ML21133A067
| ML21133A067 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 04/29/2021 |
| From: | Exelon Generation Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML21138A803 | List:
|
| References | |
| Download: ML21133A067 (10) | |
Text
LGS UFSAR CHAPTER 1 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT TABLE OF CONTENTS
1.1 INTRODUCTION
1.2 GENERAL PLANT DESCRIPTION 1.2.1 Site Characteristics 1.2.1.1 Location 1.2.1.2 Site Environs and Access 1.2.1.3 Geology 1.2.1.4 Seismology 1.2.1.5 Hydrology 1.2.1.6 Meteorology 1.2.2 Principal Design Criteria 1.2.2.1 General Design Criteria 1.2.2.2 System Design Criteria 1.2.2.2.1 Nuclear System Criteria 1.2.2.2.2 Safety-Related Systems Criteria 1.2.2.2.3 Process Control Systems Criteria 1.2.2.2.4 Power Conversion Systems Criteria 1.2.2.2.5 Electrical Power Systems Criteria 1.2.2.2.6 Auxiliary Systems Criteria 1.2.2.2.7 Radioactive Waste Management Systems Criteria 1.2.2.2.8 Shielding and Access Control Criteria 1.2.2.2.9 Fuel Handling and Storage Facilities 1.2.3 General Arrangement of Structures and Equipment 1.2.4 System Description 1.2.4.1 Nuclear System 1.2.4.1.1 Reactor Core and Control Rods 1.2.4.1.2 Reactor Vessel and Internals 1.2.4.1.3 Reactor Recirculation System 1.2.4.1.4 Residual Heat Removal System 1.2.4.1.5 Reactor Water Cleanup System 1.2.4.1.6 Nuclear Leak Detection System 1.2.4.2 Safety-Related Systems 1.2.4.2.1 Reactor Protection System 1.2.4.2.2 Neutron Monitoring System 1.2.4.2.3 Control Rod Drive System 1.2.4.2.4 Control Rod Velocity Limiter 1.2.4.2.5 Control Rod Drive Housing Supports 1.2.4.2.6 Nuclear System Pressure Relief System 1.2.4.2.7 Reactor Core Isolation Cooling System 1.2.4.2.8 Primary Containment CHAPTER 01 1-i REV. 16, SEPTEMBER 2012
LGS UFSAR TABLE OF CONTENTS (cont'd) 1.2.4.2.9 Primary Containment and Reactor Vessel Isolation Control System 1.2.4.2.10 Secondary Containment 1.2.4.2.11 Main Steam Isolation Valves 1.2.4.2.12 Main Steam Line Flow Restrictors 1.2.4.2.13 Emergency Core Cooling Systems 1.2.4.2.14 Residual Heat Removal System (Containment Cooling) 1.2.4.2.15 Control Room Heating, Ventilating and Air Conditioning System 1.2.4.2.16 Reactor Enclosure Recirculation System and Standby Gas Treatment System 1.2.4.2.17 Standby AC Power Supply 1.2.4.2.18 DC Power Supply 1.2.4.2.19 Residual Heat Removal Service Water System 1.2.4.2.20 Emergency Service Water System 1.2.4.2.21 Main Steam Line Radiation Monitoring System 1.2.4.2.22 Reactor Enclosure and Refueling Area Ventilation Radiation Monitoring System 1.2.4.2.23 Remote Shutdown System 1.2.4.2.24 Standby Liquid Control System 1.2.4.2.25 Information in Section Deleted 1.2.4.2.26 Redundant Reactivity Control System 1.2.4.3 Instrumentation and Control Systems 1.2.4.3.1 Nuclear System Process Control and Instrumentation 1.2.4.3.2 Power Conversion Systems Process Control and Instrumentation 1.2.4.4 Electrical Systems 1.2.4.4.1 Transmission and Generation Systems 1.2.4.4.2 Electric Power Distribution Systems 1.2.4.5 Fuel Handling and Storage Systems 1.2.4.5.1 New and Spent Fuel Storage 1.2.4.5.2 Fuel Pool Cooling and Cleanup System 1.2.4.5.3 Fuel Handling Equipment 1.2.4.6 Cooling Water and Auxiliary Systems 1.2.4.6.1 Service Water System 1.2.4.6.2 Reactor Enclosure Cooling Water System 1.2.4.6.3 Turbine Enclosure Cooling Water System 1.2.4.6.4 Fire Protection System 1.2.4.6.5 Plant Heating, Ventilating, and Air Conditioning Systems 1.2.4.6.6 Instrument Air System 1.2.4.6.7 Clarified Water System 1.2.4.6.8 Demineralized Water Makeup System 1.2.4.6.9 Plant Equipment and Floor Drainage System 1.2.4.6.10 Process Sampling System 1.2.4.6.11 Plant Communication System 1.2.4.7 Power Conversion Systems 1.2.4.7.1 Turbine-Generator 1.2.4.7.2 Main Steam System 1.2.4.7.3 Main Condenser 1.2.4.7.4 Main Condenser Evacuation System 1.2.4.7.5 Steam Seal System 1.2.4.7.6 Turbine Bypass and Pressure Control System 1.2.4.7.7 Circulating Water System CHAPTER 01 1-ii REV. 16, SEPTEMBER 2012
LGS UFSAR TABLE OF CONTENTS (cont'd) 1.2.4.7.8 Condensate Cleanup System 1.2.4.7.9 Condensate and Feedwater Systems 1.2.4.7.10 Condensate and Refueling Water Storage Facilities 1.2.4.8 Radioactive Waste Systems 1.2.4.8.1 Liquid Radwaste System 1.2.4.8.2 Solid Radwaste System 1.2.4.8.3 Gaseous Radwaste System 1.2.4.9 Radiation Monitoring and Control 1.2.4.9.1 Process Radiation Monitoring 1.2.4.9.2 Area Radiation Monitors 1.2.4.9.3 Site Environs Radiation Monitors 1.2.4.10 Shielding 1.2.5 Control of Unit 2 Construction Activities During Unit 1 Operation 1.3 COMPARISON TABLES 1.3.1 Comparisons with Similar Facility Designs 1.3.2 Comparison of Final and Preliminary Information 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS 1.4.1 Applicant 1.4.2 Architect-Engineer and Constructor 1.4.3 Nuclear Steam Supply System Supplier 1.4.4 Turbine-Generator Supplier 1.4.5 Consultants 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION 1.5.1 Current Development Programs 1.5.1.1 Instrumentation for Vibration of Reactor Intervals 1.5.1.2 Core Spray Distribution 1.5.1.3 Core Spray and Core Flooding Heat Transfer Effectiveness 1.5.1.4 Verification of Pressure-Suppression Design 1.5.1.5 Critical Heat Flux Testing 1.5.1.6 Fuel Assembly Structural Testing 1.5.2 References 1.6 MATERIAL INCORPORATED BY REFERENCE/GENERAL REFERENCE 1.7 DRAWINGS AND OTHER DETAILED INFORMATION 1.8 CONFORMANCE TO NRC REGULATORY GUIDES 1.9 STANDARD DESIGNS 1.10 SYMBOLS AND TERMS CHAPTER 01 1-iii REV. 16, SEPTEMBER 2012
LGS UFSAR TABLE OF CONTENTS (cont'd) 1.10.1 Text Acronyms 1.10.2 Logic Symbols 1.10.3 Piping Identification 1.10.4 Valve Identification 1.10.5 Equipment Numbering and Location 1.10.6 Electrical Component Identification 1.10.6.1 Equipment Location Numbers 1.10.6.2 Scheme Cable Numbers 1.10.6.3 Raceway Numbers 1.11 RRRC CATEGORY 1, 2, 3, AND 4 MATTERS 1.11.1 Discussion of Categories 1.11.2 References 1.12 UNRESOLVED SAFETY ISSUES 1.12.1 Introduction 1.12.2 Applicability to LGS 1.12.3 Discussions of Tasks as They Relate to LGS 1.12.4 References 1.13 TMI-2 RELATED REQUIREMENTS FOR NEW OPERATING LICENSES 1.13.1 NUREG-0737, Clarification of the TMI Action Plan Requirements 1.13.2 TMI Action Plan Requirements for Applicants for an Operating License (Enclosure 2 to NUREG-0737) 1.13.3 References CHAPTER 01 1-iv REV. 16, SEPTEMBER 2012
LGS UFSAR CHAPTER 1 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT LIST OF TABLES TABLE TITLE 1.3-1 Comparison of Nuclear Steam Supply System Design Characteristics 1.3-2 Comparison of Engineered Safety Features and Auxiliary Systems Design Characteristics 1.3-3 Comparison of Power Conversion System Design Characteristics 1.3-4 Comparison of Containment Design Characteristics 1.3-5 Comparison of Structural Design Characteristics 1.3-6 Radioactive Waste Management Systems Design Characteristics 1.3-7 Comparison of Electrical Power Systems Design Characteristics 1.3-8 Significant Design Changes from PSAR to FSAR 1.6-1 Referenced Reports 1.7-1 Electrical Drawings 1.7-2 Figure Index for Plant Systems 1.7-3 Control and Instrumentation Drawings 1.7-4 Figure Index for Miscellaneous Drawings 1.8-1 Component Identification for Code Case N242 1.10-1 Acronyms Used in UFSAR 1.10-2 Piping and Valve Class Identification 1.11-1 Correlation of LGS UFSAR Sections with Category 2, 3, and 4 Matters 1.13-1 Vital Area Radiation Doses 1.13-2 Radiation Doses for Vital Area Access Paths 1.13-3 Solutions to Potential Vital Area Access Problems CHAPTER 01 1-v REV. 16, SEPTEMBER 2012
LGS UFSAR LIST OF TABLES (cont'd)
TABLE TITLE 1.13-4 Potential Unplanned Release Paths 1.13-5 Access Path Identification 1.13-6 Radiation Qualification of Safety-Related Equipment 1.13-7 X/Q Values for Vital Areas 1.13-8 High-Range Noble Gas Effluent Monitors (Table II.F.1-1) 1.13-9.1 Interim Procedures for Quantifying High-Level Accidental Radioactivity Releases (Table II.F.1-2) 1.13-10 Sampling and Analysis or Measurement of High-Range Radioiodine and Particulate Effluents in Gaseous Effluent Streams (Table II.F.1-3) 1.13-11 Containment High-Range Radiation Monitor (Table II.F.1-4) 1.13-12 Information Required for Control Room Habitability Evaluation (Table III.D.3.4-1)
CHAPTER 01 1-vi REV. 16, SEPTEMBER 2012
LGS UFSAR CHAPTER 1 - INTRODUCTION AND GENERAL DESCRIPTION OF PLANT LIST OF FIGURES FIGURE TITLE 1.2-1 Deleted 1.2-2 Deleted 1.2-3 Deleted 1.2-4 Deleted 1.2-5 Deleted 1.2-6 Deleted 1.2-7 Deleted 1.2-8 Deleted 1.2-9 Deleted 1.2-10 Deleted 1.2-11 Deleted 1.2-12 Deleted 1.2-13 Deleted 1.2-14 Deleted 1.2-15 Deleted 1.2-16 Deleted 1.2-17 Deleted 1.2-18 Deleted 1.2-19 Deleted 1.2-20 Deleted 1.2-21 Deleted 1.2-22 Deleted CHAPTER 01 1-vii REV. 16, SEPTEMBER 2012
LGS UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE 1.2-23 Deleted 1.2-24 Deleted 1.2-25 Deleted 1.2-26 Deleted 1.2-27 Deleted 1.2-28 Deleted 1.2-29 Deleted 1.2-30 Deleted 1.2-31 Deleted 1.2-32 Deleted 1.2-33 Deleted 1.2-34 Deleted 1.2-35 Deleted 1.2-36 Deleted 1.2-37 Deleted 1.2-38 Deleted 1.2-39 Deleted 1.2-40 Deleted 1.2-41 Deleted 1.2-42 Deleted 1.2-43 Deleted 1.2-44 Deleted 1.2-45 Deleted CHAPTER 01 1-viii REV. 16, SEPTEMBER 2012
LGS UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE 1.2-46 Deleted 1.2-47 Deleted 1.2-48 Deleted 1.2-49 Deleted 1.2-50 Deleted 1.2-51 Deleted 1.2-52 Deleted 1.2-53 Deleted 1.2-54 Deleted 1.2-55 Deleted 1.2-56 Deleted 1.2-57 Deleted 1.2-58 Deleted 1.2-59 Deleted 1.2-60 Deleted 1.2-61 Deleted 1.2-62 Deleted 1.2-63 Deleted 1.2-64 Deleted 1.2-65 Deleted 1.2-66 Deleted 1.2-67 Deleted 1.2-68 Deleted CHAPTER 01 1-ix REV. 16, SEPTEMBER 2012
LGS UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE 1.2-69 Deleted 1.2-70 Deleted 1.2-71 Deleted 1.2-72 Deleted 1.2-73 Deleted 1.2-74 Deleted 1.2-75 Deleted 1.2-76 Deleted 1.2-77 Deleted 1.2-78 Deleted 1.2-79 Deleted 1.2-80 Deleted 1.2-81 Deleted 1.2-82 Deleted 1.2-83 RHR and Core Spray Strainer General Arrangement Plan, Reactor Building Units 1 and 2, Areas 13, 14, 17, and 18, el 181 - 11 1.2-84 Reactor System Heat Balance 1.10-1 Deleted 1.10-2 Logic Symbols 1.13-1 Dose Rate Reduction Factors for ECCS/RHR Piping (0 to 24 hr) 1.13-2 Dose Rate Reduction Factors for ECCS/RHR Piping (24 to 720 hr)
CHAPTER 01 1-x REV. 16, SEPTEMBER 2012