ML21286A328

Amendment 29 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System, Table of Contents

ML21286A328
Person / Time
Site:	Browns Ferry
Issue date:	10/04/2021
From:	Tennessee Valley Authority
To:	Office of Nuclear Reactor Regulation
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BFN-29 4.0-i REACTOR COOLANT SYSTEM TABLE OF CONTENTS 4.0 Reactor Coolant System............................................................................................................ 4.1-1 4.1 Summary Description................................................................................................................ 4.1-1 4.2 Reactor Vessel And Appurtenances Mechanical Design........................................................... 4.2-1 4.2.1 Power Generation Objective...................................................................................... 4.2-1 4.2.2 Power Generation Design Basis................................................................................ 4.2-1 4.2.3 Safety Design Basis................................................................................................... 4.2-1 4.2.4 Description................................................................................................................. 4.2-2 4.2.5 Safety Evaluation....................................................................................................... 4.2-10 4.2.6 Inspection and Testing............................................................................................... 4.2-15 4.3 Reactor Recirculation System................................................................................................... 4.3-1 4.3.1 Power Generation Objective...................................................................................... 4.3-1 4.3.2 Power Generation Design Basis................................................................................ 4.3-1 4.3.3 Safety Design Basis................................................................................................... 4.3-1 4.3.4 Description................................................................................................................. 4.3-1 4.3.5 Safety Evaluation....................................................................................................... 4.3-7 4.3.6 Inspection and Testing............................................................................................... 4.3-8 4.4 Nuclear System Pressure Relief System................................................................................... 4.4-1 4.4.1 Safety Objective......................................................................................................... 4.4-1 4.4.2 Power Generation Objective...................................................................................... 4.4-1 4.4.3 Safety Design Basis................................................................................................... 4.4-1 4.4.4 Power Generation Design Basis................................................................................ 4.4-2 4.4.5 Description................................................................................................................. 4.4-2 4.4.6 Safety Evaluation....................................................................................................... 4.4-9 4.4.7 Inspection and Testing............................................................................................... 4.4-10 4.5 Main Steam Line Flow Restrictor............................................................................................... 4.5-1 4.5.1 Safety Objective......................................................................................................... 4.5-1 4.5.2 Safety Design Basis................................................................................................... 4.5-1 4.5.3 Description................................................................................................................. 4.5-1 4.5.4 Safety Evaluation....................................................................................................... 4.5-2 4.5.5 Inspection and Testing............................................................................................... 4.5-3 4.6 Main Steam Isolation Valves..................................................................................................... 4.6-1 4.6.1 Safety Objectives....................................................................................................... 4.6-1 4.6.2 Safety Design Basis................................................................................................... 4.6-1 4.6.3 Description................................................................................................................. 4.6-2 4.6.4 Safety Evaluation....................................................................................................... 4.6-5 4.6.5 Inspection and Testing............................................................................................... 4.6-8

BFN-29 4.0-ii REACTOR COOLANT SYSTEM TABLE OF CONTENTS (Cont'd) 4.7 Reactor Core Isolation Cooling System..................................................................................... 4.7-1 4.7.1 Power Generation Objective...................................................................................... 4.7-1 4.7.2

[Deleted]..................................................................................................................... 4.7-1 4.7.3 Power Generation Design Basis................................................................................ 4.7-1 4.7.4 Safety Design Basis................................................................................................... 4.7-1 4.7.5 Description................................................................................................................. 4.7-1 4.7.6 Safety Evaluation....................................................................................................... 4.7-4 4.7.7 Inspection and Testing............................................................................................... 4.7-4 4.8 Residual Heat Removal System (RHRS).................................................................................. 4.8-1 4.8.1 Safety Objective......................................................................................................... 4.8-1 4.8.2 Power Generation Objective...................................................................................... 4.8-1 4.8.3 Safety Design Basis................................................................................................... 4.8-1 4.8.4 Power Generation Design Basis................................................................................ 4.8-2 4.8.5 Summary Description................................................................................................. 4.8-2 4.8.6 Description................................................................................................................. 4.8-4 4.8.7 Safety Evaluation....................................................................................................... 4.8-8 4.8.8 Inspection and Testing............................................................................................... 4.8-8 4.9 Reactor Water Cleanup System................................................................................................ 4.9-1 4.9.1 Power Generation Objective...................................................................................... 4.9-1 4.9.2 Power Generation Design Basis................................................................................ 4.9-1 4.9.3 Description (Figures 4.9-1, 4.9-2, 4.9-3, 4.9-5, 4.9-6, 4.9-7, 4.9-8, 4.9-9, and 4.9-10)................................................................................................ 4.9-1 4.9.4 Inspection and Testing............................................................................................... 4.9-3 4.10 Nuclear System Leakage Rate Limits....................................................................................... 4.10-1 4.10.1 Safety Objective......................................................................................................... 4.10-1 4.10.2 Safety Design Basis................................................................................................... 4.10-1 4.10.3 Description................................................................................................................. 4.10-1 4.10.4 Safety Evaluation....................................................................................................... 4.10-7 4.10.5 Inspection and Testing............................................................................................... 4.10-7 4.11 Main Steam Lines, Feedwater Piping, and Drains..................................................................... 4.11-1 4.11.1 Power Generation Objective...................................................................................... 4.11-1 4.11.2 Safety Design Basis................................................................................................... 4.11-1 4.11.3 Power Generation Design Bases............................................................................... 4.11-1 4.11.4 Description................................................................................................................. 4.11-1 4.11.5 Safety Evaluation....................................................................................................... 4.11-3 4.11.6 Inspection and Testing............................................................................................... 4.11-3

BFN-29 4.0-iii REACTOR COOLANT SYSTEM TABLE OF CONTENTS (Cont'd) 4.12 Inservice Inspection And Testing............................................................................................... 4.12-1 4.12.1 Introduction................................................................................................................ 4.12-1 4.12.2 Scope......................................................................................................................... 4.12-2 4.12.3 Responsibility............................................................................................................. 4.12-2 4.12.4 Area and Extent of Examination................................................................................. 4.12-2

BFN-29 4.0-iv REACTOR COOLANT SYSTEM LIST OF TABLES Table Title 4.2-1 Reactor Pressure Vessel Materials 4.2-2 Reactor Vessel Data 4.2-3 Reactor Vessel Attachments 4.3-1 Reactor Recirculation System Design Characteristics (3952 MWt) 4.3-1b (Deleted) 4.4-1 (Deleted) 4.4-1A Nuclear System Main Steam Relief Valves (Units 2 and 3) 4.7-1 Reactor Core Isolation Cooling System Turbine - Pump Design Data 4.8-1 Residual Heat Removal System Equipment Design Data 4.9-1 Reactor Water Cleanup System Equipment Design Data

BFN-29 4.0-v REACTOR COOLANT SYSTEM LIST OF ILLUSTRATIONS Figure Title 4.2-1 Reactor Vessel 4.2-2 Reactor Vessel Nozzles and Penetrations 4.2-3 Reactor Vessel 4.2-4 Reactor Vessel 4.3-1 Recirculation System--Elevation, Isometric 4.3-2a sht 1 Nuclear Boiler Flow Diagram 4.3-2a sht 2 Nuclear Boiler Flow Diagram 4.3-2a sht 3 Nuclear Boiler Flow Diagram 4.3-2b (Deleted) 4.3-3 Jet Pump--Operating Principle 4.3-4 Recirculation System--Core Flooding Capability 4.4-1 2-Stage Safety/Relief Valve Schematic (Closed Position) 4.4-2 2-Stage Safety/Relief Valve Schematic (Open Position) 4.4-3 Safety Valve Sizing Analysis 4.4-4 Deleted by Amendment 13 4.4-5 Deleted by Amendment 13 4.4-6 T-Quencher for Safety/Relief Discharge 4.4-7 Mechanical Main Steam Relief Valve Vent Piping 4.4-8 Mechanical Main Steam Relief Valve Vent Piping 4.5-1 Primary Steam Piping 4.5-2 Primary Steam Piping 4.5-3 Primary Steam Piping 4.6-1 Main Steam Isolation Valve 4.7-1a Reactor Core Isolation Cooling System Flow Diagram 4.7-1b Reactor Core Isolation Cooling System, Mechanical Control Diagram 4.7-1c Reactor Core Isolation Cooling System - Flow Diagram 4.7-1d Reactor Core Isolation Cooling System - Mechanical Control Diagram 4.7-1e Reactor Core Isolation Cooling System - Mechanical Control Diagram 4.7-1f Reactor Core Isolation Cooling System - Flow Diagram 4.7-2a (Deleted) 4.7-2b (Deleted) 4.7-2c (Deleted) 4.7-2d (Deleted) 4.7-2e (Deleted) 4.7-2f (Deleted) 4.7-2g (Deleted) 4.7-2h (Deleted) 4.8-1 Residual Heat Removal System, Unit Cross Connections and Standby Coolant Supply 4.9-1 Reactor Water Cleanup System Flow Diagram 4.9-2 Reactor Water Cleanup Demineralizer Flow Diagram 4.9-3 Reactor Water Cleanup System, Mechanical Control Diagram 4.9-4 (Deleted)

BFN-29 4.0-vi REACTOR COOLANT SYSTEM LIST OF ILLUSTRATIONS (contd)

Figure Title 4.9-4a (Deleted) 4.9-4b (Deleted) 4.9-4c (Deleted) 4.9-4d (Deleted) 4.9-5 Reactor Water Cleanup System - Flow Diagram 4.9-6 Reactor Water Cleanup Demineralizer - Flow Diagram 4.9-7 Reactor Water Cleanup System - Mechanical Control Diagram 4.9-8 Reactor Water Cleanup System - Flow Diagram 4.9-9 Reactor Water Cleanup Demineralizer - Flow Diagram 4.9-10 Reactor Water Cleanup System - Mechanical Control Diagram 4.10-1 Drywell Leak Detection System Diagram 4.10-2 Deleted 4.10-3 Axial Through-Wall Crack Data Correlation 4.11-1 Feedwater Piping Arrangement