ML21257A268
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CHAPTER 1 INTRODUCTION AND
SUMMARY
TABLE OF CONTENTS PAGE 1.0 INTROD UCTION AND
SUMMARY
1.1-1 1.1 INTROD UCTION 1.1-1 1.
1.1 REFERENCES
1.1-2 1.2
SUMMARY
PLANT DESCRIPTION 1.2-1 1.2.1 PLANT SITE 1.2-1 1.2.2 PLANT ARRANGEMENT 1.2-1 1.2.3 REACTOR 1.2-1 1.2.4 REACTOR COOLANT SYSTEM 1.2-2 1.2.5 CONTAINMENT 1.2-2 1.2.6 ENGINEERED SAFETY FEATURES SYSTEMS 1.2-3 1.2.7 REACTOR PLANT PROTECTION, CONTROL, AND 1.2-4 INSTRUMENTATION SYSTEMS 1.2.7.1 Reactor Protection 1.2-4 1.2.7.2 Reactor Control 1.2-4 1.2.7.3 Instrumentation 1.2-5 1.2.8 ELECTRICAL SYSTEMS 1.2-5 1.2.9 AUXILIARY SYSTEMS 1.2-6 1.2.9.1 Chemical and Volume Control System 1.2-6 1.2.9.2 Shutdown Cooling System 1.2-7 1.2.9.3 Component Cooling System 1.2-7 1.2.9.4 Fuel Handling and Storage Systems 1.2-8 1.2.9.5 Sampling System 1.2-8 1.2.9.6 Cooling Water Systems 1.2-8 1.2.9.7 Plant Ventilation Systems 1.2-9 1.2.9.8 Plant Fire Protection System 1.2-10 1.2.9.9 Auxiliary Steam System 1.2-11 1.2.10 STEAM AND POWER CONVERSION SYSTEM 1.2-11 1.2.11 WASTE PROCESSING SYSTEMS 1.2-12 1.3 COMPARISON WITH OTHER PLANTS 1.3-1 1.4 PRINCIPAL ARCHITECTURAL AND ENGINEERING CRITERIA FOR 1.4-1 DESIGN 1.4.1 PLANT DESIGN 1.4-1 1.4.2 REACTOR 1.4-1 1.4.3 REACTOR COOLANT AND AUXILIARY SYSTEMS 1.4-2 1.4.4 CONTAINMENT STRUCTURE 1.4-2 1.4.5 ENGINEERED SAFETY FEATURES 1.4-2 1.4.6 PROTECTION, CONTROL, AND INSTRUMENTATION SYSTEMS 1.4-3 1.4.7 ELECTRICAL SYSTEMS 1.4-3 1.4.8 WASTE PROCESSING AND RADIATION PROTECTION 1.4-3 CALVERT CLIFFS UFSAR 1-i Rev.52
CHAPTER 1 INTRODUCTION AND
SUMMARY
TABLE OF CONTENTS PAGE 1.4.9 FUEL HANDLING AND STORAGE 1.4-3 1.4.10 NIL DUCTILITY TRANSITION TEMPERATURE 1.4-3 1.4.11 FIELD RUNNING OF 2" AND SMALLER DIAMETER PIPE 1.4-3 1.5 RESEARCH AND DEVELOPMENT REQUIREMENTS 1.5-1 1.
5.1 INTRODUCTION
1.5-1 1.5.2 CEA TESTING 1.5-1 1.5.2.1 Critical Experiments 1.5-1 1.5.2.2 Mechanical Testing 1.5-1 1.5.3 CONTROL ELEMENT DRIVE MECHANISM TESTING 1.5-2 1.5.4 FUEL ASSEMBLY DESIGN 1.5-3 1.5.4.1 Prototype Tests 1.5-3 1.5.4.2 Assembly Flow Distribution Tests 1.5-4 1.5.4.3 DNB Testing on the Mark V CEA Fuel Assembly, 1.5-5 1969-1970 1.5.4.4 Dynamic Loop and Vibration Testing 1.5-5 1.5.5 MODERATOR TEMPERATURE COEFFICIENT 1.5-6 1.5.6 FUEL ROD CLADDING 1.5-6 1.5.7 REACTOR VESSEL FLOW TESTS 1.5-7 1.5.8 INCORE INSTRUMENTATION TESTS 1.5-7 1.5.9 MATERIALS IRRADIATION SURVEILLANCE 1.5-8 1.6 ACRS SPECIAL INTEREST ITEMS 1.6-1 1.6.1 GENERAL 1.6-1 1.6.2 QUALITY ASSURANCE 1.6-1 1.6.3 FAILED FUEL DETECTION 1.6-1 1.6.4 REACTOR VESSEL THERMAL SHOCK 1.6-2 1.6.5 BLOWDOWN FORCES ON CORE AND REACTOR COOLANT 1.6-3 SYSTEM COMPONENTS 1.6.6 EFFECT OF FUEL ROD FAILURE ON ECCS PERFORMANCE 1.6-3 1.7 IDENTIF ICATION OF CONTRACTORS 1.7-1 1.8 GENERI C ISSUES 1.8-1 1.8.1 THREE MILE ISLAND ACTION ITEMS 1.8-1 1.8.2 STATION BLACKOUT 1.8-16 1.8.3 MAINTENANCE RULE 1.8-17 1.8.4 INDIVIDUAL PLANT EXAMINATION 1.8-18 1.8.5 GENERIC LETTER 2008-01, MANAGING GAS ACCUMULATION 1.8-19 1.8.6 RISK INFORMED CATEGORIZATION AND TREATMENT OF 1.8-20 SSCS, 10 CFR 50.69 1.8.6.1 Introduction 1.8-20 1.8.6.2 Scope 1.8-20 1.8.6.3 SCC Categorization 1.8-20 CALVERT CLIFFS UFSAR Rev.52 1-II
CHAPTER 1 INTRODUCTION AND
SUMMARY
TABLE OF CONTENTS PAGE 1.8.6.4 Alternative Treatment 1.8-21 1.8.6.5 Periodic Reviews 1.8-21 1.
8.7 REFERENCES
1.8-21 APPENDIX 1A QUALITY ASSURANCE PROGRAM FOR DESIGN AND 1A-1 CONSTRUCTION APPENDIX 1B QUALITY ASSURANCE PROGRAM FOR THE OPERATIONS 1B-1 PHASE APPENDIX 1C AEC PROPOSED GENERAL DESIGN CRITERIA FOR 1C-1.1 NUCLEAR POWER PLANTS CALVERT CLIFFS UFSAR Rev.52 1-III
CHAPTER 1 INTRODUCTION AND
SUMMARY
LIST OF TABLES TITLE PAGE 1-1 COMPARISON OF ORIGINAL PLANT CHARACTERISTICS 1.3-2 1-2 ANALYSIS OF MODERATOR TEMPERATURE COEFFICIENTS IN 1.5-9 THE CONNECTICUT YANKEE REACTOR AT START-OF-LIFE CALVERT CLIFFS UFSAR Rev.52 1-IV
CHAPTER 1 INTRODUCTION AND
SUMMARY
LIST OF FIGURES FIGURE 1-1 SITE PLAN 1-2 CALVERT CLIFFS SITE PLAN 1-3A CIRCULATING WATER SYSTEM (Sheet 1) 1-3B CIRCULATING WATER SYSTEM (Sheet 2) 1-4 EQUIPMENT LOCATION DRAWINGS - KEY PLAN 1-5 EQUIPMENT LOCATION - AUXILIARY BUILDING PLAN AT ELEVATIONS
(-)8'0", (-)10'0" & (-)15'0" 1-6 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDING PLAN AT ELEVATIONS 5' & 10' - UNIT 1 1-7 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDINGS UNIT NO. 1 - PLAN AT ELEVATION 27'0" 1-8 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDING PLAN AT ELEVATION 45'0" - UNIT NO. 1 1-9 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDINGS UNIT NO. 1 - PLAN AT ELEVATION 69'0" 1-10 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDING PLAN AT ELEVATION 5'0" & 10'0" - UNIT NO. 2 1-11 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDINGS UNIT NO. 2 - PLAN AT ELEVATION 27'0" 1-12 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDING PLAN AT ELEVATION 45'0" - UNIT NO. 2 1-13 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDINGS PLAN ELEVATION 69' - UNIT 2 1-14 EQUIPMENT LOCATION - CONTAINMENT & AUXILIARY BUILDINGS UNIT NO. 1 - SECTION E-E 1-15 EQUIPMENT LOCATION - CONTAINMENT BUILDING UNIT NO. 2 -
SECTION F-F 1-16 EQUIPMENT LOCATION - AUXILIARY BUILDING SECTION G-G 1-17 EQUIPMENT LOCATION - TURBINE BUILDING PLAN FLOOR ELEVATION 12'0" - UNIT NO. 1 1-18 EQUIPMENT LOCATION - TURBINE BUILDING UNIT NO. 1 - PLAN FLOOR EL. 27'0", 26'0", & 23'0" 1-19 EQUIPMENT LOCATION - TURBINE BLDG. UNIT NO. 1 - PLAN FLOOR EL.
45'0" 1-20 EQUIPMENT LOCATION - TURBINE BUILDING UNIT NOS. 1 & 2 - PLAN FLOOR ELEVATION 12'0" 1-21 EQUIPMENT LOCATION - TURBINE BUILDING UNIT NOS. 1 & 2 - PLAN FLOOR EL. 29'0", 27'0", 26'4", & 23'0" 1-22 EQUIPMENT LOCATION - TURBINE BUILDING PLAN FLOOR ELEVATION 45'0" & 69'0" - UNIT NOS. 1 & 2 1-23 EQUIPMENT LOCATION - TURBINE BUILDING PLAN UNIT 2, FLOOR ELEVATION 12' CALVERT CLIFFS UFSAR Rev.52 1-V
CHAPTER 1 INTRODUCTION AND
SUMMARY
LIST OF FIGURES FIGURE 1-24 EQUIPMENT LOCATION - TURBINE BUILDING UNIT NO. 2 - PLAN FLOOR EL. 27'0", 26'4", & 26'0" 1-25 EQUIPMENT LOCATION - TURBINE BUILDING UNIT NO. 2 - PLAN FLOOR EL. 45'0" 1-26 EQUIPMENT LOCATION - TURBINE BUILDING SECTION H-H, UNIT 1 1-27 EQUIPMENT LOCATION - TURBINE BUILDING UNIT NO. 2 - SECTION "K-K" 1-28 EQUIPMENT LOCATION - WATER TREATMENT AREA, WAREHOUSE &
INTAKE STRUCTURE PLAN - UNIT NO. 1 1-29 EQUIPMENT LOCATION - WATER TREATMENT AREA, WAREHOUSE &
INTAKE STRUCTURE PLAN - UNIT 2 1-30 EQUIPMENT LOCATION - SERVICE BUILDING, WATER TREATMENT AREA
& INTAKE STRUCTURE SECTION "J-J" 1-31 EQUIPMENT LOCATION - DIESEL GENERATOR BUILDING 1, ELEVATION 356 1-32 EQUIPMENT LOCATION - DIESEL GENERATOR BUILDING 1, ELEVATION 456 1-33 EQUIPMENT LOCATION - DIESEL GENERATOR BUILDING 1, ELEVATION 666 1-34 EQUIPMENT LOCATION - DIESEL GENERATOR BUILDING 1, ELEVATION 806 1-35 EQUIPMENT LOCATION - DIESEL GENERATOR BUILDING 2, ELEVATION 356 1-36 EQUIPMENT LOCATION - DIESEL GENERATOR BUILDING 2, ELEVATION 456 1-37 EQUIPMENT LOCATION - DIESEL GENERATOR BUILDING 2, ELEVATION 666 CALVERT CLIFFS UFSAR Rev.52 1-VI
CHAPTER 1 INTRODUCTION AND
SUMMARY
LIST OF ACRONYMS ACRS Advisory Committee on Reactor Safeguards AEC Atomic Energy Commission AFW Auxiliary Feedwater AHU Air Handling Unit ASTM American Society for Testing and Materials BGE Baltimore Gas and Electric Company CCNPP Calvert Cliffs Nuclear Power Plant CE Combustion Engineering, Inc.
CEA Control Element Assembly CEDM Control Element Drive Mechanism CREVS Control Room Emergency Ventilation System CSS Containment Spray System CVCS Chemical and Volume Control System DBE Design Basis Event DNB Departure from Nucleate Boiling DNBR Departure from Nucleate Boiling Ratio ECC Emergency Core Cooling ECCS Emergency Core Cooling System EDG Emergency Diesel Generator EOP Emergency Operating Procedure ESF Engineered Safety Feature FSAR Final Safety Analysis Report GSI Generic Safety Issue HVAC Heating, Ventilation, and Air Conditioning HEPA High Efficiency Particulate Air HPSI High Pressure Safety Injection ITS Improved Technical Specifications LOCA Loss-of-Coolant Accident LPSI Low Pressure Safety Injection MTC Moderator Temperature Coefficient NDTT Nil-Ductility Transition Temperature NRC Nuclear Regulatory Commission NSSS Nuclear Steam Supply System NUMARC Nuclear Management & Resources Council PORV Power-Operated Relief Valve PSAR Preliminary Safety Analysis Report RCP Reactor Coolant Pump RCS Reactor Coolant System RPS Reactor Protective System RVCH Reactor Vessel Closure Head RWT Refueling Water Tank SACM Societe Alsacienne De Constructions Mecaniques De Mulhouse SBO Station Blackout CALVERT CLIFFS UFSAR Rev.52 1-VII
CHAPTER 1 INTRODUCTION AND
SUMMARY
LIST OF ACRONYMS SER Safety Evaluation Report SG Steam Generator SIT Safety Injection Tank SRO Senior Reactor Operator TMI Three Mile Island TRM Technical Requirements Manual VCT Volume Control Tank CALVERT CLIFFS UFSAR Rev.52 1-VIII