ML21257A302

2 to Updated Final Safety Analysis Report, Chapter 3, Reactor, Table of Contents

ML21257A302
Person / Time
Site:	Calvert Cliffs
Issue date:	09/07/2021
From:	Exelon Generation Co
To:	Office of Nuclear Reactor Regulation
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References
NEI 99-04
Download: ML21257A302 (9)

Text

CHAPTER 3 REACTOR TABLE OF CONTENTS PAGE 3.0 REACTOR 3.1-1 3.1 GENERAL DESIGN

SUMMARY

3.1-1 3.2 DESIGN BASIS 3.2-1 3.2.1 PERFORMANCE OBJECTIVES 3.2-1 3.2.2 DESIGN OBJECTIVES 3.2-1 3.2.3 DESIGN LIMITS 3.2-1 3.2.3.1 Nuclear Design Limits 3.2-1 3.2.3.2 Reactivity Control Design Limits 3.2-2 3.2.3.3 Thermal and Hydraulic Design Limits 3.2-2 3.2.3.4 Mechanical Design Limits 3.2-2 3.2.3.5 Fuel Assembly Design Limits 3.2-3 3.2.3.6 Control Element Assembly Design Limits 3.2-4 3.

2.4 REFERENCES

3.2.5 3.3 MECHANICAL DESIGN 3.3-1 3.3.1

SUMMARY

3.3-1 3.3.2 CORE MECHANICAL DESIGN 3.3-1 3.3.2.1 Fuel Rod Mechanical Design 3.3-1 3.3.2.2 Burnable Poison Rod Mechanical Design 3.3-2 3.3.2.3 Fuel Assembly Mechanical Design 3.3-3 3.3.2.4 Control Element Assembly Mechanical Design 3.3-7 3.3.2.5 Neutron Source Design 3.3-9 3.3.2.6 Guide Tube Flux Suppressor Design 3.3-9 3.3.2.7 Test Capsule Assembly Design 3.3-9 3.3.2.8 ZIRLO Cladding (Westinghouse Fuel) 3.3-10 3.3.2.9 M5 Cladding (AREVA/Framatome Fuel) 3.3-11 3.3.2.10 Axial Blankets 3.3-11 3.3.2.11 Radial Enrichment Zoning 3.3-11 3.3.2.12 Armoring 3.3-11 3.3.3 REACTOR INTERNAL STRUCTURES 3.3-11 3.3.3.1 Core Support Assembly 3.3-12 3.3.3.2 Core Support Barrel 3.3-12 3.3.3.3 Core Support Plate and Support Column 3.3-13 3.3.3.4 Core Shroud 3.3-13 3.3.3.5 Flow Skirt 3.3-13 3.3.3.6 Upper Guide Structure Assembly 3.3-14 3.3.4 CONTROL ELEMENT DRIVE MECHANISM 3.3-15 3.3.4.1 Design 3.3-15 3.

3.5 REFERENCES

3.3-16 3.4 NUCLEAR DESIGN AND EVALUATION 3.4-1

CALVERT CLIFFS UFSAR 3-i Rev. 52 CHAPTER 3 REACTOR TABLE OF CONTENTS PAGE 3.4.1

SUMMARY

3.4-1 3.4.2 REACTIVITY AND CONTROL REQUIREMENTS 3.4-1 3.4.2.1 Fuel Temperature Coefficient 3.4-2 3.4.2.2 Moderator Temperature Coefficient 3.4-2 3.4.2.3 Moderator Pressure Coefficient 3.4-3 3.4.2.4 Moderator Void Coefficient 3.4-3 3.4.2.5 Power Coefficient 3.4-3 3.4.3 SHUTDOWN REACTIVITY CONTROL 3.4-4 3.4.3.1 Shutdown Reactivity Margin 3.4-4 3.4.3.2 Power Defect 3.4-5 3.4.3.3 Control Element Assembly Bite and Power Dependent 3.4-5 Insertion Limits 3.4.3.4 Shutdown Conditions 3.4-6 3.4.4 CONTROL ELEMENT ASSEMBLY PATTERN, OPERATIONS, 3.4-6 AND WORTHS 3.4.5 REACTIVITY INSERTION RATES 3.4-7 3.4.6 POWER DISTRIBUTION 3.4-7 3.4.6.1 General 3.4-7 3.4.6.2 Objective 3.4-7 3.4.6.3 Fuel Management and Operations 3.4-7 3.4.6.4 Power Peaking Limits 3.4-8 3.4.6.5 Power Distribution Monitoring Capability 3.4-8 3.4.7 REACTOR STABILITY 3.4-8 3.4.7.1 General 3.4-8 3.4.7.2 Method of Analysis 3.4-9 3.4.7.3 Radial Stability 3.4-9 3.4.7.4 Azimuthal Stability 3.4-10 3.4.7.5 Axial Stability 3.4-10 3.4.7.6 Detection and Control of Oscillations 3.4-10 3.4.8 NEUTRON FLUX AT PRESSURE VESSEL 3.4-10 3.4.9 ANALYTICAL METHODS 3.4-11 3.4.9.1 General 3.4-11 3.4.9.2 Coarse-Mesh Diffusion Calculations - Westinghouse 3.4-12 only 3.4.9.3 Power Distribution Monitoring 3.4-12 3.4.10 REFERENCES 3.4-13 3.5 THERMAL AND HYDRAULIC DESIGN AND EVALUATION 3.5-1 3.5.1 GENERAL 3.5-1 3.5.1.1 Cycle Summaries 3.5-1

CALVERT CLIFFS UFSAR 3-ii Rev. 52 CHAPTER 3 REACTOR TABLE OF CONTENTS PAGE 3.5.2 THERMAL AND HYDRAULIC DESIGN BASES 3.5-12 3.5.2.1 Minimum Departure from Nucleate Boiling Ratio 3.5-12 3.5.2.2 Fuel Design Basis 3.5-12 3.5.2.3 Hydraulic Stability 3.5-13 3.5.3 STATISTICAL COMBINATION OF UNCERTAINTIES 3.5-13 3.5.4 REACTOR HYDRAULICS 3.5-13 3.5.4.1 Coolant Flow 3.5-13 3.5.4.2 Pressure Losses 3.5-14 3.5.4.3 Partial Flow Operation 3.5-14 3.5.5 MAXIMUM CORE TEMPERATURE 3.5-14 3.5.6 DEPARTURE FROM NUCLEATE BOILING 3.5-15 3.5.6.1 Design Approach to Departure from Nucleate Boiling 3.5-15 3.5.6.2 Evaluation of Margin to DNB 3.5-15 3.5.7 VAPOR FRACTION 3.5-15 3.5.8 THERMAL AND HYDRAULIC EVALUATION 3.5-16 3.5.8.1 Statistical Analysis of Hot Channel Factors 3.5-16 3.5.8.2 Fuel Temperature Conditions 3.5-16 3.5.8.3 Flow Stability 3.5-16 3.5.8.4 AREVA/Framatome Fuel Assemblies 3.5-16 3.

5.9 REFERENCES

3.5-17 3.6 ORIGINAL FUEL DESIGN EVALUATION 3.6-1 3.6.1 FUEL DESIGN AND ANALYSIS 3.6-1 3.6.2 ANALYSIS OF BURNUP AND LINEAR HEAT RATINGS 3.6-2 3.6.3

SUMMARY

OF PERTINENT FUELS IRRADIATION 3.6-3 INFORMATION 3.6.3.1 High Linear Heat Rating Irradiations 3.6-3 3.6.3.2 Shippingport Blanket Irradiations 3.6-3 3.6.3.3 NRX Irradiations (AECL - Canada) 3.6-4 3.6.3.4 Saxton Irradiations 3.6-4 3.6.3.5 Vallecitos Boiling Water Reactor - Dresden 3.6-4 3.6.3.6 Large Seed Blanket Reactor Rods 3.6-5 3.6.3.7 Central Melting in Big Rock 3.6-5 3.6.3.8 Peach Bottom 2 3.6-5 3.6.4 EVALUATION 3.6-6 3.

6.5 REFERENCES

3.6-6 3.7 SUPPLEMENTARY FUEL DESIGN AND EVALUATION 3.7-1 3.7.1 FUEL ROD DESIGN EVALUATION 3.7-1 3.7.1.1 Mechanical Design Evaluation 3.7-1 3.7.1.2 Fuel Thermal Design Evaluation 3.7-3

CALVERT CLIFFS UFSAR 3-iii Rev. 52 CHAPTER 3 REACTOR TABLE OF CONTENTS PAGE 3.7.1.3 License Conditions with RODEX2 Methodology 3.7-8 3.7.2 DESIGN EVALUATION OF OTHER FUEL ASSEMBLY 3.7-9 COMPONENTS 3.7.2.1 Burnable Poison Rod Design Evaluation 3.7-9 3.7.2.2 CEA Guide Tube Evaluation 3.7-9 3.7.3 DEMONSTRATION PROGRAMS 3.7-10 3.7.3.1 Introduction 3.7-10 3.7.3.2 CE/EPRI Fuel Performance Evaluation 3.7-10 3.7.3.3 CE Irradiation of Test Fuel Rods 3.7-11 3.7.3.4 SCOUT Program 3.7-11 3.7.3.5 PROTOTYPE Program 3.7-11 3.7.3.6 Materials Surveillance Specimens 3.7-12 3.7.3.7 Prototype CEA 3.7-12 3.7.3.8 ANF Demonstration Assemblies 3.7-12 3.7.3.9 Erbium Demonstration Assemblies 3.7-12 3.7.3.10 Test Capsule Assemblies 3.7-13 3.7.3.11 Lead Fuel Assemblies for Unit 2 Cycle 11 3.7-13 3.7.3.12 Batch 1RT Lead Fuel Assemblies 3.7-13 3.7.3.13 Framatome and Westinghouse Lead Fuel Assemblies 3.7-14 for Unit 2 Cycle 15 3.7.3.14 Framatome Lead Test Assemblies for Unit 2 Cycle 24 3.7-15 3.7.4 CHRONOLOGY OF FUEL EXPERIENCE 3.7-15 3.7.4.1 Unit 1 3.7-15 3.7.4.2 Unit 2 3.7-27 3.

7.5 REFERENCES

3.7-35

CALVERT CLIFFS UFSAR 3-iv Rev. 52 CHAPTER 3 REACTOR LIST OF TABLES TITLE PAGE 3.2-1 PRIMARY STRESS LIMITS FOR CRITICAL REACTOR VESSEL 3.2-6 INTERNAL STRUCTURES 3.3-1 UNIT 1 BATCH-RELATED DATA 3.3-18 3.3-2 UNIT 2 BATCH-RELATED DATA 3.3-37 3.3-3 BURNABLE POISON ROD DATA 3.3-56 3.3-4 CONTROL ELEMENT ASSEMBLY DATA 3.3-58 3.3-5 CORE RELATED DATA 3.3-60 3.4-1 NUCLEAR PARAMETERS 3.4-15 3.4-2 CEA REACTIVITY WORTH AND ALLOWANCES, (% ) 3.4-17 3.5-1 DELETED 3.5-18 3.5-2 REACTOR COOLANT FLOWS IN BYPASS CHANNELS 3.5-19 3.5-3 DESIGN REACTOR PRESSURE LOSSES 3.5-20 3.6-1 TYPICAL PEAK BURNUP - MAXIMUM HEAT RELATIONSHIP 3.6-8 3.6-2 COMPARISON OF MAXIMUM HEAT RATINGS 3.6-9

CALVERT CLIFFS UFSAR 3-v Rev. 52 CHAPTER 3 REACTOR LIST OF FIGURES FIGURE 3.1-1 REACTOR VERTICAL ARRANGEMENT 3.3-1 REACTOR CORE CROSS -SECTION 3.3-2 FIRST CYCLE FUEL ROD 3.3-3 FUEL ROD 3.3-3A FUEL ROD ASSEMBLY (Westinghouse) 3.3-3B FUEL ROD DESIGN (UNIT 2 CYCLE 16) 3.3-3C FUEL ROD DESIGN (UNIT 1 CYCLES 18, 19, & 20 AND UNIT 2 CYCLES 17 & 18) 3.3-4 sh 1-47 BURNABLE POISON ROD LOCATION (Sheets 1 - 47) 3.3-5 FUEL ASSEMBLY 3.3-6 FUEL ASSEMBLY HOLD DOWN 3.3-7 CANTILEVER TAB FUEL SPACER GRID 3.3-7A I-SPRING UNVANED SPACER GRID (TURBO) 3.3-7B I-SPRING VANED SPACER GRID (TURBO) 3.3-8 CONTROL ELEMENT ASSEMBLY (CEA) 3.3-9A WESTINGHOUSE/ABB-CE - CONTROL ELEMENT ASSEMBLIES 3.3-9B AREVA/FRAMATOME - CONTROL ELEMENT ASSEMBLIES 3.3-10 CEA GROUP IDENTIFICATION 3.3-11 CORE ORIENTATION 3.3-12 PRESSURE VESSEL - CORE SUPPORT BARREL SNUBBER ASSEMBLY 3.3-13 CORE SHROUD ASSEMBLY 3.3-14 UPPER GUIDE STRUCTURE ASSEMBLY 3.3-15 CONTROL ELEMENT DRIVE MECHANISM (MAGNETIC JACK) 3.3-16 AREVA/FRAMATOME HTP FUEL ASSEMBLY, FUEL ROD, AND SPACER GRIDS 3.4-1 CYCLE 1 FUEL TEMPERATURE COEFFICIENT VS AVERAGE FUEL TEMPERATURE 3.4-2 CYCLE 1 POWER COEFFICIENT VS PERCENT OF FULL POWER (BEGINNING OF FIRST CYCLE) 3.4-3 FIRST CYCLE FUEL ASSEMBLY IDENTIFICATION BOTH UNITS 3.4-4 UNIT 1 CYCLE 25 QUARTER-CORE ASSEMBLY MAP 3.4-5 UNIT 2 CYCLE 24 QUARTER-CORE ASSEMBLY MAP 3.4-6 CYCLE 1 CORE POWER DISTRIBUTION, 2560 MWT (BEGINNING-OF-LIFE), NO XENON 3.4-7 UNIT 1 CYCLE 25 ASSEMBLY RELATIVE POWER DENSITY AT BOC, HFP, ARO, EQUILIBRIUM XENON 3.4-8 UNIT 2 CYCLE 24 ASSEMBLY RELATIVE POWER DENSITY AT BOC, HFP, ARO, EQUILIBRIUM XENON 3.4-9 CYCLE 1 CORE POWER DISTRIBUTION, 2560 MWT, 1000 MWD/MTU, EQUILIBRIUM XENON 3.4-10 UNIT 1 CYCLE 25 ASSEMBLY RELATIVE POWER DENSITY AT 10,000 MWd/MTU, HFP, ARO, EQUILIBRIUM XENON 3.4-11 UNIT 2 CYCLE 24 ASSEMBLY RELATIVE POWER DENSITY AT 10,000 MWd/MTU, HFP, ARO, EQUILIBRIUM XENON

CALVERT CLIFFS UFSAR 3-vi Rev. 52 CHAPTER 3 REACTOR LIST OF FIGURES FIGURE 3.4-12 CYCLE 1 CORE POWER DISTRIBUTION, 2560 MWT, END-OF-CYCLE, EQUILIBRIUM XENON 3.4-13 UNIT 1 CYCLE 25 ASSEMBLY RELATIVE POWER DENSITY AT EOC, HFP, ARO, EQUILIBRIUM XENON 3.4-14 UNIT 2 CYCLE 24 ASSEMBLY RELATIVE POWER DENSITY AT EOC, HFP, ARO, EQUILIBRIUM XENON 3.4-15 CORE POWER DISTRIBUTION - CEA GROUP 5 BEGINNING OF FIRST CYCLE, NO XENON 3.4-16 UNIT 1 CYCLE 25 ASSEMBLY RELATIVE POWER DENSITY WITH BANK 5 INSERTED TO PDIL AT BOC, HFP, EQUILIBRIUM XENON 3.4-17 UNIT 2 CYCLE 24 ASSEMBLY RELATIVE POWER DENSITY WITH BANK 5 INSERTED TO PDIL AT BOC, HFP, EQUILIBRIUM XENON 3.4-18 CORE POWER DISTRIBUTION - CEA GROUP 5 END-OF-CYCLE 1, EQUILIBRIUM 3.4-19 UNIT 1 CYCLE 25 ASSEMBLY RELATIVE POWER DENSITY WITH BANK 5 INSERTED TO PDIL AT EOC, HFP, EQUILIBRIUM XENON 3.4-20 UNIT 2 CYCLE 24 ASSEMBLY RELATIVE POWER DENSITY WITH BANK 5 INSERTED TO PDIL AT EOC, HFP, EQUILIBRIUM XENON 3.4-21 CORE POWER DISTRIBUTION - PART LENGTH CEA (P-1),

BEGINNING OF FIRST CYCLE, NO XENON 3.4-22 CORE POWER DISTRIBUTION - PART LENGTH CEA (P-1),

BEGINNING OF FIRST CYCLE, EQUILIBRIUM XENON 3.4-23 AXIAL PEAK VS % CEA INSERTION (BEGINNING OF FIRST CYCLE) 3.4-24 AXIAL PEAK VS CEA INSERTION WITH PART LENGTH CEAs (END OF FIRST CYCLE) 3.4-25 NUCLEAR HEAT FLUX PEAK VS CEA INSERTION (BEGINNING OF FIRST CYCLE) 3.4-26 NUCLEAR HEAT FLUX PEAK VS CEA INSERTION WITH PART LENGTH CEAs (END OF FIRST CYCLE) 3.4-27 FIRST CYCLE POWER DEPENDENT CEA INSERTION LIMITS 3.4-28 Deleted 3.7-1 FRAMATOME LEAD FUEL ASSEMBLY

CALVERT CLIFFS UFSAR 3-vii Rev. 52 CHAPTER 3 REACTOR LIST OF ACRONYMS ABB Asea Brown Boveri, Inc.

ANF Advanced Nuclear Fuel AOO Anticipated Operational Occurrence APD Axial Power Distribution ARI All Rods Inserted ASI Axial Shape Index ASME American Society of Mechanical Engineers B&PV Boiler and Pressure Vessel BGE Baltimore Gas and Electric Company BOC Beginning of Cycle BOL Beginning of Life BPR Burnable Poison Rods CE Combustion Engineering, Inc.

CEA Control Element Assembly CEDM Control Element Drive Mechanism CEDS Control Element Drive System CHF Critical Heat Flux CVCS Chemical and Volume Control System DBE Design Basis Event DNB Departure from Nucleate Boiling DNBR Departure from Nucleate Boiling Ratio ENDF Evaluated Nuclear Data File EOC End of Cycle EOL End of Life ESCU Extended Statistical Combination of Uncertainties ESFAS Engineered Safety Feature Actuation Signal FANP Framatome Advanced Nuclear Power FTC Fuel Temperature Coefficient GTFS Guide Tube Flux Suppressor HTP High Thermal Performance HMP High Mechanical Performance ICI Incore Instrumentation IFBA Integral Fuel Burnable Absorber LCO Limiting Conditions for Operation LEF Lower End Fitting LFA Lead Fuel Assemblies LHR Linear Heat Rate LOCA Loss-of-Coolant Accident LPD Local Power Density LSBR Large Seed Blanket Reactor LSSS Limiting Safety System Setting MDNBR Minimum Departure from Nucleate Boiling Ratio MRR Most Reactive Rod MTC Moderator Temperature Coefficient

CALVERT CLIFFS UFSAR 3-viii Rev. 52 CHAPTER 3 REACTOR LIST OF ACRONYMS NEM Nodal Expansion Method NRC Nuclear Regulatory Commission PCI Pellet-Clad Interaction PDF Probability Distribution Function PDIL Power Dependent Insertion Limit PLCEA Part Length Control Element Assembly PLHR Peak Linear Heat Rate PWR Pressurized Water Reactor RCS Reactor Coolant System RPS Reactor Protective System RSS Root-Sum-Square SAFDL Specified Acceptable Fuel Design Limit SCU Statistical Combination of Uncertainties SS Stainless Steel T-H Thermal Hydraulics TD Theoretical Density TM/LP Thermal Margin/Low Pressure UGS Upper Guide Structure UO2 Uranium Oxide VAP Value Added Pellet VBWR Vallecitos Boiling Water Reactor ZrB2 Zirc Diboride

CALVERT CLIFFS UFSAR 3-ix Rev. 52