ML21278A189: Difference between revisions

From kanterella
Jump to navigation Jump to search
(StriderTol Bot insert)
 
(StriderTol Bot change)
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE 7.0 INSTRUMENTATION AND CONTROL                                       7.1-1
{{#Wiki_filter:CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 7.0 INSTRUMENTATION AND CONTROL 7.1 1


==7.1 INTRODUCTION==
==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 CALVERT CLIFFS UFSAR                      7-i                            Rev. 51
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 HLJK RDWH RI CKDQJH RI PRZHU 7.2 3 7.2.3.2 VDULDEOH OYHU PRZHU LHYHO 7.2 3 7.2.3.3 LRZ RHDFWRU CRRODQW FORZ 7.2 4 7.2.3.4 LRZ SWHDP GHQHUDWRU WDWHU LHYHO 7.2 6 7.2.3.5 LRZ SWHDP GHQHUDWRU PUHVVXUH 7.2 6 7.2.3.6 HLJK PUHVVXUL]HU PUHVVXUH 7.2 7 7.2.3.7 TKHUPDO MDUJLQ LRZ PUHVVXUH TULS 7.2 7 7.2.3.8 LRVV RI LRDG 7.2 9 7.2.3.9 HLJK CRQWDLQPHQW PUHVVXUH 7.2 9 7.2.3.10 MDQXDO TULS 7.2 10 7.2.3.11 A[LDO FOX[ OIIVHW TULS 7.2 10 7.2.3.12 AV\\PPHWULF SWHDP GHQHUDWRU LRDG 7.2 10 7.2.4 SIGNAL GENERATION 7.2 10 7.2.4.1 HLJK RDWH RI CKDQJH RI PRZHU 7.2 10 7.2.4.2 HLJK PRZHU LHYHO 7.2 10 7.2.4.3 FORZ W DWHU LHYHO PUHVVXUH DQG TKHUPDO MDUJLQ 7.2 11 7.2.4.4 A[LDO FOX[ OIIVHW 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 POW ER 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 CRQIRUPDQFH WR SWDQGDUGV 7.3 1 7.3.1.2 SHFXULW\\ DQG AQQXQFLDWLRQ 7.3 2 7.3.1.3 SHLVPLF RHTXLUHPHQWV 7.3 3 7.3.1.4 EQYLURQPHQWDO RHTXLUHPHQWV 7.3 3 7.3.2 SYSTEM DESCRIPTION 7.3 3 7.3.2.1 SHQVRU SXEV\\VWHPV 7.3 4 7.3.2.2 AFWXDWLRQ SXEV\\VWHPV 7.3 5 7.3.2.3 UQGHUYROWDJH BORFNLQJ DQG SHTXHQFLQJ 7.3 14 7.3.3 SYSTEM SURVEILLANCE 7.3 14 7.3.3.1 RHPRWH AQQXQFLDWLRQ 7.3 14


CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE 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 CALVERT CLIFFS UFSAR                    7-ii                            Rev. 51
CALVERT CLIFFS UFSAR 7-i Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 7.3.3.2 LRFDO SHQVRU CKDQQHO SXUYHLOODQFH 7.3 15 7.3.3.3 LRFDO AFWXDWLRQ CKDQQHO SXUYHLOODQFH 7.3 15 7.3.4 ELECTRICAL POW ER 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 BLVWDEOH TULS THVW 7.3 17 7.3.6.2 THVWLQJ RI RHIXHOLQJ W DWHU TDQN LHYHO SZLWFKHV 7.3 17 7.3.6.3 AFWXDWLRQ CKDQQHO TULS THVW 7.3 17 7.3.6.4 UQGHUYROWDJH BORFNLQJ DQG SHTXHQFLQJ THVWV 7.3 17 7.3.7 PORTIONS NOT TESTED AT POW ER 7.3 18 7.4 REGULATING SYSTEMS 7.4 1 7.4.1 REACTOR REGULATING SYSTEM 7.4 1 7.4.1.1 GHQHUDO 7.4 1 7.4.1.2 S\\VWHP DHVFULSWLRQ 7.4 1 7.4.2 CONTROL ELEMENT DRIVE SYSTEM 7.4 2 7.4.2.1 DHVLJQ BDVLV 7.4 2 7.4.2.2 S\\VWHP DHVFULSWLRQ 7.4 2 7.4.2.3 S\\VWHP OSHUDWLRQ 7.4 4 7.4.3 REACTOR COOLANT PRESSURE REGULATING SYSTEM 7.4 5 7.4.3.1 DHVLJQ BDVLV 7.4 5 7.4.3.2 S\\VWHP DHVLJQ DQG OSHUDWLRQ 7.4 5 7.4.3.3 S\\VWHP EYDOXDWLRQ 7.4 6 7.4.4 PRESSURI=ER LEVEL REGULATING SYSTEM 7.4 6 7.4.4.1 DHVLJQ BDVLV 7.4 6 7.4.4.2 S\\VWHP DHVLJQ DQG OSHUDWLRQ 7.4 6 7.4.4.3 S\\VWHP EYDOXDWLRQ 7.4 6 7.4.5 FEEDW ATER REGULATING SYSTEM 7.4 7 7.4.5.1 DHVLJQ BDVLV 7.4 7 7.4.5.2 S\\VWHP DHVLJQ DQG OSHUDWLRQ 7.4 7 7.4.5.3 S\\VWHP EYDOXDWLRQ 7.4 8 7.4.6 STEAM DUMP AND TURBINE BYPASS SYSTEM 7.4 8 7.4.6.1 DHVLJQ BDVLV 7.4 8 7.4.6.2 S\\VWHP DHVLJQ DQG OSHUDWLRQ 7.4 9 7.4.6.3 S\\VWHP EYDOXDWLRQ 7.4 10 7.4.7 TURBINE GENERATOR CONTROL SYSTEM 7.4 10 7.4.7.1 UQLW 1 TXUELQH CRQWURO S\\VWHP GHQHUDO EOHFWULF 7.4 10 7.4.7.2 UQLW 2 TXUELQH CRQWURO S\\VWHP W HVWLQJKRXVH 7.4 13


CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE 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            7.5-5 Description 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    7.5-10 Technical Specification Limits 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-      7.5-20 loop Operations Instrumentation 7.5.10 REFERENCES                                                       7.5-21 CALVERT CLIFFS UFSAR                    7-iii                                  Rev. 51
CALVERT CLIFFS UFSAR 7-ii Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 7.5 INSTRUMENTATION SYSTEMS 7.5 1 7.5.1 PROCESS INSTRUMENTATION 7.5 1 7.5.1.1 DHVLJQ BDVLV 7.5 1 7.5.1.2 S\\VWHP DHVFULSWLRQ 7.5 1 7.5.2 NUCLEAR INSTRUMENTATION 7.5 3 7.5.2.1 DHVLJQ BDVLV 7.5 3 7.5.2.2 S\\VWHP DHVFULSWLRQ 7.5 4 7.5.2.3 DHVLJQ CULWHULD 7.5 5 7.5.2.4 WLGH RDQJH NXFOHDU IQVWUXPHQWDWLRQ CKDQQHO 7.5 5 DHVFULSWLRQ 7.5.2.5 PRZHU RDQJH SDIHW\\ CKDQQHO DHVFULSWLRQ 7.5 7 7.5.2.6 PRZHU RDQJH CRQWURO CKDQQHO DHVFULSWLRQ 7.5 7 7.5.2.7 IQGHSHQGHQW W LGH RDQJH CKDQQHO DHVFULSWLRQ 7.5 8 7.5.3 CEA POSITION INSTRUMENTATION 7.5 8 7.5.3.1 DHVLJQ BDVLV 7.5 8 7.5.3.2 PXOVH CRXQWLQJ PRVLWLRQ IQGLFDWLRQ S\\VWHP DHVFULSWLRQ 7.5 8 7.5.3.3 RHHG SZLWFK PRVLWLRQ IQGLFDWLRQ S\\VWHP DHVFULSWLRQ 7.5 9 7.5.3.4 AGGLWLRQDO CEA PRVLWLRQ IQGLFDWLRQ 7.5 9 7.5.4 INCORE INSTRUMENTATION 7.5 9 7.5.4.1 DHVLJQ BDVLV 7.5 9 7.5.4.2 S\\VWHP DHVFULSWLRQ 7.5 10 7.5.4.3 IQFRUH IQVWUXPHQWDWLRQ RHTXLUHPHQWV IRU MRQLWRULQJ 7.5 10 THFKQLFDO SSHFLILFDWLRQ LLPLWV 7.5.5 COMPUTER SYSTEMS 7.5 12 7.5.5.1 DDWD AFTXLVLWLRQ S\\VWHP 7.5 12 7.5.5.2 PODQW CRPSXWHU 7.5 12 7.5.5.3 SDIHW\\ PDUDPHWHU DLVSOD\\ S\\VWHP 7.5 12 7.5.5.4 THFKQLFDO SXSSRUW CHQWHU CRPSXWHU 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 SXEFRROHG MDUJLQ MRQLWRU 7.5 19 7.5.9.2 RHDFWRU VHVVHO LHYHO MRQLWRULQJ S\\VWHP 7.5 19 7.5.9.3 CRUH E[LW TKHUPRFRXSOH 7.5 20 7.5.9.4 RHGXFHG RHDFWRU CRRODQW S\\VWHP IQYHQWRU\\ DQG MLG 7.5 20 ORRS OSHUDWLRQV IQVWUXPHQWDWLRQ 7.5.10 REFERENCES 7.5 21


CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE 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 CALVERT CLIFFS UFSAR                  7-iv                    Rev. 51
CALVERT CLIFFS UFSAR 7-iii Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 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 W ASTE DISPOSAL SYSTEM CONTROL PANELS 7.6 1 7.6.4 MISCELLANEOUS LOCAL CONTROL PANELS 7.6 1 7.6.5 FEATURES W HICH ENHANCE SAFE OPERATION 7.6 1 7.6.6 REMOTE SHUTDOW N 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 PXEOLF AGGUHVV S\\VWHP 7.8 1 7.8.2.2 CRPPHUFLDO THOHSKRQHV 7.8 1 7.8.2.3 SRXQG PRZHUHG PKRQH PODQW UVH 7.8 1 7.8.2.4 SRXQG PRZHUHG PKRQH EPHUJHQF\\ UVH 7.8 2 7.8.2.5 MLFURZDYH CRPPXQLFDWLRQ S\\VWHP 7.8 2 7.8.2.6 RDGLR THOHSKRQH S\\VWHP PODQW UVH 7.8 2 7.8.3 RELIABILITY AND TESTING 7.8 2 7.9 DELETED 7.9 1 7.10 AUXILI ARY FEEDW ATER ACTUATION SYSTEM 7.10 1 7.10.1 DESIGN BASIS 7.10 1 7.10.1.1 CRQIRUPDQFH WR SWDQGDUGV 7.10 1 7.10.1.2 SHFXULW\\ DQG AQQXQFLDWLRQ 7.10 2 7.10.1.3 SHLVPLF DQG EQYLURQPHQWDO RHTXLUHPHQWV 7.10 2 7.10.2 SYSTEM DESCRIPTION 7.10 3 7.10.2.1 SHQVRU SXEV\\VWHPV 7.10 3 7.10.2.2 AFWXDWLRQ SXEV\\VWHPV 7.10 3 7.10.3 SYSTEM SURVEILLANCE 7.10 4 7.10.3.1 RHPRWH AQQXQFLDWLRQ 7.10 4 7.10.3.2 LRFDO SHQVRU CKDQQHO SXUYHLOODQFH 7.10 5 7.10.3.3 LRFDO AFWXDWLRQ CKDQQHO SXUYHLOODQFH 7.10 5 7.10.4 ELECTRICAL POW ER 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 BLVWDEOH TULS THVW 7.10 5 7.10.6.2 AFWXDWLRQ CKDQQHO TULS THVW 7.10 6 7.11 ANTICIPATED TRANSIENT WITHOUT S C R AM 7.11 1 7.11.1 DIVERSE SCRAM SYSTEM 7.11 1 7.11.1.1 DHVLJQ BDVLV 7.11 1


CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS PAGE 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 7.12-1 IMPORTANT TO SAFETY CALVERT CLIFFS UFSAR                  7-v                Rev. 51
CALVERT CLIFFS UFSAR 7-iv Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 7.11.1.2 S\\VWHP DHVFULSWLRQ 7.11 2 7.11.2 DIVERSE TURBINE TRIP 7.11 2 7.12 ENVIRONMENTAL QUALIFICATION OF ELECTRIC EQUIPMENT 7.12-1 IMPORTANT TO SAFETY


CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF TABLES TITLE                                                       PAGE 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 7.3-21 DYNAMIC LOAD TEST 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 CALVERT CLIFFS UFSAR                  7-vi                  Rev. 51
CALVERT CLIFFS UFSAR 7-v Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF TABLES TITLE P AG E 7-1 REACTOR TRIP ALLOW ABLE 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 7.3-21 DYNAMIC LOAD TEST 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 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 -
CALVERT CLIFFS UFSAR 7-vi Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF FIGURES FIGURE 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 CALVERT CLIFFS UFSAR                7-vii                        Rev. 47
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 W ATER CONTROL SYSTEM - BLOCK DIAGRAM, UNIT 1 7-14B FEED W ATER 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 POW ER TRIP OPERATION 7-21 732:(5&$/&8/$7,21 
VK  /2*,&,$*5$0 (1*,1((5(6$)(7<)($785(6$&78$7,21 
VK  6<67(081,7 
$  /2*,&,$*5$0 $8;,/,$5<)((:$7(5$&78$7,216<67(0
$)$6 81,712  
%  /2*,&,$*5$0 $8;,/,$5<)((:$7(5$&78$7,216<67(0
$)$6 81,712  
&  /2*,&,$*5$0 $8;,/,$5<)((:$7(5$&78$7,216<67(0
$)$6 81,712  
 /2*,&,$*5$0 $8;,/,$5<)((:$7(5$&78$7,216<67(0
$)$6 81,712  



CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF ACRONYMS 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.
CALVERT CLIFFS UFSAR 7-vii Rev. 47 CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF ACRONYMS AFAS Auxiliary Feedwater Actuation System AFW Auxiliary Feedwater ATW S Anticipated Transient W ithout Scram BGE Baltimore Gas and Electric Company CB Check Valve Bypass CCW Component Cooling W ater 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 CALVERT CLIFFS UFSAR                        7-viii        Rev. 50
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 W ithdrawal Interlock


CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF ACRONYMS 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 CALVERT CLIFFS UFSAR                       7-ix                       Rev. 50}}
CALVERT CLIFFS UFSAR 7-viii Rev. 50 CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF ACRONYMS 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 RVL MS Reactor Vessel Level Monitoring System RW T Ref ueling W ater 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 W ater TDM Testable Dump Manifold T M/LP Thermal Margin/Low Pressure T MR Triple Modular Redundant TSC Technical Support Center UFSAR Updated Final Safety Analysis Report
 
CALVERT CLIFFS UFSAR 7-ix Rev. 50}}

Revision as of 19:44, 19 November 2024

2 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Control, Table of Contents
ML21278A189
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 09/07/2021
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML21278A102 List: ... further results
References
NEI 99-04
Download: ML21278A189 (9)
v • d • e


Text

CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 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 HLJK RDWH RI CKDQJH RI PRZHU 7.2 3 7.2.3.2 VDULDEOH OYHU PRZHU LHYHO 7.2 3 7.2.3.3 LRZ RHDFWRU CRRODQW FORZ 7.2 4 7.2.3.4 LRZ SWHDP GHQHUDWRU WDWHU LHYHO 7.2 6 7.2.3.5 LRZ SWHDP GHQHUDWRU PUHVVXUH 7.2 6 7.2.3.6 HLJK PUHVVXUL]HU PUHVVXUH 7.2 7 7.2.3.7 TKHUPDO MDUJLQ LRZ PUHVVXUH TULS 7.2 7 7.2.3.8 LRVV RI LRDG 7.2 9 7.2.3.9 HLJK CRQWDLQPHQW PUHVVXUH 7.2 9 7.2.3.10 MDQXDO TULS 7.2 10 7.2.3.11 A[LDO FOX[ OIIVHW TULS 7.2 10 7.2.3.12 AV\\PPHWULF SWHDP GHQHUDWRU LRDG 7.2 10 7.2.4 SIGNAL GENERATION 7.2 10 7.2.4.1 HLJK RDWH RI CKDQJH RI PRZHU 7.2 10 7.2.4.2 HLJK PRZHU LHYHO 7.2 10 7.2.4.3 FORZ W DWHU LHYHO PUHVVXUH DQG TKHUPDO MDUJLQ 7.2 11 7.2.4.4 A[LDO FOX[ OIIVHW 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 POW ER 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 CRQIRUPDQFH WR SWDQGDUGV 7.3 1 7.3.1.2 SHFXULW\\ DQG AQQXQFLDWLRQ 7.3 2 7.3.1.3 SHLVPLF RHTXLUHPHQWV 7.3 3 7.3.1.4 EQYLURQPHQWDO RHTXLUHPHQWV 7.3 3 7.3.2 SYSTEM DESCRIPTION 7.3 3 7.3.2.1 SHQVRU SXEV\\VWHPV 7.3 4 7.3.2.2 AFWXDWLRQ SXEV\\VWHPV 7.3 5 7.3.2.3 UQGHUYROWDJH BORFNLQJ DQG SHTXHQFLQJ 7.3 14 7.3.3 SYSTEM SURVEILLANCE 7.3 14 7.3.3.1 RHPRWH AQQXQFLDWLRQ 7.3 14

CALVERT CLIFFS UFSAR 7-i Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 7.3.3.2 LRFDO SHQVRU CKDQQHO SXUYHLOODQFH 7.3 15 7.3.3.3 LRFDO AFWXDWLRQ CKDQQHO SXUYHLOODQFH 7.3 15 7.3.4 ELECTRICAL POW ER 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 BLVWDEOH TULS THVW 7.3 17 7.3.6.2 THVWLQJ RI RHIXHOLQJ W DWHU TDQN LHYHO SZLWFKHV 7.3 17 7.3.6.3 AFWXDWLRQ CKDQQHO TULS THVW 7.3 17 7.3.6.4 UQGHUYROWDJH BORFNLQJ DQG SHTXHQFLQJ THVWV 7.3 17 7.3.7 PORTIONS NOT TESTED AT POW ER 7.3 18 7.4 REGULATING SYSTEMS 7.4 1 7.4.1 REACTOR REGULATING SYSTEM 7.4 1 7.4.1.1 GHQHUDO 7.4 1 7.4.1.2 S\\VWHP DHVFULSWLRQ 7.4 1 7.4.2 CONTROL ELEMENT DRIVE SYSTEM 7.4 2 7.4.2.1 DHVLJQ BDVLV 7.4 2 7.4.2.2 S\\VWHP DHVFULSWLRQ 7.4 2 7.4.2.3 S\\VWHP OSHUDWLRQ 7.4 4 7.4.3 REACTOR COOLANT PRESSURE REGULATING SYSTEM 7.4 5 7.4.3.1 DHVLJQ BDVLV 7.4 5 7.4.3.2 S\\VWHP DHVLJQ DQG OSHUDWLRQ 7.4 5 7.4.3.3 S\\VWHP EYDOXDWLRQ 7.4 6 7.4.4 PRESSURI=ER LEVEL REGULATING SYSTEM 7.4 6 7.4.4.1 DHVLJQ BDVLV 7.4 6 7.4.4.2 S\\VWHP DHVLJQ DQG OSHUDWLRQ 7.4 6 7.4.4.3 S\\VWHP EYDOXDWLRQ 7.4 6 7.4.5 FEEDW ATER REGULATING SYSTEM 7.4 7 7.4.5.1 DHVLJQ BDVLV 7.4 7 7.4.5.2 S\\VWHP DHVLJQ DQG OSHUDWLRQ 7.4 7 7.4.5.3 S\\VWHP EYDOXDWLRQ 7.4 8 7.4.6 STEAM DUMP AND TURBINE BYPASS SYSTEM 7.4 8 7.4.6.1 DHVLJQ BDVLV 7.4 8 7.4.6.2 S\\VWHP DHVLJQ DQG OSHUDWLRQ 7.4 9 7.4.6.3 S\\VWHP EYDOXDWLRQ 7.4 10 7.4.7 TURBINE GENERATOR CONTROL SYSTEM 7.4 10 7.4.7.1 UQLW 1 TXUELQH CRQWURO S\\VWHP GHQHUDO EOHFWULF 7.4 10 7.4.7.2 UQLW 2 TXUELQH CRQWURO S\\VWHP W HVWLQJKRXVH 7.4 13

CALVERT CLIFFS UFSAR 7-ii Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 7.5 INSTRUMENTATION SYSTEMS 7.5 1 7.5.1 PROCESS INSTRUMENTATION 7.5 1 7.5.1.1 DHVLJQ BDVLV 7.5 1 7.5.1.2 S\\VWHP DHVFULSWLRQ 7.5 1 7.5.2 NUCLEAR INSTRUMENTATION 7.5 3 7.5.2.1 DHVLJQ BDVLV 7.5 3 7.5.2.2 S\\VWHP DHVFULSWLRQ 7.5 4 7.5.2.3 DHVLJQ CULWHULD 7.5 5 7.5.2.4 WLGH RDQJH NXFOHDU IQVWUXPHQWDWLRQ CKDQQHO 7.5 5 DHVFULSWLRQ 7.5.2.5 PRZHU RDQJH SDIHW\\ CKDQQHO DHVFULSWLRQ 7.5 7 7.5.2.6 PRZHU RDQJH CRQWURO CKDQQHO DHVFULSWLRQ 7.5 7 7.5.2.7 IQGHSHQGHQW W LGH RDQJH CKDQQHO DHVFULSWLRQ 7.5 8 7.5.3 CEA POSITION INSTRUMENTATION 7.5 8 7.5.3.1 DHVLJQ BDVLV 7.5 8 7.5.3.2 PXOVH CRXQWLQJ PRVLWLRQ IQGLFDWLRQ S\\VWHP DHVFULSWLRQ 7.5 8 7.5.3.3 RHHG SZLWFK PRVLWLRQ IQGLFDWLRQ S\\VWHP DHVFULSWLRQ 7.5 9 7.5.3.4 AGGLWLRQDO CEA PRVLWLRQ IQGLFDWLRQ 7.5 9 7.5.4 INCORE INSTRUMENTATION 7.5 9 7.5.4.1 DHVLJQ BDVLV 7.5 9 7.5.4.2 S\\VWHP DHVFULSWLRQ 7.5 10 7.5.4.3 IQFRUH IQVWUXPHQWDWLRQ RHTXLUHPHQWV IRU MRQLWRULQJ 7.5 10 THFKQLFDO SSHFLILFDWLRQ LLPLWV 7.5.5 COMPUTER SYSTEMS 7.5 12 7.5.5.1 DDWD AFTXLVLWLRQ S\\VWHP 7.5 12 7.5.5.2 PODQW CRPSXWHU 7.5 12 7.5.5.3 SDIHW\\ PDUDPHWHU DLVSOD\\ S\\VWHP 7.5 12 7.5.5.4 THFKQLFDO SXSSRUW CHQWHU CRPSXWHU 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 SXEFRROHG MDUJLQ MRQLWRU 7.5 19 7.5.9.2 RHDFWRU VHVVHO LHYHO MRQLWRULQJ S\\VWHP 7.5 19 7.5.9.3 CRUH E[LW TKHUPRFRXSOH 7.5 20 7.5.9.4 RHGXFHG RHDFWRU CRRODQW S\\VWHP IQYHQWRU\\ DQG MLG 7.5 20 ORRS OSHUDWLRQV IQVWUXPHQWDWLRQ 7.5.10 REFERENCES 7.5 21

CALVERT CLIFFS UFSAR 7-iii Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 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 W ASTE DISPOSAL SYSTEM CONTROL PANELS 7.6 1 7.6.4 MISCELLANEOUS LOCAL CONTROL PANELS 7.6 1 7.6.5 FEATURES W HICH ENHANCE SAFE OPERATION 7.6 1 7.6.6 REMOTE SHUTDOW N 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 PXEOLF AGGUHVV S\\VWHP 7.8 1 7.8.2.2 CRPPHUFLDO THOHSKRQHV 7.8 1 7.8.2.3 SRXQG PRZHUHG PKRQH PODQW UVH 7.8 1 7.8.2.4 SRXQG PRZHUHG PKRQH EPHUJHQF\\ UVH 7.8 2 7.8.2.5 MLFURZDYH CRPPXQLFDWLRQ S\\VWHP 7.8 2 7.8.2.6 RDGLR THOHSKRQH S\\VWHP PODQW UVH 7.8 2 7.8.3 RELIABILITY AND TESTING 7.8 2 7.9 DELETED 7.9 1 7.10 AUXILI ARY FEEDW ATER ACTUATION SYSTEM 7.10 1 7.10.1 DESIGN BASIS 7.10 1 7.10.1.1 CRQIRUPDQFH WR SWDQGDUGV 7.10 1 7.10.1.2 SHFXULW\\ DQG AQQXQFLDWLRQ 7.10 2 7.10.1.3 SHLVPLF DQG EQYLURQPHQWDO RHTXLUHPHQWV 7.10 2 7.10.2 SYSTEM DESCRIPTION 7.10 3 7.10.2.1 SHQVRU SXEV\\VWHPV 7.10 3 7.10.2.2 AFWXDWLRQ SXEV\\VWHPV 7.10 3 7.10.3 SYSTEM SURVEILLANCE 7.10 4 7.10.3.1 RHPRWH AQQXQFLDWLRQ 7.10 4 7.10.3.2 LRFDO SHQVRU CKDQQHO SXUYHLOODQFH 7.10 5 7.10.3.3 LRFDO AFWXDWLRQ CKDQQHO SXUYHLOODQFH 7.10 5 7.10.4 ELECTRICAL POW ER 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 BLVWDEOH TULS THVW 7.10 5 7.10.6.2 AFWXDWLRQ CKDQQHO TULS THVW 7.10 6 7.11 ANTICIPATED TRANSIENT WITHOUT S C R AM 7.11 1 7.11.1 DIVERSE SCRAM SYSTEM 7.11 1 7.11.1.1 DHVLJQ BDVLV 7.11 1

CALVERT CLIFFS UFSAR 7-iv Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL TABLE OF CONTENTS P AG E 7.11.1.2 S\\VWHP DHVFULSWLRQ 7.11 2 7.11.2 DIVERSE TURBINE TRIP 7.11 2 7.12 ENVIRONMENTAL QUALIFICATION OF ELECTRIC EQUIPMENT 7.12-1 IMPORTANT TO SAFETY

CALVERT CLIFFS UFSAR 7-v Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF TABLES TITLE P AG E 7-1 REACTOR TRIP ALLOW ABLE 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 7.3-21 DYNAMIC LOAD TEST 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

CALVERT CLIFFS UFSAR 7-vi Rev. 51 CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF FIGURES FIGURE 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 W ATER CONTROL SYSTEM - BLOCK DIAGRAM, UNIT 1 7-14B FEED W ATER 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 POW ER TRIP OPERATION 7-21 732:(5&$/&8/$7,21 

VK  /2*,&,$*5$0 (1*,1((5(6$)(7<)($785(6$&78$7,21 

VK  6<67(081,7 

$  /2*,&,$*5$0 $8;,/,$5<)((:$7(5$&78$7,216<67(0

$)$6 81,712  

%  /2*,&,$*5$0 $8;,/,$5<)((:$7(5$&78$7,216<67(0

$)$6 81,712  

&  /2*,&,$*5$0 $8;,/,$5<)((:$7(5$&78$7,216<67(0

$)$6 81,712  

 /2*,&,$*5$0 $8;,/,$5<)((:$7(5$&78$7,216<67(0

$)$6 81,712  



CALVERT CLIFFS UFSAR 7-vii Rev. 47 CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF ACRONYMS AFAS Auxiliary Feedwater Actuation System AFW Auxiliary Feedwater ATW S Anticipated Transient W ithout Scram BGE Baltimore Gas and Electric Company CB Check Valve Bypass CCW Component Cooling W ater 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 W ithdrawal Interlock

CALVERT CLIFFS UFSAR 7-viii Rev. 50 CHAPTER 7 INSTRUMENTATION AND CONTROL LIST OF ACRONYMS 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 RVL MS Reactor Vessel Level Monitoring System RW T Ref ueling W ater 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 W ater TDM Testable Dump Manifold T M/LP Thermal Margin/Low Pressure T MR Triple Modular Redundant TSC Technical Support Center UFSAR Updated Final Safety Analysis Report

CALVERT CLIFFS UFSAR 7-ix Rev. 50

Retrieved from "https://kanterella.com/w/index.php?title=ML21278A189&oldid=3745320"