ML18117A359
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TMI-1 UFSAR CHAPTER 03 3-i REV. 21, APRIL 2012 CHAPTER 03 - REACTOR TABLE OF CONTENTS SECTION TITLE 3.0 REACTOR 3.1 DESIGN BASES 3.1.1 PERFORMANCE OBJECTIVES 3.1.2 LIMITS 3.1.2.1 NUCLEAR LIMITS 3.1.2.2 REACTIVITY CONTROL LIMITS 3.1.2.3 THERMAL AND HYDRAULIC LIMITS 3.1.2.4 MECHANICAL LIMITS 3.1.2.4.1 REACTOR INTERNALS 3.1.2.4.1.1 ALLOWABLE STRESSES 3.1.2.4.1.2 METHODS OF LOAD ANALYSIS EMPLOYED FOR REACTOR INTERNALS AND CORE 3.1.2.4.2 CORE COMPONENTS 3.1.2.4.2.1 FUEL ASSEMBLIES 3.1.2.4.2.2 CONTROL ROD ASSEMBLIES (CRAs) 3.1.2.4.2.3 ORIFICE ROD ASSEMBLIES (ORAs) 3.1.2.4.3 CONTROL ROD DRIVE MECHANISMS 3.1.2.4.3.1 SHIM SAFETY DRIVE 3.1.2.4.3.2 DELETED 3.2 REACTOR DESIGN 3.2.1 GENERAL
SUMMARY
3.2.2 NUCLEAR DESIGN AND EVALUATION 3.2.2.1 NUCLEAR CHARACTERISTICS OF THE DESIGN 3.2.2.1.1 EXCESS REACTIVITY 3.2.2.1.2 REACTIVITY CONTROL DISTRIBUTION 3.2.2.1.3 SHUTDOWN REACTIVITY ANALYSIS 3.2.2.1.4 CONTROL ROD GROUPS FOR OPERATION 3.2.2.1.5 REACTIVITY COEFFICIENTS 3.2.2.1.5.1 DOPPLER COEFFICIENT 3.2.2.1.5.2 MODERATOR VOID COEFFICIENT 3.2.2.1.5.3 MODERATOR PRESSURE COEFFICIENT 3.2.2.1.5.4 MODERATOR TEMPERATURE COEFFICIENT 3.2.2.1.5.5 POWER COEFFICIENT 3.2.2.1.6 REACTIVITY INSERTION RATES 3.2.2.1.7 POWER DECAY CURVES 3.2.2.2 NUCLEAR EVALUATION 3.2.2.2.1 ANALYTICAL MODELS 3.2.2.2.1.1 FUEL CYCLE ANALYSIS 3.2.2.2.1.2 CONTROL OF POWER DISTRIBUTIONS 3.2.2.2.1.3 POWER MALDISTRIBUTIONS 3.2.2.2.1.4 CONTROL ROD ANALYSIS 3.2.2.2.2 XENON STABILITY ANALYSIS AND CONTROL
TMI-1 UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE CHAPTER 03 3-ii REV. 21, APRIL 2012 3.2.3 THERMAL AND HYDRAULIC DESIGN AND EVALUATION 3.2.3.1 THERMAL AND HYDRAULIC CHARACTERISTICS 3.2.3.1.1 FUEL ASSEMBLY HEAT TRANSFER DESIGN 3.2.3.1.1.1 DESIGN CRITERIA 3.2.3.1.1.2 CRITICAL HEAT FLUX CORRELATION 3.2.3.1.1.3 NUCLEAR POWER FACTORS 3.2.3.1.1.4 ENGINEERING HOT CHANNEL FACTORS 3.2.3.1.1.5 CORE FLOW DISTRIBUTION HOT CHANNEL FACTORS 3.2.3.1.1.6 MAXIMUM REACTOR DESIGN OVERPOWER 3.2.3.1.1.7 MAXIMUM DESIGN CONDITIONS 3.2.3.1.1.8 MOST PROBABLE DESIGN CONDITIONS 3.2.3.1.1.9 HOT CHANNEL PERFORMANCE FOR FOUR-PUMP OPERATION 3.2.3.1.1.10 HOT CHANNEL PERFORMANCE
SUMMARY
FOR PARTIAL PUMP FLOW 3.2.3.1.1.11 HOT CHANNEL PERFORMANCE
SUMMARY
FOR LOSS OF ALL COOLANT FLOW 3.2.3.1.2 APPLICATION OF COMPUTER CODES TO FUEL AND CLAD THERMAL CALCULATIONS 3.2.3.1.2.1 TAFY 3.2.3.1.2.2 TACO 3.2.3.1.2.3 TAFY/TACO DIFFERENCES 3.2.3.1.3 END-OF-LIFE CLAD TRANSIENTS 3.2.3.2 THERMAL AND HYDRAULIC EVALUATION 3.2.3.
2.1 INTRODUCTION
3.2.3.2.2 STATISTICAL CORE DESIGN TECHNIQUE 3.2.3.2.3 EVALUATION OF THE THERMAL AND HYDRAULIC DESIGN 3.2.3.2.3.1 HOT CHANNEL COOLANT QUALITY AND VOID FRACTION 3.2.3.2.3.2 CORE VOID FRACTION 3.2.3.2.3.3 COOLANT CHANNEL HYDRAULIC STABILITY 3.2.3.2.3.4 HOT CHANNEL DNB COMPARISONS 3.2.3.2.3.5 REACTOR FLOW EFFECTS 3.2.3.2.3.6 REACTOR INLET TEMPERATURE EFFECTS 3.2.3.2.3.7 FUEL TEMPERATURE 3.2.3.2.3.8 FISSION GAS RELEASE 3.2.3.2.3.9 HOT CHANNEL FACTORS EVALUATION 3.2.3.2.3.10 EVALUATION OF THE DNBRs IN THE UNIT, WALL, CONTROL ROD AND CORNER CELLS 3.2.3.2.3.11 REMOVAL OF ORIFICE ROD ASSEMBLIES 3.2.3.2.4 FLUX FLOW TRIP SET POINT 3.2.3.2.5 EVALUATION OF INTERNALS VENT VALVE 3.2.4 MECHANICAL DESIGN 3.2.4.1 REACTOR INTERNALS 3.2.4.1.1 PLENUM ASSEMBLY 3.2.4.1.2 CORE SUPPORT ASSEMBLY 3.2.4.1.2.1 CORE SUPPORT SHIELD 3.2.4.1.2.2 CORE BARREL
TMI-1 UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE CHAPTER 03 3-iii REV. 21, APRIL 2012 3.2.4.1.2.3 LOWER GRID ASSEMBLY 3.2.4.1.2.4 FLOW DISTRIBUTOR 3.2.4.1.2.5 THERMAL SHIELD 3.2.4.1.2.6 SURVEILLANCE SPECIMEN HOLDER TUBES 3.2.4.1.2.7 INCORE INSTRUMENT GUIDE TUBE ASSEMBLY 3.2.4.1.2.8 INTERNALS VENT VALVES 3.2.4.2 CORE COMPONENTS 3.2.4.2.1 FUEL ASSEMBLIES 3.2.4.2.1.1 FUEL ASSEMBLY DESCRIPTION 3.2.4.2.1.2 FUEL ASSEMBLY EVALUATION 3.2.4.2.2 CONTROL ROD ASSEMBLY (CRA) 3.2.4.2.3 DELETED 3.2.4.2.4 BURNABLE POISON ROD ASSEMBLY (BPRA) 3.2.4.2.5 ORIFICE ROD ASSEMBLY (ORA) 3.2.4.2.6 BURNABLE POISON ROD ASSEMBLY AND ORIFICE ROD ASSEMBLY RETAINERS 3.2.4.2.6.1 BURNABLE POISON ROD ASSEMBLY RETAINERS 3.2.4.2.6.2 ORIFICE ROD ASSEMBLY RETAINERS 3.2.4.2.7 QUALITY CONTROL PROGRAM FOR CORE 3.2.4.3 CONTROL ROD DRIVES 3.2.4.
3.1 DESCRIPTION
3.2.4.3.1.1 GENERAL DESIGN CRITERIA 3.2.4.3.1.2 ADDITIONAL DESIGN CRITERIA 3.2.4.3.2 CONTROL ROD DRIVE MECHANISMS 3.2.4.3.2.1 SHIM SAFETY DRIVE MECHANISM 3.2.4.3.2.2 AXIAL POWER SHAPING ROD DRIVE MECHANISM 3.3 TESTS AND INSPECTIONS 3.3.1 NUCLEAR TESTS AND INSPECTION 3.3.1.1 CRITICAL EXPERIMENTS 3.3.1.2 ZERO POWER, APPROACH TO POWER AND POWER TESTING 3.3.2 THERMAL AND HYDRAULIC TESTS AND INSPECTION 3.3.2.1 REACTOR VESSEL FLOW DISTRIBUTION AND PRESSURE DROP TEST 3.3.3 FUEL ASSEMBLY, CONTROL ROD ASSEMBLY, AND CONTROL ROD DRIVE MECHANICAL TESTS AND INSPECTION 3.3.3.1 PROTOTYPE TESTING 3.3.3.2 MODEL TESTING 3.3.3.3 COMPONENT AND/OR MATERIAL TESTING 3.3.3.3.1 FUEL ROD CLADDING 3.3.3.3.2 FUEL ASSEMBLY STRUCTURAL COMPONENTS 3.3.3.4 CONTROL ROD DRIVE TESTS AND INSPECTION 3.3.3.4.1 CONTROL ROD DRIVE DEVELOPMENTAL TESTS 3.3.3.4.2 PRODUCTION TESTS 3.3.4 INTERNALS TESTS AND INSPECTIONS 3.3.4.1 INTERNALS NON-DESTRUCTIVE TESTING 3.3.4.1.1 ULTRASONIC EXAMINATION
TMI-1 UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE CHAPTER 03 3-iv REV. 21, APRIL 2012 3.3.4.1.2 RADIOGRAPHIC EXAMINATION (INCLUDES X-RAY OR RADIOACTIVE SOURCES) 3.3.4.1.3 LIQUID PENETRANT EXAMINATION 3.3.4.1.4 VISUAL (5X MAGNIFICATION) EXAMINATION 3.3.4.1.5 INTERNALS VENT VALVE TESTS 3.3.4.2 INTERNALS VIBRATION TESTS
3.4 REFERENCES
TMI-1 UFSAR CHAPTER 03 3-v REV. 21, APRIL 2012 CHAPTER 03 - REACTOR LIST OF TABLES TABLE TITLE 3.2-1 CORE DESIGN DATA 3.2-2 NUCLEAR DESIGN DATA 3.2-3 EXCESS REACTIVITY CONDITIONS (INITIAL CYCLE) 3.2-4 CYCLE REACTIVITY CONTROL DISTRIBUTION (CURRENT CYCLE) 3.2-5 HFP CRITICAL BORON CONCENTRATION OVER CORE LIFE (CURRENT CYCLE) 3.2-6 SHUTDOWN REACTIVITY ANALYSIS (CURRENT CYCLE) 3.2-7 CONTROL ROD GROUP WORTHS AT HZP (CURRENT CYCLE) 3.2-8 DELETED 3.2-9 REACTIVITY COEFFICIENTS (CURRENT CYCLE) 3.2-10 EXPERIMENTAL AND CALCULATED ROD AND ROD ASSEMBLY COMPARISON 3.2-11 THERMAL AND HYDRAULIC DATA 3.2-12 NUCLEAR POWER FACTORS 3.2-13 COEFFICIENTS OF VARIATION 3.2-14 HOT CHANNEL DATA & PERFORMANCE FOR FOUR-PUMP OPERATION 3.2-15 HOT CHANNEL PERFORMANCE VS PUMPS IN SERVICE 3.2-16 FUEL ASSEMBLY COMPONENT DIMENSIONS 3.2-17 HOT CHANNEL AND CORE AVERAGE COOLANT CONDITIONS (INITIAL CYCLE) 3.2-18 TYPICAL HOT CHANNEL DNB (BWC) AS A FUNCTION OF POWER (CURRENT CYCLE) 3.2-19 REACTOR CORE BYPASS FLOW (CURRENT CYCLE) 3.2-20 DNB RATIOS IN THE FUEL ASSEMBLY CHANNELS (W-3)
TMI-1 UFSAR LIST OF TABLES (cont'd)
TABLE TITLE CHAPTER 03 3-vi REV. 21, APRIL 2012 3.2-21 INTERNAL VENT VALVE MATERIALS 3.2-22 VENT VALVE SHAFT AND BUSING CLEARANCES 3.2-23 CLAD CIRCUMFERENTIAL STRESSES 3.2-24 CONTROL ROD ASSEMBLY DATA 3.2-25 DELETED 3.2-26 BURNABLE POISON ROD ASSEMBLY DATA 3.2-27 ORIFICE ROD ASSEMBLY DATA 3.2-28 CONTROL ROD DRIVE MECHANISM DESIGN DATA
TMI-1 UFSAR CHAPTER 03 3-vii REV. 21, APRIL 2012 CHAPTER 03 - REACTOR LIST OF FIGURES FIGURE TITLE 3.2-1 CONTROL ROD LOCATIONS AND GROUP DESIGNATIONS FOR TMI-1, CURRENT CYCLE 3.2-2 EJECTED ROD LOCATION BOC AND EOC 3.2-3 STUCK ROD LOCATION BOC AND EOC 3.2-4 FRACTIONS OF CHANGE IN THE RESONANCE INTEGRAL AS A FUNCTION OF T-300 FOR UO2 ROD (T IN DEGREE K) 3.2-5 UNIFORM VOID COEFFICIENT FOR 177 ASSEMBLY 3.2-6 PERCENT NEUTRON POWER VERSUS TIME FOLLOWING TRIP, BOC 3.2-7 CORE LOADING DIAGRAM TMI-1, CURRENT CYCLE 3.2-8 DELETED 3.2-9 TYPICAL DNB RATIOS (BAW-2) IN THE HOT UNIT CELL (CYCLE 5) 3.2-10 DISTRIBUTION OF FUEL ROD PEAKING (INITIAL CYCLE) 3.2-11 MAXIMUM ALLOWABLE AXIAL POWER DISTRIBUTIONS FOR A RADIAL LOCAL PEAKING FACTOR OF 1.78 3.2-12 EQUIVALENT AXIAL POWER DISTRIBUTIONS FOR RADIAL LOCAL PEAKING FACTOR OF 1.65 (INITIAL CYCLE) 3.2-13 DNB RATIOS (W-3) IN HOT UNIT CELL VERSUS REACTOR POWER (INITIAL CYCLE) 3.2-14 MAXIMUM HOT CHANNEL EXIT QUALITY VERSUS REACTOR POWER (INITIAL CYCLE) 3.2-15 HOT CHANNEL DNB RATIO (W-3) VERSUS POWER FOR PARTIAL PUMP OPERATION (INITIAL CYCLE) 3.2-16 HOT CHANNEL QUALITY AT POINT OF MINIMUM DNBR VERSUS POWER FOR PARTIAL PUMP OPERATION (INITIAL CYCLE) 3.2-17 THERMAL CONDUCTIVITY OF UO2
TMI-1 UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE CHAPTER 03 3-viii REV. 21, APRIL 2012 3.2-18 NUMBER OF DATA POINTS VERSUS E/C 3.2-19 DNB RATIO (BAW-2) VERSUS POPULATION FOR VARIOUS CONFIDENCE LEVELS 3.2-20 HOT CHANNEL FACTORS VS. PERCENT POPULATION PROTECTED 3.2-21 HOT CHANNEL AND NOMINAL CHANNEL EXIT QUALITIES VERSUS REACTOR POWER (WITHOUT ENGINEERING HOT CHANNEL FACTORS)
(INITIAL CYCLE) 3.2-22 FLOW REGIME MAP FOR THE HOT UNIT CELL 3.2-23 FLOW REGIME MAP FOR THE HOT CONTROL ROD 3.2-24 FLOW REGIME MAP FOR THE HOT WALL CELL 3.2-25 FLOW REGIME MAP FOR THE HOT CORNER CELL 3.2-26 REACTOR COOLANT SYSTEM FLOW VERSUS POWER (INITIAL CYCLE) 3.2-27 HOT CHANNEL DNB RATIO (W-3) VERSUS POWER WITH REACTOR SYSTEM FLOW AND ENERGY MIXING AS PARAMETERS (INITIAL CYCLE) 3.2-28 FUEL CENTER TEMPERATURE FOR BEGINNING-OF-CYCLE CONDITIONS (INITIAL CYCLE) 3.2-29 FUEL CENTER TEMPERATURE FOR END-OF-CYCLE CONDITIONS (INITIAL CYCLE) 3.2-30 TYPICAL POST-INITIAL CYCLE CENTER LINE FUEL TEMPERATURE VERSUS LINEAR HEAT RATE HOT PIN (CYCLE 5) 3.2-31 BURNUP EFFECT ON FUEL CENTER TEMPERATURE (INITIAL CYCLE) 3.2-32 FUEL TEMPERATURE VERSUS TOTAL FUEL VOLUME FRACTION FOR EQUILIBRIUM CYCLE AT END-OF-CYCLE 3.2-33 TYPICAL REACTOR FUEL ASSEMBLY POWER DISTRIBUTION AT END-OF-CYCLE EQUILIBRIUM CYCLE CONDITIONS FOR 1/8 CORE 3.2-34 FUEL ROD TEMPERATURE PROFILES AT 6 AND 10 Kw/FT 3.2-35 PERCENT FISSION GAS RELEASED AS A FUNCTION OF THE AVERAGE TEMPERATURE OF THE UO2 FUEL
TMI-1 UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE CHAPTER 03 3-ix REV. 21, APRIL 2012 3.2-36 AXIAL LOCAL TO AVERAGE BURNUP AND INSTANTANEOUS POWER COMPARISONS 3.2-37 FUEL TO CLAD GAP CONDUCTANCE FOR END-OF-LIFE CONDITIONS (INITIAL CYCLE) 3.2-38 FISSION GAS RELEASE FOR 1.5 AND 1.7 MAX/ AVG AXIAL POWER SHAPES (INITIAL CYCLE) 3.2-39 MAXIMUM GAS RELEASE TO PRESSURE INSIDE THE FUEL CLAD FOR VARIOUS AXIAL BURNUP AND POWER SHAPES (INITIAL CYCLE) 3.2-40 NOMINAL FUEL ROD POWER PEAKS AND CELL EXIT ENTHALPY RISE RATIOS (INITIAL CYCLE) 3.2-41 MAXIMUM FUEL ROD POWER PEAKS AND CELL EXIT ENTHALPY RISE RATIOS (INITIAL CYCLE) 3.2-42 CALCULATED AND DESIGN LIMIT LOCAL HEAT FLUX VERSUS ENTHALPY IN THE HOT UNIT CELL AT THE MOST PROBABLE CONDITION (INITIAL CYCLE) 3.2-43 CALCULATED AND DESIGN LIMIT LOCAL HEAT FLUX VERSUS ENTHALPY IN THE HOT UNIT CELL AT THE MAXIMUM DESIGN CONDITION 3.2-44 REACTOR VESSEL AND INTERNALS GENERAL ARRANGEMENT 3.2-45 REACTOR VESSEL AND INTERNALS CROSS SECTION 3.2-46 CORE FLOODING ARRANGEMENT 3.2-47 INTERNALS VENT VALVE 3.2-48 INTERNALS VENT VALVE CLEARANCE GAPS 3.2-49 FUEL ASSEMBLY 3.2-50 CONTROL ROD ASSEMBLY 3.2-51 AXIAL POWER SHAPING ROD ASSEMBLY 3.2-52 BURNABLE POISON ROD ASSEMBLY 3.2-53 ORIFICE ROD ASSEMBLY 3.2-54 SIDE VIEW OF BPRA RETAINER
TMI-1 UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE CHAPTER 03 3-x REV. 21, APRIL 2012 3.2-55 TOP VIEW OF BPRA RETAINER DURING OPERATION 3.2-56 CONTROL ROD DRIVE - GEN. ARRANGEMENT 3.2-57 CONTROL ROD DRIVE - VERTICAL SECTION