ML20339A069
Text
GINNA/UFSAR 4 REACTOR 1 4.1
SUMMARY
DESCRIPTION 2 4.1.1 REACTOR CORE 2 4.1.2 WESTINGHOUSE OPTIMIZED FUEL ASSEMBLIES/422 VAN- 2 TAGE + FUEL ASSEMBLIES 4.1.3 RECONSTITUTED FUEL ASSEMBLIES 4 4.1.4 STARTUP REPORT 5
4.1 REFERENCES
FOR SECTION 4.1 6 4.2 FUEL SYSTEM DESIGN 7 4.2.1 DESIGN BASES 7 4.2.1.1 Performance Objectives 7 4.2.1.2 Principal Design Criteria 7 4.2.1.2.1 Reactor Core Design 7 4.2.1.2.2 Suppression of Power Oscillations 9 4.2.1.2.3 Redundancy of Reactivity Control 9 4.2.1.2.4 Reactivity MODE 3 (Hot Shutdown) Capability 9 4.2.1.2.5 Reactivity Shutdown Capability 10 4.2.1.2.6 Reactivity Holddown Capability 10 4.2.1.2.7 Reactivity Control Systems Malfunction 11 4.2.1.2.8 Maximum Reactivity Worth of Control Rods 12 4.2.1.2.9 Conformance With 1972 General Design Criteria 12 4.2.1.3 Safety Limits 13 4.2.1.3.1 Nuclear Limits 13 4.2.1.3.2 Reactivity Control Limits 13 4.2.1.3.3 Thermal and Hydraulic Limits 13 4.2.1.3.4 Mechanical Limits 14 4.2.1.3.4.1 Reactor Internals 14 4.2.1.3.4.2 Fuel Assemblies 15 4.2.1.3.4.3 Control Rods 16 4.2.1.3.4.4 Control Rod Drive Assembly 16 4.2.2 FUEL SYSTEM DESIGN DESCRIPTION 16 Page 1 of 5 Revision 29 11/2020
GINNA/UFSAR 4.2.3 CORE COMPONENTS DESIGN DESCRIPTION 17 4.2.3.1 Fuel Assembly 17 4.2.3.1.1 Top Nozzle, Springs, and Clamps 18 4.2.3.1.2 Bottom Nozzle 18 4.2.3.1.3 Guide Thimbles 19 4.2.3.1.4 Instrumentation Tube 19 4.2.3.1.5 Grid Assemblies 19 4.2.3.1.6 Fuel Rods 20 4.2.3.1.7 Fuel Assembly Joints and Connections 20 4.2.3.1.8 Fuel Assembly Identification 21 4.2.3.2 Control Rods 21 4.2.3.3 Neutron Source Assemblies 22 4.2.3.4 Plugging Devices 22 4.2.3.5 Fuel Pellet and Cladding Design Considerations 23 4.2.3.6 Reload Fuel Design 23 4.2.3.6.1 Reload Fuel Design - Westinghouse Optimized Fuel 23 4.2.3.6.2 Reload Fuel Design - Westinghouse OFA/VANTAGE + Fuel 24 4.2.3.6.3 Reload Fuel Design - Westinghouse 422V+ Fuel 24 4.2.3.7 Fuel Assembly and Rod Cluster Control Assembly Tests 24 4.2.3.7.1 Reactor Evaluation Center Tests 24 4.2.3.7.2 Loading and Handling Tests 24 4.2.3.7.3 Axial and Lateral Bending Tests 24 4.2.4 DESIGN EVALUATION 25 4.2.4.1 Fuel and Cladding Evaluation - Original Core 25 4.2.4.2 Design Evaluation - Reload Optimized Fuel Assembly, OFA/VAN- 25 TAGE+ Fuel Assembly, and 422 VANTAGE+ Fuel Assembly Designs 4.2.4.2.1 Introduction 25 4.2.4.2.2 Fuel Design 26 4.2.4.2.3 Design for Seismic and Loss-of-Coolant Accident Forces 26 4.2.4.2.4 Emergency Core Cooling System (ECCS) Calculation Loss-of-Coolant 26 Accident Cladding Models 4.2.4.2.5 Initial Fuel Conditions for Transient Analysis 26 Page 2 of 5 Revision 29 11/2020
GINNA/UFSAR 4.2.4.2.6 Predicted Clad Collapse Time 26 4.2.4.2.7 Nuclear Design 27 4.2.4.2.8 Fuel Assembly Hydraulic Lift-Off 27 4.2.4.2.9 Thermal-Hydraulic Analysis 28 4.2.4.2.9.1 Sensitivity Factors 28 4.2.4.2.9.2 WRB-1 Correlation 28 4.2.4.2.9.3 Rod Bow Penalties 28 4.2.4.2.9.4 DNBR Design Limits 29 4.2.4.3 Design Evaluation of Reconstituted Fuel Assemblies 30 4.2.5 CORE COMPONENTS TESTS AND INSPECTIONS 30
4.2 REFERENCES
FOR SECTION 4.2 31 Table 4.2-1 NUCLEAR DESIGN DATA 33 Table 4.2-2 CORE MECHANICAL DESIGN PARAMETERS 35 Table 4.2-3 FUEL DESIGN 38 Table 4.2-4 KINETIC PARAMETERS USED IN TRANSIENT ANALYSIS 39 (WESTINGHOUSE OFA/VANTAGE+ AND 422V+ GINNA FUEL ASSEMBLY 14 x 14 FUEL) 4.3 RELOAD CORE NUCLEAR DESIGN 40 4.3.1 PRELIMINARY DESIGN PHASE 40 4.3.2 DETERMINATION OF NUCLEAR-RELATED KEY SAFETY 41 PARAMETERS 4.3.2.1 Reactivity Control Aspects 41 4.3.2.1.1 Insertion Limits 42 4.3.2.1.2 Total Rod Worth 43 4.3.2.1.3 Trip Reactivity 43 4.3.2.1.4 Differential Rod Worths 43 4.3.2.1.5 Summary 44 4.3.2.2 Core Reactivity Parameters and Coefficients 44 4.3.2.2.1 Moderator Temperature Coefficient 44 4.3.2.2.2 Fuel Temperature Coefficient 45 4.3.2.2.3 Boron Worth 45 4.3.2.2.4 Delayed Neutrons 45 4.3.2.2.5 Prompt Neutron Lifetime 45 4.3.2.2.6 Summary 46 Page 3 of 5 Revision 29 11/2020
GINNA/UFSAR 4.3.2.3 Reactor Core Power Distribution 46 4.3.3 EVALUATION OF RELOADS WITH OFA/VANTAGE+ AND 422V+ 46 FUEL ASSEMBLIES 4.3.4 TESTS FOR REACTIVITY ANOMALIES 47
4.3 REFERENCES
FOR SECTION 4.3 48 4.4 THERMAL AND HYDRAULIC DESIGN 49 4.4.1 DESIGN BASIS 49 4.
4.2 DESCRIPTION
AND EVALUATION OF THE THERMAL-HYDRAU- 49 LIC DESIGN AND ANALYSIS OF RELOAD CORES 4.4.2.1 Hydraulic Evaluation 49 4.4.2.2 Thermal and Hydraulic Key Safety Parameters 49 4.4.2.2.1 Engineering Hot-Channel Factors 50 4.4.2.2.2 Axial Fuel Stack Shrinkage 50 4.4.2.2.3 Fuel Temperatures 50 4.4.2.2.4 Rod Internal Pressure 50 4.4.2.2.5 Core Thermal Limits 51 4.4.2.2.6 Key Safety Parameters for Specific Events 52 4.4.2.3 VIPRE Code 52 4.4.2.3.1 Steady-State Analysis 53 4.4.2.3.2 Transient Analysis 53 4.4.3 THERMAL-HYDRAULIC METHODOLOGY FOR OFA/VANTAGE+ 53 and 422V+ FUEL ASSEMBLY DESIGN EVALUATION 4.4.3.1 General 53 4.4.3.2 Rod Bow 55 4.4.4 THERMAL AND HYDRAULIC TESTS AND INSPECTIONS 55 4.4.5 REACTOR COOLANT FLOW MEASUREMENT 55 4.4.5.1 Pump Power 56 4.4.5.2 Secondary Heat Balance 56 4.4.5.3 Elbow Tap Differential Pressure 56 4.4.5.4 Core Exit Thermocouple 56 4.4.5.5 Pump Power-Differential Pressure 57 4.4.5.6 Experience 58 4.4.5.7 Low Flow Trip Setpoint 59 4.4.5.8 Precision Calorimetric Measurement for Reactor Coolant System Flow 59
4.4 REFERENCES
FOR SECTION 4.4 63 Table 4.4-1 THERMAL AND HYDRAULIC DESIGN PARAMETERS 65 Page 4 of 5 Revision 29 11/2020
GINNA/UFSAR 4.5 REACTOR MATERIALS 67 4.5.1 CONTROL ROD DRIVE SYSTEM STRUCTURAL MATERIALS 67 4.5.2 REACTOR INTERNALS MATERIALS 67 4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEM 68 FIGURES Figure 4.2-1 Typical Rod Cluster Control Assembly Figure 4.2-2 Fuel Assembly and Control Cluster Cross Section Figure 4.2-3 14 x 14 OFA and 422V+ Fuel Assemblies Figure 4.2-4 OFA and 422V+ Top Nozzle Assemblies Figure 4.2-5 Debris Filter Bottom Nozzle Figure 4.2-6 Optimized Guide Thimble Assembly Figure 4.2-7 Optimized Instrumentation Tube Figure 4.2-8 Mid-Grid Connection Figure 4.2-9 Removable Top Nozzle and Top Grid Connection Figure 4.3-1 Control Rod Cluster Groups Figure 4.4-1 Typical Pump Power Versus Flow Curves Page 5 of 5 Revision 29 11/2020