ML22278A282

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Rev. 21 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management
ML22278A282
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 09/19/2022
From:
Constellation Energy Generation
To:
Office of Nuclear Reactor Regulation
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ML22278A223 List: ... further results
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Download: ML22278A282 (8)


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LGS UFSAR CHAPTER 11 - RADIOACTIVE WASTE MANAGEMENT TABLE OF CONTENTS 11.1 SOURCE TERMS 11.1.1 Fission Products 11.1.1.1 Noble Radiogas Fission Products 11.1.1.2 Radiohalogen Fission Products 11.1.1.3 Other Fission Products 11.1.1.4 Nomenclature 11.1.2 Activation Products 11.1.2.1 Coolant Activation Products 11.1.2.2 Noncoolant Activation Products 11.1.3 Tritium 11.1.4 Fuel Fission Production Inventory and Fuel Experience 11.1.4.1 Fuel Fission Product Inventory 11.1.4.2 Fuel Experience 11.1.5 Process Leakage Sources 11.1.6 References 11.2 LIQUID WASTE MANAGEMENT SYSTEM 11.2.1 Design Bases 11.2.2 System Description 11.2.2.1 System Operation 11.2.2.1.1 Equipment Drain Subsystem 11.2.2.1.2 Floor Drain Subsystem 11.2.2.1.3 Chemical Waste Subsystem 11.2.2.1.4 Laundry Drain Subsystem 11.2.2.2 Process Equipment Description 11.2.2.2.1 Pumps 11.2.2.2.2 Tanks 11.2.2.2.3 Filters 11.2.2.2.4 Demineralizers 11.2.2.2.5 Radwaste Evaporators (abandoned) 11.2.2.2.6 Piping 11.2.3 Radioactive Releases CHAPTER 11 11-i REV. 13, SEPTEMBER 2006

LGS UFSAR TABLE OF CONTENTS (cont'd) 11.3 GASEOUS WASTE MANAGEMENT SYSTEMS 11.3.1 Design Bases 11.3.2 System Description 11.3.2.1 Offgas System 11.3.2.1.1 General 11.3.2.1.2 Process Flow Description 11.3.2.1.3 System Design Considerations 11.3.2.1.4 Component Description 11.3.2.2 Other Radioactive Gas Release Paths 11.3.2.2.1 Primary and Secondary Containment 11.3.2.2.2 Radwaste Enclosure 11.3.2.2.3 Turbine Enclosure 11.3.3 Radioactive Releases and Estimated Doses 11.3.4 References 11.4 SOLID WASTE MANAGEMENT SYSTEM 11.4.1 Design Bases 11.4.2 System Description 11.4.2.1 System Operation 11.4.2.1.1 Wet Solid Waste Processing 11.4.2.1.2 Concentrated Liquid Waste Processing 11.4.2.1.3 Dry Solid Waste Inputs 11.4.2.1.4 Irradiated Reactor Internals 11.4.2.2 Process Equipment Description 11.4.2.2.1 Pumps 11.4.2.2.2 Tanks 11.4.2.2.3 Piping 11.4.2.2.4 Centrifuges 11.4.2.2.5 Discharge Chute Assemblies 11.4.2.2.6 Capping Machines 11.4.2.2.7 Solidification and Dewatering Equipment 11.4.2.2.8 Decontamination Station Equipment 11.4.2.2.9 Hydraulic Press (DELETED) 11.4.2.2.10 Handling Equipment 11.4.2.3 Expected Volumes 11.4.2.4 Packaging 11.4.2.4.1 HIC Service 11.4.2.4.2 HIC Material 11.4.2.4.3 HIC Integrity 11.4.2.5 Storage Facilities 11.4.3 References CHAPTER 11 11-ii REV. 13, SEPTEMBER 2006

LGS UFSAR TABLE OF CONTENTS (cont'd) 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING AND SAMPLING SYSTEMS 11.5.1 Design Bases and Specific Requirements 11.5.1.1 General Design Criteria 11.5.1.2 Basis for Detector Location Selection 11.5.1.3 Expected Radiation Levels 11.5.1.4 Quantity to be Measured 11.5.1.5 Detector Type, Sensitivity, and Range 11.5.1.6 Setpoints 11.5.1.7 Annunciators and Alarms 11.5.1.8 Calibration, Maintenance, Inspection, Decontamination, and Replacement 11.5.2 System Description 11.5.2.1 Systems Required for Safety 11.5.2.1.1 Main Steam Line Radiation Monitoring System 11.5.2.1.2 Reactor Enclosure Ventilation Exhaust Radiation Monitoring System 11.5.2.1.3 Refueling Area Ventilation Exhaust Radiation Monitoring System 11.5.2.1.4 Control Room Ventilation Radiation Monitoring System 11.5.2.1.5 Control Room Emergency Fresh Air Radiation Monitoring System 11.5.2.1.6 RHR Service Water Radiation Monitoring System 11.5.2.2 Systems Required for Plant Operation 11.5.2.2.1 North Stack Effluent Radiation Monitoring System 11.5.2.2.2 South Stack Effluent Radiation Monitoring System 11.5.2.2.3 Radwaste Equipment Rooms Ventilation Exhaust Radiation Monitoring System 11.5.2.2.4 Charcoal Treatment System Process Exhaust Radiation Monitoring System 11.5.2.2.5 Recombiner Room and Hydrogen Analyzer Exhaust Radiation Monitoring System 11.5.2.2.6 Steam Exhauster Discharge and Vacuum Pump Exhaust Radiation Monitoring System 11.5.2.2.7 Radwaste Enclosure and Chem. Lab. Expansion Ventilation Exhaust Radiation Monitoring System 11.5.2.2.8 Air Ejector Offgas Effluent Radiation Monitoring System 11.5.2.2.9 Primary Containment Leak Detector Radiation Monitoring System 11.5.2.2.10 Hot Maintenance Shop Ventilation Exhaust Radiation Monitoring System 11.5.2.2.11 Liquid Radwaste Discharge Radiation Monitoring System 11.5.2.2.12 Service Water Radiation Monitoring System 11.5.2.2.13 Reactor Enclosure Cooling Water Radiation Monitoring System 11.5.2.2.14 Process Sampling System 11.5.2.3 Postaccident Systems 11.5.2.3.1 Primary Containment Post-LOCA Radiation Monitoring System 11.5.2.3.2 North Stack Wide Range Accident Monitoring System 11.5.2.3.3 Postaccident Sampling System 11.5.3 Effluent Monitoring and Sampling 11.5.4 Process Monitoring and Sampling CHAPTER 11 11-iii REV. 13, SEPTEMBER 2006

LGS UFSAR TABLE OF CONTENTS (cont'd) 11.5.5 Postaccident Sampling Systems 11.5.5.1 System Description 11.5.5.1.1 Sample Points 11.5.5.1.2 Isolation Valves and Sample Lines 11.5.5.1.3 Piping Rack 11.5.5.1.4 Sample Station and Control Panels 11.5.5.2 Description of Sample Preparation/Chemistry and Nuclear Counting Facilities 11.5.5.2.1 Onsite Facilities 11.5.5.2.2 Arrangements for Offsite Analyses 11.5.5.3 Sample Collection and Transport Procedures 11.5.5.4 Chemical/Radiochemical Procedures 11.5.5.4.1 Sample Preparation 11.5.5.4.2 Chemical Analysis 11.5.5.4.3 Radiochemical Analysis/Gamma Ray Spectroscopy 11.5.5.4.4 Gas Analysis 11.5.5.4.5 Determination of Extent of Core Damage 11.5.5.4.6 Storage and Disposal of Sample 11.5.5.4.7 System Testing and Operator Training 11.5.5.5 Dose Rate Analysis 11.5.6 Radiation and Meteorological Monitoring System 11.5.6.1 General Description 11.5.6.2 RMMS Hardware Description 11.5.6.2.1 Radiation Monitoring and Display System 11.5.6.2.2 Meteorological Monitoring Display and Reporting System 11.5.6.3 RMMS Software Description 11.5.6.3.1 RMDS Software Description 11.5.6.3.2 MMDRS Software Description CHAPTER 11 11-iv REV. 13, SEPTEMBER 2006

LGS UFSAR LIST OF TABLES TABLE TITLE 11.1-1 Noble Radiogas Source Terms 11.1-2 Halogen Radioisotopes in Reactor Water 11.1-3 Other Fission Product Radioisotopes in Reactor Water 11.1-4 Coolant Activation Products in Reactor Water and Steam 11.1-5 Noncoolant Activation Products in Reactor Water 11.2-1 Assumptions and Parameters Used for Evaluation of Radioactivity Releases 11.2-2 Liquid Waste Management System Flows 11.2-3 Expected Radionuclide Activity Concentration in Reactor Coolant and Main Steam Used for Evaluation of Radioactivity Releases 11.2-4 Decontamination Factors Used for Evaluation of Radioactivity Releases 11.2-5 Expected Holdup Times for Collection, Processing, and Discharge Used for Evaluation of Radioactivity Releases 11.2-6 Average Daily Inputs and Activities to the Liquid Waste Management System from Two Units 11.2-7 Batched Inputs to the Liquid Waste Management System from the Solid Waste Management System for Normal Operation of Two Units 11.2-8 Expected Radionuclide Activity Inventories of Liquid Waste Management System Components 11.2-9 Maximum Radionuclide Activity Inventories of Liquid Waste Management System Components 11.2-10 Liquid Waste Management System Component Parameters 11.2-11 Expected Yearly Activity Released from Liquid Waste Management Systems 11.2-12 Comparison of Maximum Calculated Radionuclide Concentrations in the Environment from Routine Liquid Releases to 10CFR20 Limits 11.2-13 Comparison of Maximum Individual Doses Resulting from LGS Units 1 and 2 With 10CFR20, Appendix I Design Objectives CHAPTER 11 11-v REV. 13, SEPTEMBER 2006

LGS UFSAR LIST OF TABLES (cont'd)

TABLE TITLE 11.3-1 Expected Annual Activity Released from Gaseous Waste Management Systems 11.3-2 Assumptions and Parameters Used for Evaluation of Gaseous Releases 11.3-3 Offgas System Major Equipment Description 11.3-4 Comparison of Maximum Individual Doses Resulting from LGS Unit 1 & 2 With 10CFR50, Appendix I Design Objectives 11.3-5 Offgas System Equipment Malfunction Analysis 11.3-6 Release Point Data 11.3-7 Comparison of Maximum Calculated Radionuclide Concentrations in the Environment From Routine Atmospheric Releases to 10CFR20 Limits 11.4-1 Solid Waste Management System Tank Design Parameters 11.4-2 Solid Waste Management System Pump Design Parameters 11.4-3 Solid Waste Management System Process Equipment Design Parameters 11.4-4 Solid Waste Management System Flows 11.4-5 Wet Waste Input to the Solid Waste Management System 11.4-6 Dry Waste from Filters to the Solid Waste Management System 11.4-7 Expected and Maximum Shipping Cask Inventories 11.4-8 Expected Radionuclide Inventories of Solid Waste Management System Components 11.4-9 Maximum Radionuclide Inventories of Solid Waste Management System Components 11.4-10 Expected Annual Solid Waste Management System Containers to be Shipped and Activity Contents 11.5-1 Process and Effluent Radiation Monitoring Systems 11.5-2 Radiation Monitoring System Setpoints and Functions 11.5-3 Postaccident Sampling Dose Assessment 11.5-4 Gaseous Effluents Composition and Concentrations CHAPTER 11 11-vi REV. 13, SEPTEMBER 2006

LGS UFSAR LIST OF TABLES (cont'd)

TABLE TITLE 11.5-5 Liquid Effluents Composition and Concentrations CHAPTER 11 11-vii REV. 13, SEPTEMBER 2006

LGS UFSAR LIST OF FIGURES FIGURE TITLE 11.1-1 Noble Radiogas Decay Constant Exponent Frequency Histogram 11.1-2 Radiohalogen Decay Constant Exponent Frequency Histogram 11.1-3 Noble Radiogas Leakage Versus I-131 Leakage 11.2-1 Deleted 11.2-2 Deleted 11.2-3 Deleted 11.2-4 Liquid Waste Management Process Flow Diagram 11.3-1 Gaseous Waste System Process Diagram 11.3-2 Deleted 11.3-3 Deleted 11.4-1 Deleted 11.4-2 Deleted 11.4-3 Solid Waste Management System Process Flow Diagram 11.5-1 Deleted 11.5-2 Deleted CHAPTER 11 11-viii REV. 13, SEPTEMBER 2006