ML17046A410

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Revision 29 to Updated Final Safety Analysis Report, Section 7, Table of Contents
ML17046A410
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/30/2017
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
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ML17046A230 List: ... further results
References
LR-N17-0034
Download: ML17046A410 (11)
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Section 7.1 7 .1.1 7.1.1.1 7.1.1.2 7.1.1.3 7 .1. 2 7.1.2.1 7.1.2.2 7.1.2.2.1 7.1.2.2.2 7.1.2.2.3 7.1.2.2.4 7.1.2.2.5 7.1.2.3 7.1.2.4 7.1.2.5 7.1.2.6 7.1.2.7 7.1.2.8 7.1.2.9 7 .1. 3 7 .1. 4 SGS-UFSAR SECTION 7 INSTRUMENTATION AND CONTROLS TABLE OF CONTENTS Title INTRODUCTION Identification of Safety-Related Systems Reactor Trip Systems Fission Process Monitors and Controls Plant Comparison Identification of Safety Criteria Design Bases Independence of Safety-Related Systems Redundancy and Independence of Safety-Related Systems Protection Against Multiple Disability for Safety-Related Systems Demonstration of Functional Operability of Safety-Related Systems Protection System Failure Analysis Design Reactivity Control Systems' Malfunctions Missile Protection Periodic Testing of the Protection Systems (IEEE Standard 338-1971) Conformance to IEEE Standard 344-1971 Conformance and Exceptions to IEEE Standard 323-1971 Conformance to IEEE Standard 336-1971 Conformance to 10CFR50.62 Instrumentation Piping/Tubing Code Reconciliation Associated With Unit 2 SGR Control Room Design Review References for Section 7.1 7-i Page 7.1-1 7.1-2 7.1-2 7.1-2 7.1-3 7.1-3 7.1-3 7.1-4 7.1-4 7.1-6 7.1-6 7.1-7 7.1-7 7.1-8 7.1-9 7.1-10 7.1-11 7.1-11 7.1-11 7.1-11 7.1-12 7.1-13 Revision 24 May 11, 2009 Section 7.2 7.2.1 7.2.1.1 7.2.1.2 7.2.1.3 7.2.1.4 7.2.1.5 7.2.1.6 7.2.1.7 7.2.1.8 7.2.1.9 7 .2.1.10 7 .2.1.11 7.2.2 7.2.2.1 7.2.2.2 7.2.2.3 7.2.2.4 7.2.2.5 7.2.2.6 7.2.3 7.2.3.1 7.2.3.2 7.2.3.3 7.2.3.4 7.2.4 SGS-UFSAR TABLE OF CONTENTS (Cont) Title REACTOR TRIP SYSTEM Description System Description Nuclear Instrumentation Principles of Design Electrical Isolation Protection System Identification Manual Actuation Channel Bypass or Removal from Operation Capability for Test and Calibration Information Readout and Indication of Bypass Vital Protective Functions and Functional Requirements Operating Environment Design Basis Information Separation of Redundant Instrumentation and Controls Design Basis for Protection Circuits Reactor Protection System Testing Primary Power Source Protective Actions Reactor coolant Flow Measurement System Evaluation Reactor Protection System and Departure from Nucleate Boiling Page 7.2-1 7.2-1 7.2-1 7.2-2 7.2-3 7.2-3 7.2-4 7.2-4 7.2-5 7.2-5 7.2-6 7.2-6 7.2-8 7.2-8 7.2-8 7.2-9 7.2-14 7.2-17 7.2-17 7.2-25 7.2-26 7.2-26 Specific Control and Protection Interactions 7.2-27 Reactor Trip Breakers 7.2-37 Tests and Inspections References for Section 7.2 7-ii 7.2-38 7.2-39 Revision 15 June 12, 1996 * * *

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  • Section 7.3 7.3.1 7.3.1.1 7.3.1.1.1 7 .3.1.1.2 7.3.1.1.3 7.3.1.1.4 7.3.1.1.5 7.3.1.1.6 7.3.1.1.7 7.3.1.1.8 7.3.1.1.9 7. 3 .1.1.10 7. 3 . 1.1.10. 1 7. 3 .1.1.10. 2 7 . 3 .1. 1. 10. 3 7. 3 .1.1.10 .4 TABLE OF CONTENTS (Cont) ENGINEERED SAFETY FEATURES INSTRUMENTATION Description System Design 7.3-3 Engineered Safety Features Actuation Instrumentation Description 7.3-3 Engineered Safety Features and Associated Systems' Actuation Engineered Safety Features Vital Functions Engineered Safety Features Calibration and Test 7.3-4 7.3-4 7.3-5 Feedwater Isolation 7.3-5 Main Steam Isolation 7.3-5 Indication 7.3-6 Engineered Safety Features Instrumentation Instrumentation Used During a Loss-of-Coolant Accident (LOCA) Engineered Safety Features Control Safety Injection Only Blackout Only Safety Injection Plus Blackout Safety Injection Plus One 4 kV Vital Bus Undervoltage 7.3-9 7.3-11 7.3-13 7.3-13 7.3-14 7.3-15 7.3.1.1.10.5 Sustained Degraded Vital Bus Voltage (Degraded Grid) 7.3-16 7.3-16 7.3-16a 7.3-16a 7.3-17 7.3-18 7.3-19 7.3-19 7. 3. 1. 1.10. 6 7.3.1.2 7.3.1.2.1 7.3.1.2.2 7.3.2 7.3.2.1 7.3.2.2 7.3.2.3 7.3.2.4 7.3.2.5 SGS-UFSAR Tests and Inspections Design Bases General Design Criteria Environmental Capability System Evaluation Pressurizer Pressure Motor and Valve Control Manual Control of Engineered Safety Features 7.3-20 Testing 7.3-21 Containment Flooding Analysis 7.3-27 7-iii Revision 13 June 12, 1994 section 7.3.2.6 7.3.2.7 7.3.3 7.4 7.4.1 7.4.2 7.5 7.5.1 7.5.2 7.5.3 7.5.3.1 7.5.3.2 7.5.3.3 7.6 7.6.1 7.6.2 7.6.3 7.6.3.1 7.6.3.2 7.6.3.3 7.6.4 7.6.5 7.7 7.7.1 7.7.1.1 SGS-UFSAR TABLE OF CONTENTS ( COnt) Single Failure of Components Electrical Interlocks References fer Section 7.3 SYSTEMS REQUIRED FOR SAFE SHOTDOWN Bot Shutdown outside the control Room Cold Shutdown OUtside the COntrol Room SAFETY-RELATED DISPLAY INSTRUMENTATION Description Bypass Indication Evaluation Identification of Design Basis Differences from Regulatory Guide 1.97 Regulatory Guide 1.97 Compliance Levels Planned Actions ALL OTHER INSTRUMENTATION REQUIRED FOR SAFETY Residual Heat Removal Isolation Valves Accumulator Isolation Valves Pressurizer overpressure Protection System (POPS) Design Basis system Design and Operation Design Evaluation Feedwater Pump Turbine Trips References fer Section 7.6 CONTROL SYSTEMS NOT REQUIRED FOR SAFETY Design Basis Reactor control system 7-iv 7.3-31 7.3-31a 7.3-36 7.4-1 7.4-1 7.4-2 7.5-1 7.5-1 7.5-2 7.5-6 7.5-7 7.5-11 7.5-13 7.6-1 7.6-1 7.6-2 7.6-3 7.6-3 7.6-5 7.6-6 7.6-7 7.6-8 7.7-1 7.7-1 7.7-1 Revision 16 January 31, 1998
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  • Section 7.7.1.2 7.7.2 7.7.2.1 7.7.2.2 7.7.2.2.1 7.7.2.2.2 7.7.2.3 7.7.2.3.1 7.7.2.3.2 7.7.2.4 7.7.2.5 7.7.2.6 7.7.2.7 7.7.2.8 7.7.2.9 7.7.2.10 7.7.2.11 7.7.2.12 7.7.2.13 7.7.3 7.7.3.1 7.7.3.2 7.7.3.3 7.7.3.4 7.7.3.5 7.7.3.6 7.7.3.6.1 7.7.3.6.2 7.7.3.7 7.7.3.7.1 7.7.3.7.2 7.7.3.8 7.7.4 7.8 SGS-UFSAR TABLE OF CONTENTS (Cant) Title Operating Control Stations System Design Rod Cluster Control Assembly Arrangements Rod Control Control Bank Rod Insertion Monitor Rod Deviation Alarm Plant Control System Interlocks Rod Stops Automatic Turbine Load Runback Pressurizer Pressure Control Pressurizer Level Control Steam Generator Water Level Control Steam Dump Control In-core Instrumentation Operating Control Stations Plant Alarm and Annunciator Systems Residual Heat Removal Performance Monitoring System Seismic Monitoring Instrumentation Meteorological Monitoring Instrumentation System Design Evaluation Unit Stability Step Load Changes Without Steam Dump Loading and Unloading Loss of Load With Steam Dump Turbine Generator Trip With Reactor Trip In-core Instrumentation Thermocouples Moveable Miniature Neutron Flux Detectors Operating Control Systems Control Room Availability Control Room Evaluation Secondary System Design Evaluation References for Section 7.7 ATWS MITIGATION SYSTEM ACTUATION CIRCUITRY {AMSAC) 7-v 7.7-4 7.7-5 7,7-6 7,, 7-6 7.7-7 7.7-8 7.7-8 7.7-8 7.7-8 7.7-9 7.7-9 7.7-10 7.7-12 7.7-13 7,7..,15 7.7-21 7.7-21 7.7-21a 7.7-21a 7.7-21a 7.7-21a 7.7-22 7.7...;23 7.7-23 7.7-25 7.7-25 7.7-26 7.7-28 7.7-28 7.7-29 7.7-29 7.7-30 7.8-1 Revision 23 October 17, 2007 I 7.8.il 7 .8. 1.1 7. 8 .1. 2 7.8.1.3 7.8.1.4 7.8.1.5 7.8.1.6 7.8.1.7 7.8.1.8 7.8.1.9 7.8.1.10 7.8.1.11 7.8.1.12 7.8.2 7.8.(2.1 7.8.2.2 7.8.2.3 7.8.2.4 7.8.2.5 7.8.2.6 7.8.2.7 7.8.2.8 7.8.2.9 7.8.2.10 7.8.2.11 7.8.2.12 7.8.t2.13 7.8.2.14 7.8.2.15 SGS-OFSAR TABLE OF CONTENTS (Cant) Title Description Description Equipment Description Performance Requirements AMSAC Interlocks 7.8-1 7.8-1 7.8-2 7.8-4 7.8-4 Steam Generator Level Sensor Arrangement 7.8-5 Turbine Steamline Inlet Pressure Arrangement 7.8-5 Trip System 7.8-5 Isolation Devices 7.8-5 AMSAC Diversity From the Reactor Protection System Power Supply Environmental Variations Setpoints Analysis Safety Classification/Safety-Related Interface Redundancy Diversity From the Existing Trip System Electrical Independence Physical From the RTS and ESFAS Environmental Qualification Qualification Test, Maintenance, and Surveillance Quality Assurance Power Supply Testability at Power Inadvertent Actuation Maintenance Bypasses Operating Bypasses Indication of Bypasses Means for Bypassing 7-va 7.8-6 7.8-6 7.8-7 7.8-7 7.8-8 7.8-8 7.8-8 7.8-8 7.8-8 7.8-9 7.8-9 7.8-9 7.8-9 7.8-10 7.8-10 7. 8-11 7. 8-11 7.8-11 7.8-12 7.8-12 Revision 21 December 6, 2004 * * *
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  • section 7.8.2.16 7.8.2.17 7.8.2.18 7.8.3 7.9 7.9.1 7.9.2 7.10 7.10.1 7.10.2 7.10.3 7.10.4 7.10.4.1 7.10.4.2 7.10.4.3 7.10.4.4 7.10.5 7.10.6 7.10.7 7.10.8 7.10.9 7A 7A.l 7A.2 7A.3 7A.4 7A.S 7A.6 SGS-UFSAR TABLE OF CONTENTS (Cont) Completion of Mitigative Actions Once Initiated Manual Initiation Information Readout compliance With Standards and Design Criteria PHYSICAL SEPARATION AND ELECTRICAL ISOLATION Physical Separation Electrical Isolation SAFETY PARAMETER DISPLAY SYSTEM (SPDS) Functional Description System Description Computer subsystem Display Subsystem Top Level Display Second Level Display Third Level Display Fourth Level Display Human Factors Isolation Parameter Selection Data Validation References Program Element Descriptions Resulting From the Implementation of the May 6, 1983 order Introduction Training Procurement and Management Operating Procedures Maintenance and Surveillance Control of Vendor Information 7-vb 7.8-12 7.8-13 7.8-13 7.8-13 7.9-1 7.9-1 7.9-5 7.10-1 7.10-1 7.10-1 7.10-2 7.10-2 7.10-2 7.10.2 7.10-3 7.10-3 7.10-3 7.10-3 7.10-3 7.10-4 7.10-5 7A-1 7A-2 7A-2 7A-3 7A-4 7A-5 7A-6 Revision 15 June 12, 1996 7.2-1 7.2-2 7.2-3 7.2-4 7.2-5 7.3-1 7.3-2 7.3-3 7.3-4 7.3-5 7.3-6 7.3-7 I SGS-UFSAR LIST OF TABLES List of Reactor Trips, Engineered Safety Features1 Containment and Steam Line Isolation and Auxiliary Feedwater Interlock Circuits Legend of Analog Symbols Salem Unit 1 -Reactor Trip System Instrument Response Times Salem Unit 2 Reactor Trip System Instrument Response Times Process Instrumentation for RPS and ESF Actuation Post-Accident Equipment (Inside Containment) Operational and Testing Requirements Postulated Submerged Electrical Components in the Containment Following a LOCA Safety Evaluation -Electrical Components and Circuits That are Affected by the Flooding of Components Within the Containment During Post-LOCA Conditions Safety Evaluation Submerged Electrical Components in the Containment During Post-LOCA Conditions Safety Evaluation -Electrical Components and Circuits That are Affected by the Flooding of Components Within The Containment During Post-LOCA Conditions Safety Evaluation -Electrical Components and Circuits That are Affected by the Flooding of Components Within the Containment During Post-LOCA Conditions -Junction/Terminal Boxes 7-vi Revision 23 October 171 2007 * * *
  • 7.3-8 7.3-9 7.5-l 7.5-2 7.5-3 7.5-4 7.5-5
  • 7.7-1 7.7-2 7.7-3 7.7-4 7,7-5 7.7-6 7.10-1 7.10-2 7.10-3
  • SGS-UFSAR LIST OF TABLES (Cont) Salem Unit 1 -Engineered Safety Features Response Times Salem Unit 2 -Engineered Safety Features Response Times Main Control Room Indicators and/or Recorders Available to the Operator Main Control Room Indicators and/or Recorders Available to the Operator to Monitor Significant Plant Parameters During Normal Operation Index Type "A" Variables Summary of Instrumentation Compliance with Regulatory Guide 1.97 Justification for Nonconformance to Regulatory Guide 1.97 Rod Stops Overhead Annunciator Groupings Seismic Monitoring Instrumentation Seismic Monitoring Instrumentation Surveillance Requirements Meteorological Monitoring Instrumentation Meteorological Requirements Monitoring Instrumentation Surveillance Safety Parameter Display System Parameters Comparisons of Safety Functions with NUREG-0737 Supplement 1 Critical Safety Functions Associated with Barriers 7-vii Revision 23 October 17, 2007 Figure 7.2-1 7.2-2 7.2-3 7.2-4 7.2-5 7.2-6 7.2-7 7.3-1 7.3-2 7.3-3 7.3-4 7.6-1 7.7-1 7.7-2 7.7-3 7.7-4 SGS-UFSAR LIST OF FIGURES Title Illustration of Overpower and Overtemperature Setpoints ( vs Tavg) Deleted: Refer to Plant Drawing 221051 Setpoint Reduction Function for Overpower and Overtemperature Trips Pressurizer Pressure Control and Protection System Pressurizer Level Control and Protection System Pressurizer Sealed Reference Leg Level System Steam Generator Level Control and Protection System Containment Pressure Instrumentation Typical MOV 230 V Power Lockout Typical MOV Control Power Lockout without Interposing Relay Typical MOV Control Power Lockout with Interposing Relay Accumulator Discharge Valves -Status Monitoring Block Diagram of Reactor Control System Control Bank Rod Insertion Monitor Rod Deviation Comparator In-Core Instrumentation Details 7-viii Revision 27 November 25, 2013 Figure 7.7-5 7.7-6 7.7-7 7.7-8 7.7-9
  • SGS-UFSAR LIST OF FIGURES (Cant) Title Schematic Arrangement of In-Core Flux Detectors (Plan View) Typical Arrangement of Movable Miniature Neutron Flux Detector system (Elevation) Advanced Digital Feedwater Control System Input Signal Validation Scheme Advanced Digital Feedwater Control System Feedwater Control Functional Logic with Algorithms Advanced Digital Feedwater Control System Feedwater Control Valve Linearization Functional Block Diagram 7-ix Revision 17 October 16, 1998
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