ML16309A371

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Revision 22 to Updated Safety Analysis Report, Chapter 7, Table of Contents
ML16309A371
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 10/24/2016
From:
Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
Shared Package
ML16309A376 List:
References
NMP2L 2633
Download: ML16309A371 (14)
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Text

U.S. NUCLEAR REGULATORY COMMISSION DOCKET 50-410 LICENSE NPF-69 NINE MILE POINT NUCLEAR STATION UNIT 2 UPDATED SAFETY ANALYSIS REPORT OCTOBER 2016 REVISION 22

NMP Unit 2 USAR CHAPTER 7 LIST OF EFFECTIVE FIGURES Revision Revision Figure No. Number Figure No. Number 7.2-1 Sh 1 R15 7.6-3 Sh 2 R21 7.2-1 Sh 2 R15 7.6-4 A00 7.2-1 Sh 3 R15 7.6-5 A00 7.2-1 Sh 4 R15 7.6-6 Sh 1 R13 7.2-1 Sh 5 A23 7.6-6 Sh 2 R21 7.3-1 A09 7.6-6 Sh 2 R21 7.3-2 Sh 1 R03 7.6-6 Sh 3 A23 7.3-2 Sh 2 A23 7.6-6 Sh 4 R13 7.3-2 Sh 3 R16 7.6-6 Sh 5 R18 7.3-3 Sh 1 R15 7.6-6 Sh 6 A23 7.3-3 Sh 2 R00 7.6-6 Sh 7 A23 7.3-3 Sh 3 R00 7.6-7 A27 7.3-4 Sh 1 R00 7.6-8 R13 7.3-4 Sh 2 R15 7.6-9 Sh 1 A23 7.3-4 Sh 3 R00 7.6-9 Sh 2 A23 7.3-4 Sh 4 R00 7.6-9 Sh 3 A23 7.3-4 Sh 5 R16 7.6-9 Sh 4 A23 7.3-5 Sh 1 R00 7.6-9 Sh 5 A23 7.3-5 Sh 2 R16 7.6-9 Sh 6 R01 7.3-6 Sh 1 R00 7.6-9 Sh 7 A23 7.3-6 Sh 2 R19 7.6-9 Sh 8 A23 7.3-6 Sh 3 R16 7.6-9 Sh 9 A23 7.3-6 Sh 4 R19 7.6-9 Sh 10 R10 7.3-6 Sh 5 R00 7.7-1 Sh 1 R15 7.3-7 R22 7.7-1 Sh 2 R1 7.3-8 A09 7.7-1 Sh 3 A23 7.3-9 A09 7.7-1 Sh 4 R15 7.3-10 Sh 1 R08 7.7-1 Sh 5 A23 7.3-10 Sh 2 R13 7.7-1 Sh 6 R18 7.4-1 Sh 1 R22 7.7-1 Sh 7 R03 7.4-1 Sh 2 A23 7.7-2 Sh 1 R15 7.4-1 Sh 3 R15 7.7-2 Sh 2 R15 7.4-1 Sh 4 R20 7.7-2 Sh 3 R15 7.4-1 Sh 5 R10 7.7-2 Sh 4 R15 7.4-1 Sh 6 R15 7.7-2 Sh 5 R15 7.4-2 R13 7.7-2 Sh 6 R15 7.6-1 Sh 1 R22 7.7-2 Sh 7 A23 7.6-1 Sh 2 R22 7.7-2 Sh 8 R18 7.6-2 A00 7.7-2 Sh 9 R03 7.6-3 Sh 1 R20 7.7-2 Sh 10 A23 Chapter 07 EF 7-1 Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 LIST OF EFFECTIVE FIGURES (cont,d.)

Revision Revision Figure No. Number Figure No. Number 7.7-2 Sh 11 A23 7A.1-1 R00 7.7-2 Sh 12 A23 7A.1-2 R00 7.7-2 Sh 13 R18 7A.1-3 R00 7.7-2 Sh 14 R18 7A.1-4 R00 7.7-2 Sh 15 A23 7A.1-5 R00 7.7-2 Sh 16 A23 7A.1-6 R00 7.7-2 Sh 17 A23 7A.1-7 R00 7.7-2 Sh 18 A23 7A.1-8 R00 7.7-2 Sh 19 A23 7A.1-9 R00 7.7-2 Sh 20 A23 7A.6-1 R16 7.7-2 Sh 21 A23 7.7-2 Sh 22 A23 7.7-2 Sh 23(Deleted) R03 7.7-2 Sh 24 R04 7.7-2 Sh 25 R03 7.7-2 Sh 26 R09 7.7-2 Sh 27 A23 7.7-2 Sh 28 R09 7.7-2 Sh 29 A23 7.7-2 Sh 30 A23 7.7-2 Sh 31 R16 7.7-2 Sh 32 A23 7.7-2 Sh 33 R08 7.7-2 Sh 34 A23 7.7-2 Sh 35 R17 7.7-3 A00 7.7-4 A10 7.7-5 A00 7.7-6 Sh 1 A23 7.7-6 Sh 2 A23 7.7-6 Sh 3 R09 7.7-6 Sh 4 R00 7.7-6 Sh 5 A23 7.7-6 Sh 6 R00 7.7-6 Sh 7 R00 7.7-7 R00 7.7-8 R16 7.7-9 A00 7.7-10 R00 Chapter 07 EF 7-2 Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 INSTRUMENTATION AND CONTROL SYSTEMS TABLE OF CONTENTS Section Title

7.1 INTRODUCTION

7.1.1 Identification of Safety-Related Systems 7.1.1.1 Reactor Protection (Trip) System 7.1.1.2 Engineered Safety Features Systems 7.1.1.3 Systems Required For Safe Shutdown 7.1.1.4 Safety-Related Display Instrumentation 7.1.1.5 All Other Instrumentation Systems Required for Safety 7.1.2 Identification of Safety Criteria 7.1.2.1 Conformance to 10CFR50 Appendix A 7.1.2.2 Conformance to IEEE Standards 7.1.2.3 Conformance to Regulatory Guides 7.1.2.4 Instrument Errors 7.2 REACTOR PROTECTION (TRIP) SYSTEM INSTRUMENTATION AND CONTROLS 7.2.1 Reactor Protection System Description 7.2.1.1 Reactor Protection System Function 7.2.1.2 Reactor Protection System Operation 7.2.1.2.1 Neutron Monitoring System 7.2.1.2.2 Other Trip Signals 7.2.1.3 Testability 7.2.1.4 Design Basis 7.2.1.4.1 Location and Minimum Number of Sensors 7.2.1.4.2 Prudent Operational Limits 7.2.1.4.3 Margin 7.2.1.4.4 Levels 7.2.1.4.5 Range of Transient, Steady-State, and Environmental Conditions 7.2.1.4.6 Malfunctions, Accidents, and Other Unusual Events That Could Cause Damage to Safety Systems 7.2.1.4.7 Minimum Performance Requirements 7.2.1.5 Final System Drawings 7.2.2 Analysis 7.2.2.1 Conformance to 10CFR50, Appendix A, General Design Criteria 7.2.2.2 Conformance to IEEE Standards 7.2.2.2.1 Conformance to IEEE-279-1971 7.2.2.2.2 Conformance to IEEE-338-1971 7.2.2.2.3 Conformance to IEEE-344-1971 7.2.2.2.4 Conformance to IEEE-379-1972 Chapter 07 7-i Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 TABLE OF CONTENTS (Contd.)

Section Title 7.2.2.2.5 Conformance to IEEE-384-1974 7.2.2.3 Conformance to Regulatory Guides 7.3 ENGINEERED SAFETY FEATURE SYSTEMS 7.3.1 Description 7.3.1.1 System Descriptions 7.3.1.1.1 Emergency Core Cooling Systems -

Instrumentation and Controls 7.3.1.1.1.1 High-Pressure Core Spray System -

Instrumentation and Controls 7.3.1.1.1.2 Automatic Depressurization System -

Instrumentation and Controls 7.3.1.1.1.3 Low-Pressure Core Spray -

Instrumentation and Controls 7.3.1.1.1.4 RHR Low-Pressure Coolant Injection Mode - Instrumentation and Controls 7.3.1.1.2 Primary Containment and Reactor Vessel Isolation Control System (PCRVICS) - Instrumentation and Controls 7.3.1.1.3 RHR Containment Spray Cooling Mode

- Instrumentation and Controls 7.3.1.1.4 RHR Suppression Pool Cooling Mode

- Instrumentation and Controls 7.3.1.1.5 Standby Gas Treatment System 7.3.1.1.6 Combustible Gas Control System (Hydrogen Recombiners) 7.3.1.1.7 Reactor Building Heating, Ventilating, and Air Conditioning System 7.3.1.1.8 Service Water System 7.3.1.1.9 Service Water Pump Bays Ventilation System 7.3.1.1.10 Control Building Heating, Ventilating, and Air Conditioning System 7.3.1.1.11 Control Building Chilled Water System 7.3.1.1.12 Standby Power System 7.3.1.1.13 Diesel Generator Building Heating, Ventilating, and Air Conditioning System 7.3.1.2 Design Basis 7.3.1.2.1 Variables Monitored to Provide Protective Action 7.3.1.2.2 Location and Number of Sensors 7.3.1.2.3 Prudent Operational Limits 7.3.1.2.4 Margin 7.3.1.2.5 Levels Chapter 07 7-ii Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 TABLE OF CONTENTS (Contd.)

Section Title 7.3.1.2.6 Range of Transient, Steady-State, and Environmental Conditions 7.3.1.2.7 Malfunctions, Accidents, and Other Unusual Events That Could Cause Damage to Safety Systems 7.3.1.2.8 Minimum Performance Requirements 7.3.1.3 Final System Drawings 7.3.2 Analysis 7.3.2.1 ESF Systems - Instrumentation and Controls 7.3.2.1.1 Conformance to 10CFR50 Appendix A 7.3.2.1.2 Conformance to IEEE Standards 7.3.2.1.2.1 Conformance to IEEE-279-1971 7.3.2.1.2.2 Conformance to IEEE-338-1971 7.3.2.1.2.3 Conformance to IEEE-384-1974 7.3.2.1.3 Conformance to Regulatory Guides 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN 7.4.1 Description 7.4.1.1 Reactor Core Isolation Cooling System 7.4.1.2 Standby Liquid Control System 7.4.1.3 RHR/Reactor Shutdown Cooling Mode 7.4.1.4 Remote Shutdown System 7.4.1.5 Design Basis 7.4.1.5.1 Variables Monitored to Provide Protective Actions 7.4.1.5.2 Location and Minimum Number of Sensors 7.4.1.5.3 Prudent Operational Limits 7.4.1.5.4 Margin 7.4.1.5.5 Levels 7.4.1.5.6 Range of Transient, Steady-State, and Environmental Conditions 7.4.1.5.7 Malfunctions, Accidents, and Other Unusual Events That Could Cause Damage to Safety System 7.4.1.5.8 Minimum Performance Requirements 7.4.1.6 Final System Drawings 7.4.2 Analysis 7.4.2.1 Reactor Core Isolation Cooling System Instrumentation and Controls 7.4.2.1.1 Conformance to General Requirements 7.4.2.1.2 Conformance to 10CFR50 Appendix A 7.4.2.1.3 Conformance to IEEE Standards 7.4.2.1.3.1 Conformance with IEEE-279-1971 7.4.2.1.3.2 Conformance to IEEE-379-1972 7.4.2.1.4 Conformance to Regulatory Guides 7.4.2.2 Standby Liquid Control System Chapter 07 7-iii Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 TABLE OF CONTENTS (Contd.)

Section Title Instrumentation and Controls 7.4.2.2.1 Conformance to General Requirements 7.4.2.2.2 Conformance to 10CFR50 Appendix A 7.4.2.2.3 Conformance to IEEE Standards 7.4.2.2.3.1 Conformance to IEEE-279-1971 7.4.2.2.3.2 Conformance to IEEE-338-1971 7.4.2.2.3.3 Conformance to IEEE-379-1972 7.4.2.2.4 Conformance to Regulatory Guides 7.4.2.3 RHRS/Reactor Shutdown Cooling Mode (RSCM) Instrumentation and Controls 7.4.2.4 Remote Shutdown System 7.4.2.4.1 Conformance to General Requirements 7.4.2.4.2 Conformance to 10CFR50 Appendix A 7.4.2.4.3 Conformance to IEEE Standards 7.4.2.4.4 Conformance to Regulatory Guides 7.5 SAFETY-RELATED DISPLAY INSTRUMENTATION 7.5.1 Description 7.5.1.1 General 7.5.1.1.1 Transmitter/Trip Unit Main Control Room Indication 7.5.1.1.2 Reactor Water Level 7.5.1.1.3 Reactor Pressure 7.5.1.2 Reactor Shutdown Indication 7.5.1.3 Primary Containment and Reactor Vessel Isolation Indication 7.5.1.4 ECCS and RCIC Indication 7.5.1.5 Other Systems Indications 7.5.2 Analysis 7.5.2.1 Compliance With Regulatory/Industry Standards 7.5.3 Testing 7.6 ALL OTHER INSTRUMENTATION SYSTEMS REQUIRED FOR SAFETY 7.6.1 Description 7.6.1.1 Process Radiation Monitoring System

- Instrumentation and Controls 7.6.1.2 High-Pressure/Low-Pressure Interlocks - Instrumentation and Controls 7.6.1.3 Leak Detection System -

Instrumentation and Controls 7.6.1.4 Neutron Monitoring System -

Instrumentation and Controls 7.6.1.4.1 Intermediate Range Monitor Subsystem 7.6.1.4.2 Local Power Range Monitors Chapter 07 7-iv Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 TABLE OF CONTENTS (Contd.)

Section Title 7.6.1.4.3 Average Power Range Monitor Subsystem 7.6.1.5 Recirculation Pump Trip System -

Instrumentation and Controls 7.6.1.6 Safety/Relief Valves - Relief Function 7.6.1.7 Spent Fuel Pool Cooling and Cleanup System - Instrumentation and Controls 7.6.1.8 Redundant Reactivity Control System

- Instrumentation and Controls 7.6.1.9 Design Basis 7.6.1.9.1 Variables Monitored to Provide Protective Actions 7.6.1.9.2 Location and Minimum Number of Sensors 7.6.1.9.3 Prudent Operational Limits 7.6.1.9.4 Margin 7.6.1.9.5 Levels 7.6.1.9.6 Range of Transient, Steady-State, and Environmental Conditions 7.6.1.9.7 Malfunctions, Accidents, and Other Unusual Events That Could Cause Damage to Safety Systems 7.6.1.9.8 Minimum Performance Requirements 7.6.1.10 Final System Drawings 7.6.2 Analysis 7.6.2.1 Process Radiation Monitoring System

- Analysis 7.6.2.2 High-Pressure/Low-Pressure Interlocks - Analysis 7.6.2.2.1 Conformance to General Functional Requirements 7.6.2.2.2 Conformance to 10CFR50 Appendix A 7.6.2.2.3 Conformance to IEEE Standards 7.6.2.2.4 Conformance to Regulatory Guides 7.6.2.3 Leak Detection System (Safety Related) - Analysis 7.6.2.3.1 Conformance to General Functional Requirements 7.6.2.3.2 Specific Regulatory Requirements Conformance 7.6.2.3.2.1 Conformance to 10CFR50 Appendix A 7.6.2.3.2.2 Conformance to IEEE Standards 7.6.2.3.2.3 Conformance to Regulatory Guides 7.6.2.4 Neutron Monitoring System - Analysis 7.6.2.4.1 Conformance to General Functional Requirements - Intermediate Range Monitor Subsystem Chapter 07 7-v Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 TABLE OF CONTENTS (Contd.)

Section Title 7.6.2.4.2 Conformance to 10CFR50 Appendix A 7.6.2.4.3 Conformance to IEEE Standards 7.6.2.4.3.1 Conformance to IEEE-279-1971 7.6.2.4.3.2 Conformance to IEEE-338-1971 7.6.2.4.3.3 Conformance to IEEE-384-1974 7.6.2.4.4 Conformance to Regulatory Guides 7.6.2.5 Recirculation Pump (Trip) System -

Analysis 7.6.2.5.1 Conformance to 10CFR50 Appendix A 7.6.2.5.2 Conformance to IEEE Standards 7.6.2.5.2.1 Conformance to IEEE-279-1971 7.6.2.5.2.2 Conformance to IEEE-379-1972 7.6.2.5.2.3 Conformance to IEEE-384-1974 7.6.2.5.3 Conformance to Regulatory Guides 7.6.2.6 Safety/Relief Valves - Relief Function - Analysis 7.6.2.7 Spent Fuel Pool Cooling and Cleanup System - Analysis 7.6.2.7.1 Conformance to General Functional Requirements 7.6.2.7.2 Conformance to 10CFR50 Appendix A 7.6.2.7.3 Conformance to IEEE Standards 7.6.2.7.4 Conformance to Regulatory Guides 7.6.2.8 Redundant Reactivity Control System 7.6.2.8.1 Conformance to General Functional Requirements 7.6.2.8.2 Conformance to 10CFR50 Appendix A 7.6.2.8.3 Conformance to IEEE Standards 7.6.2.8.3.1 IEEE Standard 279-1971 7.6.2.8.3.2 IEEE Standard 388-1975 7.6.2.8.3.3 IEEE Standard 379-1972 7.6.2.8.4 Conformance to Regulatory Guides 7.6.3 References 7.7 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY 7.7.1 Description 7.7.1.1 Reactor Manual Control System -

Instrumentation and Controls 7.7.1.1.1 Reactor Manual Control System Function 7.7.1.1.2 RMCS Operation 7.7.1.1.3 RMCS Control Room Displays 7.7.1.1.4 Environmental Consideration 7.7.1.1.5 Rod Sequence Control Subsystem to the RMCS 7.7.1.1.6 Nuclear Measurement Analysis and Control Rod Worth Minimizer (NUMAC RWM)

Chapter 07 7-vi Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 TABLE OF CONTENTS (Contd.)

Section Title 7.7.1.2 Recirculation Flow Control System -

Instrumentation and Controls 7.7.1.3 Feedwater Control System -

Instrumentation and Controls 7.7.1.4 Refueling Interlocks -

Instrumentation and Controls 7.7.1.4.1 Refueling Interlocks Function 7.7.1.4.2 Refueling Interlocks Operation and Equipment 7.7.1.4.3 Level of Interlock Action 7.7.1.5 Steam Bypass and Pressure Regulation System 7.7.1.5.1 System Function 7.7.1.5.2 System Operation 7.7.1.6 Process Computer System (PMS) 7.7.1.7 Neutron Monitoring System (TIP, SRM, RBM) 7.7.1.7.1 Neutron Monitoring System -

Traversing In-Core Probe (TIP)

Subsystem 7.7.1.7.1.1 System Function 7.7.1.7.1.2 TIP System Operation 7.7.1.7.2 Source Range Monitor 7.7.1.7.2.1 Source Range Monitor Function 7.7.1.7.2.2 Source Range Monitor Operation 7.7.1.7.3 Rod Block Monitor 7.7.1.7.3.1 Rod Block Monitor Function 7.7.1.7.3.2 Rod Block Monitor Operation 7.7.1.8 Reactor Water Cleanup System 7.7.1.9 Leak Detection System 7.7.1.9.1 Reactor Vessel Head Seal Leak Detection 7.7.1.9.2 Safety/Relief Valve Seal Leak Detection 7.7.2 Analysis APPENDIX 7A SPECIAL STUDIES APPENDIX 7B ELECTRICAL SEPARATION Chapter 07 7-vii Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 LIST OF TABLES Table Number Title 7.1-1 DESIGN AND SUPPLY RESPONSIBILITY OF SAFETY-RELATED SYSTEMS 7.1-2 SAFETY-RELATED SYSTEMS SIMILARITY TO LICENSED REACTORS 7.1-3 CODES AND STANDARDS APPLICABILITY INDEX 7.1-4 EXAMPLES OF REGULATORY GUIDES APPLICABLE TO PLANT SYSTEMS 7.2-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SPECIFICATIONS 7.2-2 CATEGORY I INSTRUMENTATION WITH COMMON SENSING LINES 7.3-1 HIGH-PRESSURE CORE SPRAY SYSTEM INSTRUMENTATION SPECIFICATIONS 7.3-2 AUTOMATIC DEPRESSURIZATION SYSTEM INSTRUMENTATION SPECIFICATIONS 7.3-3 LOW-PRESSURE CORE SPRAY INSTRUMENT SPECIFICATIONS 7.3-4 LOW-PRESSURE COOLANT INJECTION INSTRUMENTATION SPECIFICATIONS 7.3-5 PRIMARY CONTAINMENT AND REACTOR VESSEL ISOLATION CONTROL SYSTEM INSTRUMENT SPECIFICATIONS 7.3-6 RHR CONTAINMENT SPRAY COOLING MODE INSTRUMENTATION SPECIFICATIONS 7.3-7 RHR SUPPRESSION POOL COOLING MODE INSTRUMENTATION SPECIFICATIONS 7.3-8 STANDBY GAS TREATMENT SYSTEM INSTRUMENTATION SPECIFICATIONS 7.3-9 COMBUSTIBLE GAS CONTROL SYSTEM INSTRUMENTATION SPECIFICATIONS 7.3-10 REACTOR BUILDING HVAC SYSTEM INSTRUMENTATION SPECIFICATIONS Chapter 07 7-viii Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 LIST OF TABLES (Contd.)

Table Number Title 7.3-11 SERVICE WATER SYSTEM INSTRUMENTATION SPECIFICATIONS 7.3-12 SERVICE WATER PUMP BAYS VENTILATION SYSTEM INSTRUMENTATION SPECIFICATIONS 7.3-13 CONTROL BUILDING HVAC SYSTEM INSTRUMENTATION SPECIFICATIONS 7.3-14 CONTROL BUILDING CHILLED WATER SYSTEM INSTRUMENTATION SPECIFICATION 7.3-15 STANDBY POWER SYSTEM INSTRUMENTATION SPECIFICATIONS 7.3-16 DIESEL GENERATOR BUILDING HVAC INSTRUMENTATION SPECIFICATIONS 7.4-1 REACTOR CORE ISOLATION COOLING INSTRUMENT SPECIFICATIONS 7.5-1 SAFETY-RELATED DISPLAY INSTRUMENTATION 7.5-2 CONFORMANCE TO REGULATORY GUIDE 1.97 (REVISION 3) 7.6-1 HIGH-PRESSURE/LOW-PRESSURE INTERLOCKS INSTRUMENTATION SPECIFICATIONS 7.6-2 DELETED 7.6-3 LEAK DETECTION SYSTEM INSTRUMENTATION SPECIFICATIONS 7.6-4 IRM INSTRUMENT SPECIFICATIONS 7.6-5 LPRM SYSTEM INSTRUMENT SPECIFICATIONS 7.6-6 APRM SYSTEM TRIPS INSTRUMENT SPECIFICATION 7.7-1 DESIGN AND SUPPLY RESPONSIBILITY OF PLANT CONTROL SYSTEM 7.7-2 SIMILARITY OF UNIT 2 TO OTHER PLANTS 7.7-3 REFUELING INTERLOCK EFFECTIVENESS Chapter 07 7-ix Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 LIST OF FIGURES Figure Number Title 7.2-1 REACTOR PROTECTION SYSTEM (SHEETS 1 THROUGH 5) 7.3-1 EMERGENCY COOLING SYSTEM NETWORK 7.3-2 HPCS SYSTEM FCD (SHEETS 1 THROUGH 3) 7.3-3 HPCS POWER SUPPLY FCD (SHEETS 1 THROUGH 3) 7.3-4 NBS FCD (SHEETS 1 THROUGH 5) 7.3-5 LPCS FCD (SHEETS 1 AND 2) 7.3-6 RHR SYSTEM FCD (SHEETS 1 THROUGH 5) 7.3-7 REACTOR WATER CLEANUP SYSTEM 7.3-8 ISOLATION CONTROL SYSTEM FOR MAIN STEAM LINE ISOLATION VALVES 7.3-9 ISOLATION CONTROL SYSTEM USING MOTOR-OPERATED VALVES 7.3-10 BALANCE OF PLANT ESF ACTUATION LOGIC DIAGRAM (SHEETS 1 AND 2) 7.4-1 RCIC FCD (SHEETS 1 THROUGH 6) 7.4-2 SBLC FCD 7.6-1 LEAK DETECTION SYSTEM (SHEETS 1 AND 2) 7.6-2 RANGES OF NEUTRON MONITORING SYSTEM 7.6-3 NMS IED (SHEETS 1 AND 2) 7.6-4 DETECTOR DRIVE SYSTEM 7.6-5 FUNCTIONAL BLOCK DIAGRAM OF IRM CHANNEL 7.6-6 NEUTRON MONITORING SYSTEM (SHEETS 1 THROUGH 7) 7.6-7 POWER RANGE MONITOR DETECTOR ASSEMBLY LOCATION 7.6-8 APRM CIRCUIT ARRANGEMENT FOR REACTOR PROTECTION SYSTEM INPUT CHAPTER 7 Chapter 07 7-x Rev. 22, October 2016

NMP Unit 2 USAR CHAPTER 7 LIST OF FIGURES (Contd.)

Figure Number Title 7.6-9 REDUNDANT REACTIVITY CONTROL SYSTEM (SHEETS 1 THROUGH 10) 7.7-1 CONTROL ROD DRIVE HYDRAULIC SYSTEM (SHEETS 1 THROUGH 7) 7.7-2 REACTOR MANUAL CONTROL SYSTEM (SHEETS 1 THROUGH 35) 7.7-3 REACTOR MANUAL CONTROL SYSTEM OPERATION 7.7-4 REACTOR MANUAL CONTROL SELF-TEST PROVISIONS 7.7-5 ELEVEN-WIRE POSITION PROBE 7.7-6 REACTOR RECIRCULATION SYSTEM (SHEETS 1 THROUGH 7) 7.7-7 FLOW CONTROL SYSTEM BLOCK DIAGRAM 7.7-8 FEEDWATER CONTROL SYSTEM 7.7-9 SIMPLIFIED DIAGRAM PRESSURE CONTROL SYSTEM 7.7-10 SIMPLIFIED DIAGRAM TURBINE PRESSURE AND SPEED-LOAD CONTROL REQUIREMENTS Chapter 07 7-xi Rev. 22, October 2016

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