.2.1 Sensor Subsystems 7.3-4 7.3.2.2 Actuation Subsystems 7.3-5 7.3.2.3 Undervoltage, Blocking, and Sequencing 7.3-14 7.3.3 SYSTEM SURVEILLANCE 7.3-14 7.3.3.1 Remote Annunciation 7.3-14
CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE CALVERT CLIFFS UFSAR 7-ii Rev. 51 7.3.3.2 Local Sensor Channel Surveillance 7.3-15 7.3.3.3 Local Actuation Channel Surveillance 7.3-15 7.3.4 ELECTRICAL POWER SUPPLY 7.3-15 7.3.5 SYSTEM EVALUATION 7.3-16 7.3.6 MANUAL TESTING FEATURES 7.3-17 7.3.6.1 Bistable Trip Test 7.3-17 7.3.6.2 Testing of Refueling Water Tank Level Switches 7.3-17 7.3.6.3 Actuation Channel Trip Test 7.3-17 7.3.6.4 Undervoltage, Blocking, and Sequencing Tests 7.3-17 7.3.7 PORTIONS NOT TESTED AT POWER 7.3-18 7.4 REGULATING SYSTEMS 7.4-1 7.4.1 REACTOR REGULATING SYSTEM 7.4-1 7.4.1.1 General 7.4-1 7.4.1.2
System Description
7.4-1 7.4.2 CONTROL ELEMENT DRIVE SYSTEM 7.4-2 7.4.2.1 Design Basis 7.4-2 7.4.2.2
System Description
7.4-2 7.4.2.3 System Operation 7.4-4 7.4.3 REACTOR COOLANT PRESSURE REGULATING SYSTEM 7.4-5 7.4.3.1 Design Basis 7.4-5 7.4.3.2 System Design and Operation 7.4-5 7.4.3.3 System Evaluation 7.4-6 7.4.4 PRESSURIZER LEVEL REGULATING SYSTEM 7.4-6 7.4.4.1 Design Basis 7.4-6 7.4.4.2 System Design and Operation 7.4-6 7.4.4.3 System Evaluation 7.4-6 7.4.5 FEEDWATER REGULATING SYSTEM 7.4-7 7.4.5.1 Design Basis 7.4-7 7.4.5.2 System Design and Operation 7.4-7 7.4.5.3 System Evaluation 7.4-8 7.4.6 STEAM DUMP AND TURBINE BYPASS SYSTEM 7.4-8 7.4.6.1 Design Basis 7.4-8 7.4.6.2 System Design and Operation 7.4-9 7.4.6.3 System Evaluation 7.4-10 7.4.7 TURBINE GENERATOR CONTROL SYSTEM 7.4-10 7.4.7.1 Unit 1 Turbine Control System (General Electric) 7.4-10 7.4.7.2 Unit 2 Turbine Control System (Westinghouse) 7.4-13
CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE CALVERT CLIFFS UFSAR 7-iii Rev. 51 7.5 INSTRUMENTATION SYSTEMS 7.5-1 7.5.1 PROCESS INSTRUMENTATION 7.5-1 7.5.1.1 Design Basis 7.5-1 7.5.1.2
System Description
7.5-1 7.5.2 NUCLEAR INSTRUMENTATION 7.5-3 7.5.2.1 Design Basis 7.5-3 7.5.2.2
System Description
7.5-4 7.5.2.3 Design Criteria 7.5-5 7.5.2.4 Wide Range Nuclear Instrumentation Channel Description 7.5-5 7.5.2.5 Power Range Safety Channel Description 7.5-7 7.5.2.6 Power Range Control Channel Description 7.5-7 7.5.2.7 Independent Wide Range Channel Description 7.5-8 7.5.3 CEA POSITION INSTRUMENTATION 7.5-8 7.5.3.1 Design Basis 7.5-8 7.5.3.2 Pulse Counting Position Indication System Description 7.5-8 7.5.3.3 Reed Switch Position Indication System Description 7.5-9 7.5.3.4 Additional CEA Position Indication 7.5-9 7.5.4 INCORE INSTRUMENTATION 7.5-9 7.5.4.1 Design Basis 7.5-9 7.5.4.2
System Description
7.5-10 7.5.4.3 Incore Instrumentation Requirements for Monitoring Technical Specification Limits 7.5-10 7.5.5 COMPUTER SYSTEMS 7.5-12 7.5.5.1 Data Acquisition System 7.5-12 7.5.5.2 Plant Computer 7.5-12 7.5.5.3 Safety Parameter Display System 7.5-12 7.5.5.4 Technical Support Center Computer 7.5-13 7.5.6 RADIOACTIVITY MONITORING 7.5-13 7.5.7 SEISMIC INSTRUMENTATION 7.5-13 7.5.8 POST-ACCIDENT MONITORING INSTRUMENTATION 7.5-14 7.5.9 INADEQUATE CORE COOLING INSTRUMENTATION 7.5-18 7.5.9.1 Subcooled Margin Monitor 7.5-19 7.5.9.2 Reactor Vessel Level Monitoring System 7.5-19 7.5.9.3 Core Exit Thermocouple 7.5-20 7.5.9.4 Reduced Reactor Coolant System Inventory and Mid-loop Operations Instrumentation 7.5-20 7.5.10 REFERENCES 7.5-21
CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE CALVERT CLIFFS UFSAR 7-iv Rev. 51 7.6 OPERATING CONTROL STATIONS 7.6-1 7.6.1 GENERAL LAYOUT 7.6-1 7.6.2 CONTROL ROOM 7.6-1 7.6.3 RADIOACTIVE WASTE DISPOSAL SYSTEM CONTROL PANELS 7.6-1 7.6.4 MISCELLANEOUS LOCAL CONTROL PANELS 7.6-1 7.6.5 FEATURES WHICH ENHANCE SAFE OPERATION 7.6-1 7.6.6 REMOTE SHUTDOWN CAPABILITY 7.6-1 7.7 CONTROL ROOM ANNUNCIATION 7.7-1 7.8 COMMUNICATIONS 7.8-1 7.8.1 DESIGN BASIS 7.8-1 7.8.2 COMMUNICATION SYSTEM DESCRIPTION 7.8-1 7.8.2.1 Public Address System 7.8-1 7.8.2.2 Commercial Telephones 7.8-1 7.8.2.3 Sound-Powered Phone (Plant Use) 7.8-1 7.8.2.4 Sound-Powered Phone (Emergency Use) 7.8-2 7.8.2.5 Microwave Communication System 7.8-2 7.8.2.6 Radio Telephone System (Plant Use) 7.8-2 7.8.3 RELIABILITY AND TESTING 7.8-2 7.9 DELETED 7.9-1 7.10 AUXILIARY FEEDWATER ACTUATION SYSTEM 7.10-1 7.10.1 DESIGN BASIS 7.10-1 7.10.1.1 Conformance to Standards 7.10-1 7.10.1.2 Security and Annunciation 7.10-2 7.10.1.3 Seismic and Environmental Requirements 7.10-2 7.10.2 SYSTEM DESCRIPTION 7.10-3 7.10.2.1 Sensor Subsystems 7.10-3 7.10.2.2 Actuation Subsystems 7.10-3 7.10.3 SYSTEM SURVEILLANCE 7.10-4 7.10.3.1 Remote Annunciation 7.10-4 7.10.3.2 Local Sensor Channel Surveillance 7.10-5 7.10.3.3 Local Actuation Channel Surveillance 7.10-5 7.10.4 ELECTRICAL POWER SUPPLY 7.10-5 7.10.5 SYSTEM EVALUATION 7.10-5 7.10.6 MANUAL TESTING FEATURES 7.10-5 7.10.6.1 Bistable Trip Test 7.10-5 7.10.6.2 Actuation Channel Trip Test 7.10-6 7.11 ANTICIPATED TRANSIENT WITHOUT SCRAM 7.11-1 7.11.1 DIVERSE SCRAM SYSTEM 7.11-1 7.11.1.1 Design Basis 7.11-1
CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE CALVERT CLIFFS UFSAR 7-v Rev. 51 7.11.1.2
System Description
7.11-2 7.11.2 DIVERSE TURBINE TRIP 7.11-2 7.12 ENVIRONMENTAL QUALIFICATION OF ELECTRIC EQUIPMENT IMPORTANT TO SAFETY 7.12-1
CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF TABLES TITLE PAGE CALVERT CLIFFS UFSAR 7-vi Rev. 51 7-1 REACTOR TRIP ALLOWABLE LIMITS AND PRETRIP LIMITS 7.2-18 7-2 REACTOR PROTECTIVE INSTRUMENTATION RESPONSE TIMES 7.2-19 7-3 LIST OF CLASS I (SEISMIC) EQUIPMENT SUBJECTED TO DYNAMIC LOAD TEST 7.3-21 7-4 ENGINEERED SAFETY FEATURES RESPONSE TIMES 7.3-22 7-5 PROHIBITS ON CEAs (MANUAL CONTROL MODE) 7.4-18 7-6 CEA POSITION LIGHT MATRIX 7.5-22
CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF FIGURES FIGURE CALVERT CLIFFS UFSAR 7-vii Rev. 47 7-1 REACTOR PROTECTIVE SYSTEM - BLOCK DIAGRAM 7-2 REACTOR PROTECTIVE SYSTEM - FUNCTION DIAGRAM 7-2A REACTOR PROTECTIVE SYSTEM - INTERFACE LOGIC DIAGRAM 7-3 PRESSURIZER PRESSURE MEASUREMENT CHANNEL -
FUNCTIONAL DIAGRAM 7-4 EX-CORE NUCLEAR INSTRUMENTATION 7-5 LOW FLOW PROTECTIVE SYSTEM - FUNCTIONAL DIAGRAM 7-6 THERMAL MARGIN/LOW PRESSURE TRIP CHANNEL - BLOCK DIAGRAM 7-6A THERMAL MARGIN/LOW PRESSURE TRIP - FUNCTION DIAGRAM 7-6B ASYMETRIC STEAM GENERATOR TRIP (ASGT) - FUNCTIONAL DIAGRAM 7-7 NEUTRON FLUX MONITORING SYSTEM STARTUP AND LOGARITHMIC RANGE CHANNELS 7-9 SAFETY INJECTION ACTUATION SIGNAL 7-10 sh 1 LOGIC DIAGRAM - ENGINEERED SAFETY FEATURES ACTUATION 7-10 sh 2 SYSTEM UNIT 1 7-11 REACTOR REGULATING SYSTEM-BLOCK DIAGRAM 7-12 CEA POSITION SETPOINTS 7-13 PRESSURE CONTROL PROGRAM 7-14A FEED WATER CONTROL SYSTEM - BLOCK DIAGRAM, UNIT 1 7-14B FEED WATER CONTROL SYSTEM - BLOCK DIAGRAM, UNIT 2 7-15 sh 1 BLOCK DIAGRAM - STEAM DUMP AND BYPASS SYSTEM 7-15 sh 2 7-15 sh 3 PROGRAM OF STEAM DUMP, BYPASS VALVES AND QUICK OPENING OVERRIDE 7-16 CONTROL ELEMENT DRIVE SYSTEM-BLOCK DIAGRAM 7-17 STEAM GENERATOR PROTECTIVE SYSTEM MEASUREMENT CHANNEL 7-18 SCHEMATIC LOW STEAM GENERATOR PRESSURE BYPASS 7-20 VARIABLE HIGH POWER TRIP OPERATION 7-21 T POWER CALCULATION 7-22 sh 1 LOGIC DIAGRAM - ENGINEERED SAFETY FEATURES ACTUATION 7-22 sh 2 SYSTEM UNIT 2 7-24A LOGIC DIAGRAM - AUXILIARY FEEDWATER ACTUATION SYSTEM (AFAS) UNIT NO. 1 7-24B LOGIC DIAGRAM - AUXILIARY FEEDWATER ACTUATION SYSTEM (AFAS) UNIT NO. 1 7-24C LOGIC DIAGRAM - AUXILIARY FEEDWATER ACTUATION SYSTEM (AFAS) UNIT NO. 2 7-24D LOGIC DIAGRAM - AUXILIARY FEEDWATER ACTUATION SYSTEM (AFAS) UNIT NO. 2
CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF ACRONYMS CALVERT CLIFFS UFSAR 7-viii Rev. 50 AFAS Auxiliary Feedwater Actuation System AFW Auxiliary Feedwater ATWS Anticipated Transient Without Scram BGE Baltimore Gas and Electric Company CB Check Valve Bypass CCW Component Cooling Water CE Combustion Engineering, Inc.
CEA Control Element Assembly CEDM Control Element Drive Mechanism CEDS Control Element Drive System CET Core Exit Thermocouple CFR Code of Federal Regulations CIS Containment Isolation Signal CMI CEA Motion Inhibits CRS Containment Radiation Signal CRT Cathode Ray Tube CSAS Containment Spray Actuation Signal CSF Critical Safety Functions CVCIS Chemical and Volume Control Isolation Signal d/p Differential Pressure DAS Data Acquisition System DEV Deviation Alarm DNB Departure From Nucleate Boiling DNBR Departure From Nucleate Boiling Ratio DSS Diverse Scram System DTT Diverse Turbine Trip ECCS Emergency Core Cooling System EHC Electro-Hydraulic Control ERGO Excessive Regulatory Group Overlap ESF Engineered Safety Feature ESFAS Engineered Safety Feature Actuation System ET Emergency Trip ETS Emergency Trip Signal FCR Facility Change Request HJTC Heated Junction Thermocouple HPSI High Pressure Safety Injection ICC Inadequate Core Cooling ICCI Inadequate Core Cooling Instrumentation ICI Incore Instrumentation IEB Inspection and Enforcement Bulletin IEEE Institute of Electrical and Electronic Engineers LOCA Loss-of-Coolant Accident LOCI Loss-of-Coolant Incident LPSI Low Pressure Safety Injection MFIV Main Feedwater Isolation Valve MIRG Shutdown Group Insertion Interlock MISH Regulating Group Withdrawal Interlock
CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF ACRONYMS CALVERT CLIFFS UFSAR 7-ix Rev. 50 MSIV Main Steam Isolation Valve MSLB Main Steam Line Break MSR Moisture Separator Reheaters NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System OOS Out-of-Sequence OPC Overspeed Protection Control PA Public Address PAM Post-Accident Monitoring PDIL Power Dependent Insertion Limit PORV Power-Operated Relief Valve Q-List Quality-List RAS Recirculation Actuation Signal RCP Reactor Coolant Pump RCS Reactor Coolant System RPS Reactor Protective System RPSCIP Reactor Protective System Calibration and Indication Panel RTD Resistance Temperature Detector RVLMS Reactor Vessel Level Monitoring System RWT Refueling Water Tank SCMM Subcooled Margin Monitor SER Safety Evaluation Report SG Steam Generator SGIS Steam Generator Isolation Signal SIAS Safety Injection Actuation Signal SPDS Safety Parameter Display System SRW Service Water TDM Testable Dump Manifold TM/LP Thermal Margin/Low Pressure TMR Triple Modular Redundant TSC Technical Support Center UFSAR Updated Final Safety Analysis Report