ML21133A064
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LGS UFSAR CHAPTER 4 - REACTOR TABLE OF CONTENTS
4.0 INTRODUCTION
4.1
SUMMARY
DESCRIPTION 4.1.1 Reactor Vessel 4.1.2 Reactor Internal Components 4.1.2.1 Reactor Core 4.1.2.1.1 General 4.1.2.1.2 Core Configuration 4.1.2.1.3 Fuel Assembly Description 4.1.2.1.4 Fuel Assembly Support and Control Rod Location 4.1.2.2 Shroud 4.1.2.3 Shroud Head and Steam Separator Assembly 4.1.2.4 Steam Dryer Assembly 4.1.3 Reactivity Control Systems 4.1.3.1 Operation 4.1.3.2 Description of Control Rods 4.1.3.3 Supplementary Reactivity Control 4.1.4 Analysis Techniques 4.1.4.1 Reactor Internal Components 4.1.4.1.1 MASS (Mechanical Analysis of Space Structure) 4.1.4.1.2 SNAP (MULTISHELL) 4.1.4.1.3 GASP 4.1.4.1.4 NOHEAT 4.1.4.1.5 FINITE 4.1.4.1.6 DYSEA 4.1.4.1.7 SHELL 5 4.1.4.1.8 HEATER 4.1.4.1.9 FAP-71 (Fatigue Analysis Program) 4.1.4.1.10 CREEP/PLAST 4.1.4.1.11 ANSYS 4.1.4.2 Fuel Rod Thermal Analysis 4.1.4.3 Reactor Systems Dynamics 4.1.4.4 Nuclear Engineering Analysis 4.1.4.5 Neutron Fluence Calculations 4.1.4.6 Thermal-Hydraulic Calculations 4.1.5 References 4.2 FUEL SYSTEM DESIGN 4.2.1 Design Bases CHAPTER 04 4-i REV. 16, SEPTEMBER 2012
LGS UFSAR TABLE OF CONTENTS (cont'd) 4.2.2 Description and Design Drawings 4.2.2.1 Reactivity Control Assembly (Control Rods) 4.2.2.2 Reactivity Control Assembly Evaluation 4.2.3 Design Evaluation 4.2.3.1 Exceptions to GESTAR II 4.2.4 Testing, Inspection, and Surveillance Plans 4.2.5 References 4.3 NUCLEAR DESIGN 4.3.1 Design Bases 4.3.2 Description 4.3.2.1 Nuclear Design Description 4.3.2.2 Power Distribution 4.3.2.3 Reactivity Coefficient 4.3.2.4 Control Requirements 4.3.2.4.1 Shutdown Reactivity 4.3.2.4.1 Reactivity Variations 4.3.2.5 Control Rod Patterns and Reactivity Worths 4.3.2.5.1 Scram Reactivity 4.3.2.6 Criticality of Reactor During Refueling 4.3.2.7 Stability 4.3.2.7.1 Xenon Transients 4.3.2.7.2 Thermal-Hydraulic Stability 4.3.2.8 Vessel Irradiations 4.3.3 Analytical Methods 4.3.4 Changes 4.3.5 References 4.4 THERMAL AND HYDRAULIC DESIGN 4.4.1 Design Basis 4.4.2 Description of Thermal-Hydraulic Design of the Reactor Core 4.4.2.1 Summary Comparison 4.4.2.2 Critical Power Ratio 4.4.2.3 Linear Heat Generation Rate 4.4.2.4 Void Fraction Distribution 4.4.2.5 Core Coolant Flow Distribution and Orificing Pattern 4.4.2.6 Core Pressure Drop and Hydraulic Loads 4.4.2.7 Correlation and Physical Data 4.4.2.8 Thermal Effects of Operational Transients CHAPTER 04 4-ii REV. 16, SEPTEMBER 2012
LGS UFSAR TABLE OF CONTENTS (cont'd) 4.4.2.9 Uncertainties in Estimates 4.4.2.10 Flux Tilt Considerations 4.4.3 Description of the Thermal and Hydraulic Design of the Reactor Coolant System 4.4.3.1 Plant Configuration Data 4.4.3.1.1 Reactor Coolant System Configuration 4.4.3.1.2 Reactor Coolant System Thermal-Hydraulic Data 4.4.3.1.3 Reactor Coolant System Geometric Data 4.4.3.2 Operating Restrictions on Pumps 4.4.3.3 Power-Flow Operating Map 4.4.3.3.1 Limits for Normal Operation 4.4.3.3.2 Regions of the Power-Flow Map 4.4.3.4 Temperature-Power Operating Map (PWR) 4.4.3.5 Load-Following Characteristics 4.4.3.6 Thermal and Hydraulic Characteristics Summary Table 4.4.4 Evaluation 4.4.5 Testing and Verification 4.4.6 Instrumentation Requirements 4.4.6.1 Deleted 4.5 REACTOR MATERIALS 4.5.1 Control Rod System Structural Materials 4.5.1.1 Material Specifications 4.5.1.1.1 Material List 4.5.1.1.2 Special Materials 4.5.1.2 Austenitic Stainless Steel Components: Processes, Inspections, and Tests 4.5.1.3 Other Materials 4.5.1.4 Cleaning and Cleanliness Control 4.5.1.4.1 Protection of Materials During Fabrication, Shipping, and Storage 4.5.2 Reactor Internal Materials 4.5.2.1 Material Specifications 4.5.2.2 Controls on Welding 4.5.2.3 Nondestructive Examination of Wrought Seamless Tubular Products 4.5.2.4 Regulatory Guide Conformance for Fabrication and Processing of Austenitic Stainless Steel 4.5.2.5 Other Materials 4.5.3 Control Rod Drive Housing Supports 4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS 4.6.1 Control Rod Drive System 4.6.1.1 Design CHAPTER 04 4-iii REV. 16, SEPTEMBER 2012
LGS UFSAR TABLE OF CONTENTS (cont'd) 4.6.1.1.1 Safety Design Bases 4.6.1.1.2 Power Generation Design Basis 4.6.1.2 Description 4.6.1.2.1 Control Rod Drive Mechanisms 4.6.1.2.2 Drive Components 4.6.1.2.3 Materials of Construction 4.6.1.2.4 Control Rod Drive Hydraulic System 4.6.1.2.5 Control Rod Drive System Operation 4.6.1.2.6 Instrumentation 4.6.1.3 Control Rod Drive Housing Supports 4.6.1.3.1 Safety Objective 4.6.1.3.2 Safety Design Bases 4.6.1.3.3 Description 4.6.2 Evaluations of the CRD System 4.6.2.1 Failure Mode and Effects Analysis 4.6.2.2 Protection from Common Mode Failures 4.6.2.3 Safety Evaluation 4.6.2.3.1 Control Rods 4.6.2.3.2 Control Rod Drives 4.6.2.3.3 Control Rod Drive Housing Supports 4.6.2.3.4 Loss of Scram Discharge Valve Air Pressure 4.6.3 Testing and Verification of the Control Rod Drives 4.6.3.1 Control Rod Drives 4.6.3.1.1 Testing and Inspection 4.6.3.2 Control Rod Drive Housing Supports 4.6.3.2.1 Testing and Inspection 4.6.4 Information for Combined Performance of Reactivity Systems 4.6.4.1 Vulnerability to Common Mode Failures 4.6.4.2 Accidents Taking Credit for Multiple Reactivity Systems 4.6.5 Evaluation of Combined Performance 4.6.6 References CHAPTER 04 4-iv REV. 16, SEPTEMBER 2012
LGS UFSAR CHAPTER 4 - REACTOR LIST OF TABLES TABLE TITLE 4.3-1 Calculated Neutron Fluxes (Used to Evaluate Vessel Irradiation) 4.3-2 Calculated Neutron Flux at Core Equivalent Boundary 4.3-3 Calculated Initial Core Effective Multiplication and Control System Worth - No Voids, 20oC 4.4-1 Thermal and Hydraulic Design Characteristics of the Reactor Core 4.4-2 Reactor Coolant System Geometric Data 4.4-3 Axial Void Fraction Distribution 4.4-4 Axial Flow Quality Distribution 4.4.5 Axial Power Distribution Used to Generate Void and Quality Distributions 4.4-6 Deleted 4.4-7 Safety Injection Line Lengths 4.4-8 Stability Analysis Results (Cycle-1 Most Limiting Conditions) 4.6-1 Identification of Scram Discharge System Components CHAPTER 04 4-v REV. 16, SEPTEMBER 2012
LGS UFSAR CHAPTER 4 - REACTOR LIST OF FIGURES FIGURE TITLE 4.3-1 Model for One-Dimensional Transport Analysis of Vessel Fluence 4.3-2 Radial Power Distributions Used in the Vessel Fluence Calculation 4.3-3 Reference Loading Pattern 4.4-1 Power-Flow Operating Map 4.4-2 Total Core Stability 4.4-3 10 psi Pressure Regulator Setpoint Step at 51.5% Rated Power (Natural Circulation) 4.4-4 10 Cent Rod Reactivity Step at 51.5% Rated Power (Natural Circulation) 4.4-5 6 Inch Water Level Setpoint Step at 51.5% Rated Power (Natural Circulation) 4.4-6 6 Inch Water Level Setpoint Step at 68% Rated Power and 51.5% Rated Flow 4.4-7 Deleted 4.6-1 Control Rod to Control Rod Drive Coupling 4.6-2 Control Rod Drive Unit 4.6-3 Control Rod Drive Schematic BWR/4&5 4.6-4 Control Rod Drive 4.6-5 Deleted 4.6-6 Deleted 4.6-7 Deleted 4.6-8 Control Rod Drive Hydraulic Control Unit 4.6-9 Control Rod Drive Housing Support CHAPTER 04 4-vi REV. 16, SEPTEMBER 2012