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TMI-1 UFSAR CHAPTER 06 6-i REV. 23, APRIL 2016 CHAPTER 6 - ENGINEERED SAFEGUARDS TABLE OF CONTENTS SECTION TITLE 6.0 ENGINEERED SAFEGUARDS 6.1 EMERGENCY CORE COOLING SYSTEM 6.1.1 DESIGN BASES 6.1.2 SYSTEM DESIGN 6.1.2.1 ECCS OPERATION 6.1.2.2 CODES AND STANDARDS 6.1.2.3 MATERIAL COMPATIBILITY 6.1.2.4 COMPONENT DESIGN 6.1.2.5 COOLANT STORAGE 6.1.2.6 PUMP CHARACTERISTICS 6.1.2.7 HEAT EXCHANGER CHARACTERISTICS 6.1.2.8 RELIEF VALVE SETTINGS 6.1.2.9 RELIABILITY CONSIDERATIONS 6.1.2.10 MISSILE PROTECTION 6.1.2.11 ACTUATION 6.1.2.12 ENVIRONMENTAL CONSIDERATIONS 6.1.2.13 ECCS SUMP STRAINER DESIGN CONSIDERATIONS 6.1.2.14 GL 2008-01 GAS ENTRAINMENT PROGRAM 6.1.3 DESIGN EVALUATION 6.1.3.1 MAKEUP AND PURIFICATION SYSTEM (INCLUDES HIGH PRESSURE INJECTION) 6.1.3.2 DECAY HEAT REMOVAL SYSTEM (INCLUDES LOW PRESSURE INJECTION) 6.1.3.3 CORE FLOODING SYSTEM 6.1.4 TESTS AND INSPECTIONS 6.2 REACTOR BUILDING SPRAY SYSTEM 6.2.1 DESIGN BASES 6.2.2 SYSTEM DESIGN 6.2.2.1 PIPING AND INSTRUMENTATION DIAGRAM 6.2.2.2 CODES AND STANDARDS 6.2.2.3 MATERIAL COMPATIBILITY 6.2.2.4 COMPONENT DESIGN 6.2.2.5 COOLANT STORAGE 6.2.2.6 PUMP CHARACTERISTICS 6.2.2.7 RELIABILITY CONSIDERATIONS 6.2.2.8 MISSILE PROTECTION 6.2.2.9 ACTUATION 6.2.2.10 ENVIRONMENTAL CONSIDERATIONS 6.2.3 DESIGN EVALUATION 6.2.4 TESTS AND INSPECTION 6.2.4.1 INITIAL TESTING 6.2.4.2 PERIODIC TESTING
TMI-1 UFSAR TABLE OF CONTENTS (cont'd)
SECTION TITLE CHAPTER 06 6-ii REV. 23, APRIL 2016 6.3 REACTOR BUILDING EMERGENCY COOLING SYSTEM 6.3.1 DESIGN BASES 6.
3.2 DESCRIPTION
6.3.3 ACTUATION 6.4 ENGINEERED SAFEGUARDS LEAKAGE AND RADIATION CONSIDERATIONS 6.
4.1 INTRODUCTION
6.4.2
SUMMARY
OF POSTACCIDENT RECIRCULATION 6.4.3 BASES OF LEAKAGE ESTIMATE 6.4.4 DESIGN BASIS LEAKAGE 6.4.5 SAFEGUARDS CUBICLE LEAK DETECTION 6.4.6 PERIODIC LEAK REDUCTION PROGRAM 6.5 REACTOR BUILDING COMBUSTIBLE GAS CONTROL 6.5.1 DELETED 6.5.1.1 DELETED 6.5.1.2 DELETED 6.5.1.3 DELETED 6.5.1.4 DELETED 6.5.2 HYDROGEN MONITORING 6.5.2.1 DESIGN BASIS 6.5.2.2 SYSTEM DESCRIPTION AND DESIGN 6.5.2.3 DESIGN EVALUATION 6.5.2.4 TESTS AND INSPECTIONS 6.5.3 HYDROGEN GENERATION 6.5.3.1 DESIGN BASIS 6.5.3.2 PHENOMENA DESCRIPTION 6.5.3.3 DESIGN EVALUATION 6.6 REACTOR BUILDING PRESSURE TIME RESPONSE 6.6.1 PEAK CONTAINMENT PRESSURE 6.6.2 MINIMUM CONTAINMENT BACKPRESSURE
6.7 REFERENCES
TMI-1 UFSAR CHAPTER 06 6-iii REV. 23, APRIL 2016 CHAPTER 6 - ENGINEERED SAFEGUARDS LIST OF TABLES TABLE TITLE 6.1-1 CORE FLOODING SYSTEM COMPONENT DATA 6.1-2 QUALITY CONTROL STANDARDS FOR ENGINEERED SAFEGUARDS SYSTEMS 6.1-3 ENGINEERED SAFEGUARDS PIPING DESIGN CONDITIONS 6.1-4 SINGLE FAILURE ANALYSIS - EMERGENCY CORE COOLING SYSTEM 6.1-5 EMERGENCY INJECTION SYSTEMS COMPONENT TESTING 6.1-6 DESIGN BASIS ACCIDENT BS & DH PUMP NPSH EVALUATION
SUMMARY
6.2-1 REACTOR BUILDING SPRAY SYSTEM DATA 6.2-2 SINGLE FAILURE ANALYSIS - REACTOR BUILDING SPRAY SYSTEM 6.3-1 SINGLE FAILURE ANALYSIS - REACTOR BUILDING EMERGENCY COOLING SYSTEM 6.3-2 REACTOR BUILDING COOLING UNIT PERFORMANCE AND EQUIPMENT DATA 6.3-3 DELETED 6.3-4 DELETED 6.3-5 DELETED 6.3-6 DELETED 6.3-7 DELETED 6.3-8 DELETED 6.3-9 DELETED 6.4-1 DELETED 6.4-2 DELETED
TMI-1 UFSAR LIST OF TABLES (cont'd)
TABLE TITLE CHAPTER 06 6-iv REV. 23, APRIL 2016 6.4-3 DELETED 6.6-1 PEAK REACTOR BUILDING PRESSURE VERSUS BREAK SIZE AND LOCATION 6.6-2 MASS RATE AND ENTHALPY TO THE REACTOR BUILDING FOR A 14.1 FT2 HOT LEG BREAK 6.6-3 MASS RATE AND ENTHALPY TO THE REACTOR BUILDING FOR A 7 FT2 SPLIT AT THE PUMP SUCTION 6.6-4 ENERGY DISTRIBUTION FOR THE 7 FT2 BREAK (SPLIT) AT REACTOR COOLANT PUMP SUCTION 6.6-5 A COMPARISON OF KEY PARAMETERS OF THE GENERIC EVALUATION MODEL FOR MINIMUM CONTAINMENT PRESSURE VERSUS INDIVIDUAL PLANT PARAMETERS 6.6-6 MINIMUM CONTAINMENT - BACK PRESSURE COMPARISON: TMI-1 AND GENERIC 6.6-7 REACTOR BUILDING DATA FOR REACTOR BUILDING PEAK PRESSURE ANALYSIS 6.6-8 GENERAL PARAMETERS USED IN REACTOR BUILDING PEAK PRESSURE ANALYSIS 6.6-9 HEAT TRANSFER COEFFICIENTS APPLIED TO THE HEAT STRUCTURES FOR MINIMUM BACK PRESSURE ANALYSIS
TMI-1 UFSAR CHAPTER 06 6-v REV. 23, APRIL 2016 CHAPTER 6 - ENGINEERED SAFEGUARDS LIST OF FIGURES FIGURE TITLE 6.0-1 SIMPLIFIED SCHEMATIC DIAGRAM OF ENGINEERED SAFEGUARDS SYSTEM FOR CORE AND BUILDING PROTECTION 6.0-2 SIMPLIFIED SCHEMATIC DIAGRAM OF EMERGENCY CORE COOLING SYSTEM 6.0-3 DELETED 6.0-4 DELETED 6.1-1 DELETED 6.1-2 MAKEUP PUMP CHARACTERISTICS 6.1-3 DECAY HEAT REMOVAL PUMP CHARACTERISTICS 6.1-4 DECAY HEAT REMOVAL COOLER CHARACTERISTICS 6.2-1 DELETED 6.3-1 REACTOR BUILDING EMERGENCY COOLER CHARACTERISTICS AT DESIGN CONDITIONS 6.4-1 REACTOR BUILDING SPRAY PUMP (BS-P1A) PERFORMANCE TEST 6.5-1 DELETED 6.6-1 MULTINODE REPRESENTATION OF NUCLEAR STEAM SUPPLY SYSTEM 6.6-2 REACTOR BUILDING PRESSURE VERSUS TIME FOR 8.55 FT2 COLD LEG BREAK (PUMP SUCTION) 6.6-3 REACTOR BUILDING PRESSURE VERSUS TIME FOR 7.0 FT2 COLD LEG BREAK (PUMP SUCTION) 6.6-4 REACTOR BUILDING PRESSURE VERSUS TIME FOR 5.13 FT2 COLD LEG BREAK (PUMP SUCTION) 6.6-5 REACTOR BUILDING PRESSURE VERSUS TIME FOR 3.0 FT2 COLD LEG BREAK (PUMP SUCTION) 6.6-6 REACTOR BUILDING PRESSURE VERSUS TIME FOR 2.0 FT2 COLD LEG BREAK (PUMP SUCTION)
TMI-1 UFSAR LIST OF FIGURES (cont'd)
FIGURE TITLE CHAPTER 06 6-vi REV. 23, APRIL 2016 6.6-7 REACTOR BUILDING PRESSURE VERSUS TIME FOR 0.5 FT2 COLD LEG BREAK (PUMP SUCTION) 6.6-8 AVERAGE CORE INLET VELOCITY VERSUS TIME FOR 7.0 FT2 COLD LEG BREAK (PUMP SUCTION) 6.6-9 REACTOR BUILDING PRESSURE VERSUS TIME FOR 14.1 FT2 HOT LEG BREAK 6.6-10 REACTOR BUILDING PRESSURE VERSUS TIME FOR 11.0 FT2 HOT LEG BREAK 6.6-11 REACTOR BUILDING PRESSURE VERSUS TIME FOR 8.55 FT2 HOT LEG BREAK 6.6-12 REACTOR BUILDING PRESSURE VERSUS TIME FOR 5.0 FT2 HOT LEG BREAK 6.6-13 MINIMUM CONTAINMENT BACKPRESSURE
TMI-1 UFSAR CHAPTER 06 6-vii REV. 23, APRIL 2016 CHAPTER 6 - ENGINEERED SAFEGUARDS APPENDICES 6A
SUMMARY
DESCRIPTION - REACTOR BUILDING FAN COOLER ASSEMBLY 6B CONTAINMENT DESIGN BASIS ACCIDENT AND ENVIRONMENTAL QUALIFICATION