ML110040467
| ML110040467 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 12/22/2010 |
| From: | Arent G Tennessee Valley Authority |
| To: | Document Control Desk, Office of New Reactors |
| Spink T | |
| References | |
| BELLEFONTE.P02.NP, BELLEFONTE.P02.NP.3, TENNVALLEY, TENNVALLEY.SUBMISSION.6, +reviewedmmc1 | |
| Download: ML110040467 (9) | |
Text
Bellefonte Nuclear Plant Units 3 & 4 COL Application Part 2 Final Safety Analysis Report Revision 3
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR Revision 3 i
MASTER TABLE OF CONTENTS Section Title Page CHAPTER 1 INTRODUCTION AND GENERAL DESCRIPTION OF THE PLANT
1.1 INTRODUCTION
................................................................................. 1.1-1 1.2 GENERAL PLANT DESCRIPTION..................................................... 1.2-1 1.3 COMPARISONS WITH SIMILAR FACILITY DESIGNS...................... 1.3-1 1.4 IDENTIFICATION OF AGENTS AND CONTRACTORS..................... 1.4-1 1.5 REQUIREMENTS FOR FURTHER TECHNICAL INFORMATION..... 1.5-1 1.6 MATERIAL REFERENCED................................................................. 1.6-1 1.7 DRAWINGS AND OTHER DETAILED INFORMATION...................... 1.7-1 1.8 INTERFACES FOR STANDARD DESIGN.......................................... 1.8-1 1.9 COMPLIANCE WITH REGULATORY CRITERIA............................... 1.9-1 1.10 NUCLEAR POWER PLANTS TO BE OPERATED ON MULTI-UNIT SITES........................................................................... 1.10-1 APP. 1A CONFORMANCE WITH REGULATORY GUIDES.................1A-1 APP. 1B SEVERE ACCIDENT MITIGATION DESIGN ALTERNATIVES......................................................................1B-1 APP. 1AA CONFORMANCE WITH REGULATORY GUIDES.............. 1AA-1 CHAPTER 2 SITE CHARACTERISTICS 2.0 SITE CHARACTERISTICS.................................................................. 2.0-1 2.1 GEOGRAPHY AND DEMOGRAPHY.................................................. 2.1-1 2.2 NEARBY INDUSTRIAL, TRANSPORTATION, AND MILITARY FACILITIES......................................................................................... 2.2-1 2.3 METEOROLOGY................................................................................ 2.3-1 2.4 HYDROLOGIC ENGINEERING.......................................................... 2.4-1 2.5 GEOLOGY, SEISMOLOGY, AND GEOTECHNICAL INFORMATION................................................................................... 2.5-1 APP. 2AA EARTHQUAKE CATALOG.................................................. 2AA-1 APP. 2BB GEOTECHNICAL BORING LOGS...................................... 2BB-1 APP. 2CC TEST PIT LOGS..................................................................2CC-1 APP. 2DD ATMOSPHERIC DISPERSION AND DEPOSITION FACTORS BASED ON TWO YEARS OF ON SITE METEOROLOGICAL DATA................................................2DD-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR MASTER TABLE OF CONTENTS (Continued)
Section Title Page Revision 3 ii CHAPTER 3 DESIGN OF STRUCTURES, COMPONENTS, EQUIPMENT AND SYSTEMS 3.1 CONFORMANCE WITH NUCLEAR REGULATORY COMMISSION GENERAL DESIGN CRITERIA........................................................... 3.1-1 3.2 CLASSIFICATION OF STRUCTURES, COMPONENTS, AND SYSTEMS........................................................................................... 3.2-1 3.3 WIND AND TORNADO LOADINGS.................................................... 3.3-1 3.4 WATER LEVEL (FLOOD) DESIGN..................................................... 3.4-1 3.5 MISSILE PROTECTION...................................................................... 3.5-1 3.6 PROTECTION AGAINST THE DYNAMIC EFFECTS ASSOCIATED WITH THE POSTULATED RUPTURE OF PIPING............................. 3.6-1 3.7 SEISMIC DESIGN............................................................................... 3.7-1 3.8 DESIGN OF CATEGORY I STRUCTURES........................................ 3.8-1 3.9 MECHANICAL SYSTEMS AND COMPONENTS............................... 3.9-1 3.10 SEISMIC AND DYNAMIC QUALIFICATION OF SEISMIC CATEGORY I MECHANICAL AND ELECTRICAL EQUIPMENT...... 3.10-1 3.11 ENVIRONMENTAL QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT.............................................................. 3.11-1 APP. 3A HVAC DUCTS AND DUCT SUPPORTS.................................3A-1 APP. 3B LEAK-BEFORE-BREAK EVALUATION OF THE AP1000 PIPING.......................................................................3B-1 APP. 3C REACTOR COOLANT LOOP ANALYSIS METHODS............3C-1 APP. 3D METHODOLOGY FOR QUALIFYING AP1000 SAFETY-RELATED ELECTRICAL AND MECHANICAL EQUIPMENT.3D-1 APP. 3E HIGH-ENERGY PIPING IN THE NUCLEAR ISLAND.............3E-1 APP. 3F CABLE TRAYS AND CABLE TRAY SUPPORTS...................3F-1 APP. 3G NUCLEAR ISLAND SEISMIC ANALYSES............................. 3G-1 APP. 3H AUXILIARY AND SHIELD BUILDING CRITICAL SECTIONS.3H-1 APP. 3I EVALUATION FOR HIGH FREQUENCY SEISMIC INPUT..... 3I-1 CHAPTER 4 REACTOR 4.1
SUMMARY
DESCRIPTION................................................................. 4.1-1 4.2 FUEL SYSTEM DESIGN..................................................................... 4.2-1 4.3 NUCLEAR DESIGN............................................................................. 4.3-1 4.4 THERMAL AND HYDRAULIC DESIGN.............................................. 4.4-1 4.5 REACTOR MATERIALS...................................................................... 4.5-1 4.6 FUNCTIONAL DESIGN OF REACTIVITY CONTROL SYSTEMS...... 4.6-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR MASTER TABLE OF CONTENTS (Continued)
Section Title Page Revision 3 iii CHAPTER 5 REACTOR COOLANT SYSTEM AND CONNECTED SYSTEMS 5.1
SUMMARY
DESCRIPTION................................................................. 5.1-1 5.2 INTEGRITY OF REACTOR COOLANT PRESSURE BOUNDARY.... 5.2-1 5.3 REACTOR VESSEL............................................................................ 5.3-1 5.4 COMPONENT AND SUBSYSTEM DESIGN....................................... 5.4-1 CHAPTER 6 ENGINEERED SAFETY FEATURES 6.0 ENGINEERED SAFETY FEATURES.................................................. 6.0-1 6.1 ENGINEERED SAFETY FEATURES MATERIALS............................ 6.1-1 6.2 CONTAINMENT SYSTEMS................................................................ 6.2-1 6.3 PASSIVE CORE COOLING SYSTEM................................................ 6.3-1 6.4 HABITABILITY SYSTEMS.................................................................. 6.4-1 6.5 FISSION PRODUCT REMOVAL AND CONTROL SYSTEMS........... 6.5-1 6.6 INSERVICE INSPECTION OF CLASS 2, 3, AND MC COMPONENTS................................................................................... 6.6-1 APP. 6A FISSION PRODUCT DISTRIBUTION IN THE AP1000 POST-DESIGN BASIS ACCIDENT CONTAINMENT ATMOSPHERE........................................................................6A-1 CHAPTER 7 INSTRUMENTATION AND CONTROLS
7.1 INTRODUCTION
................................................................................. 7.1-1 7.2 REACTOR TRIP.................................................................................. 7.2-1 7.3 ENGINEERED SAFETY FEATURES.................................................. 7.3-1 7.4 SYSTEMS REQUIRED FOR SAFE SHUTDOWN.............................. 7.4-1 7.5 SAFETY-RELATED DISPLAY INFORMATION.................................. 7.5-1 7.6 INTERLOCK SYSTEMS IMPORTANT TO SAFETY........................... 7.6-1 7.7 CONTROL AND INSTRUMENTATION SYSTEMS............................. 7.7-1 CHAPTER 8 ELECTRIC POWER
8.1 INTRODUCTION
................................................................................. 8.1-1 8.2 OFFSITE POWER SYSTEM............................................................... 8.2-1 8.3 ONSITE POWER SYSTEMS.............................................................. 8.3-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR MASTER TABLE OF CONTENTS (Continued)
Section Title Page Revision 3 iv CHAPTER 9 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING..................................................... 9.1-1 9.2 WATER SYSTEMS............................................................................. 9.2-1 9.3 PROCESS AUXILIARIES.................................................................... 9.3-1 9.4 AIR-CONDITIONING, HEATING, COOLING, AND VENTILATION SYSTEM.............................................................................................. 9.4-1 9.5 OTHER AUXILIARY SYSTEMS.......................................................... 9.5-1 APP. 9A FIRE PROTECTION ANALYSIS.............................................9A-1 CHAPTER 10 STEAM AND POWER CONVERSION 10.1
SUMMARY
DESCRIPTION............................................................... 10.1-1 10.2 TURBINE-GENERATOR................................................................... 10.2-1 10.3 MAIN STEAM SUPPLY SYSTEM..................................................... 10.3-1 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM................................................................... 10.4-1 CHAPTER 11 RADIOACTIVE WASTE MANAGEMENT 11.1 SOURCE TERMS.............................................................................. 11.1-1 11.2 LIQUID WASTE MANAGEMENT SYSTEMS.................................... 11.2-1 11.3 GASEOUS WASTE MANAGEMENT SYSTEM................................ 11.3-1 11.4 SOLID WASTE MANAGEMENT....................................................... 11.4-1 11.5 RADIATION MONITORING............................................................... 11.5-1 CHAPTER 12 RADIATION PROTECTION 12.1 ASSURING THAT OCCUPATIONAL RADIATION EXPOSURES ARE AS-LOW-AS-REASONABLY ACHIEVABLE (ALARA)..................................................................... 12.1-1 12.2 RADIATION SOURCES.................................................................... 12.2-1 12.3 RADIATION PROTECTION DESIGN FEATURES........................... 12.3-1 12.4 DOSE ASSESSMENT....................................................................... 12.4-1 12.5 HEALTH PHYSICS FACILITIES DESIGN......................................... 12.5-1 APP. 12AA RADIATION PROTECTION PROGRAM DESCRIPTION... 12AA-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR MASTER TABLE OF CONTENTS (Continued)
Section Title Page Revision 3 v
CHAPTER 13 CONDUCT OF OPERATIONS 13.1 ORGANIZATIONAL STRUCTURE OF APPLICANT......................... 13.1-1 13.2 TRAINING......................................................................................... 13.2-1 13.3 EMERGENCY PLANNING................................................................ 13.3-1 13.4 OPERATIONAL PROGRAMS........................................................... 13.4-1 13.5 PLANT PROCEDURES..................................................................... 13.5-1 13.6 SECURITY........................................................................................ 13.6-1 13.7 FITNESS FOR DUTY........................................................................ 13.7-1 APP. 13AA CONSTRUCTION-RELATED ORGANIZATION................. 13AA-1 CHAPTER 14 INITIAL TEST PROGRAM 14.1 SPECIFIC INFORMATION TO BE INCLUDED IN PRELIMINARY/
FINAL SAFETY ANALYSIS REPORTS............................................ 14.1-1 14.2 SPECIFIC INFORMATION TO BE INCLUDED IN STANDARD SAFETY ANALYSIS REPORTS........................................................ 14.2-1 14.3 CERTIFIED DESIGN MATERIAL...................................................... 14.3-1 14.4 COMBINED LICENSE APPLICANT RESPONSIBILITIES................ 14.4-1 CHAPTER 15 ACCIDENT ANALYSES 15.0 ACCIDENT ANALYSES.................................................................... 15.0-1 15.1 INCREASE IN HEAT REMOVAL FROM THE PRIMARY SYSTEM............................................................................................ 15.1-1 15.2 DECREASE IN HEAT REMOVAL BY THE SECONDARY SYSTEM............................................................................................ 15.2-1 15.3 DECREASE IN REACTOR COOLANT SYSTEM FLOW RATE....... 15.3-1 15.4 REACTIVITY AND POWER DISTRIBUTION ANOMALIES.............. 15.4-1 15.5 INCREASE IN REACTOR COOLANT INVENTORY......................... 15.5-1 15.6 DECREASE IN REACTOR COOLANT INVENTORY....................... 15.6-1 15.7 RADIOACTIVE RELEASE FROM A SUBSYSTEM OR COMPONENT............................................................................. 15.7-1 15.8 ANTICIPATED TRANSIENTS WITHOUT SCRAM........................... 15.8-1 APP. 15A EVALUATION MODELS AND PARAMETERS FOR ANALYSIS OF RADIOLOGICAL CONSEQUENCES OF ACCIDENTS...........................................................................15A-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR MASTER TABLE OF CONTENTS (Continued)
Section Title Page Revision 3 vi APP. 15B REMOVAL OF AIRBORNE ACTIVITY FROM THE CONTAINMENT ATMOSPHERE FOLLOWING A LOCA......15B-1 CHAPTER 16 TECHNICAL SPECIFICATIONS 16.1 TECHNICAL SPECIFICATIONS....................................................... 16.1-1 16.2 DESIGN RELIABILITY ASSURANCE PROGRAM........................... 16.2-1 16.3 INVESTMENT PROTECTION........................................................... 16.3-1 CHAPTER 17 QUALITY ASSURANCE 17.1 QUALITY ASSURANCE DURING THE DESIGN AND CONSTRUCTION PHASES.............................................................. 17.1-1 17.2 QUALITY ASSURANCE DURING THE OPERATIONS PHASE....... 17.2-1 17.3 QUALITY ASSURANCE DURING DESIGN, PROCUREMENT, FABRICATION, INSPECTION, AND/OR TESTING OF NUCLEAR POWER PLANT ITEMS.................................................................... 17.3-1 17.4 DESIGN RELIABILITY ASSURANCE PROGRAM........................... 17.4-1 17.5 QUALITY ASSURANCE PROGRAM DESCRIPTION -
NEW LICENSE APPLICANTS.......................................................... 17.5-1 17.6 MAINTENANCE RULE PROGRAM................................................. 17.6-1 17.7 COMBINED LICENSE INFORMATION ITEMS................................. 17.7-1
17.8 REFERENCES
.................................................................................. 17.8-1 CHAPTER 18 HUMAN FACTORS ENGINEERING 18.1 OVERVIEW....................................................................................... 18.1-1 18.2 HUMAN FACTORS ENGINEERING PROGRAM MANAGEMENT... 18.2-1 18.3 OPERATING EXPERIENCE REVIEW.............................................. 18.3-1 18.4 FUNCTIONAL REQUIREMENTS ANALYSIS AND ALLOCATION... 18.4-1 18.5 AP1000 TASK ANALYSIS IMPLEMENTATION PLAN..................... 18.5-1 18.6 STAFFING......................................................................................... 18.6-1 18.7 INTEGRATION OF HUMAN RELIABILITY ANALYSIS WITH HUMAN FACTORS ENGINEERING................................................. 18.7-1 18.8 HUMAN SYSTEM INTERFACE DESIGN......................................... 18.8-1 18.9 PROCEDURE DEVELOPMENT...................................................... 18.9-1 18.10 TRAINING PROGRAM DEVELOPMENT........................................ 18.10-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR MASTER TABLE OF CONTENTS (Continued)
Section Title Page Revision 3 vii 18.11 HUMAN FACTORS ENGINEERING VERIFICATION AND VALIDATION................................................................................... 18.11-1 18.12 INVENTORY.................................................................................... 18.12-1 18.13 DESIGN IMPLEMENTATION.......................................................... 18.13-1 18.14 HUMAN PERFORMANCE MONITORING...................................... 18.14-1 CHAPTER 19 PROBABILISTIC RISK ASSESSMENT
19.1 INTRODUCTION
............................................................................... 19.1-1 19.2 INTERNAL INITIATING EVENTS...................................................... 19.2-1 19.3 MODELING OF SPECIAL INITIATORS............................................ 19.3-1 19.4 EVENT TREE MODELS.................................................................... 19.4-1 19.5 SUPPORT SYSTEMS....................................................................... 19.5-1 19.6 SUCCESS CRITERIA ANALYSIS..................................................... 19.6-1 19.7 FAULT TREE GUIDELINES.............................................................. 19.7-1 19.8 PASSIVE CORE COOLING SYSTEM - PASSIVE RESIDUAL HEAT REMOVAL.............................................................................. 19.8-1 19.9 PASSIVE CORE COOLING SYSTEM - CORE MAKEUP TANKS.... 19.9-1 19.10 PASSIVE CORE COOLING SYSTEM - ACCUMULATOR............. 19.10-1 19.11 PASSIVE CORE COOLING SYSTEM - AUTOMATIC DEPRESSURIZATION SYSTEM.................................................... 19.11-1 19.12 PASSIVE CORE COOLING SYSTEM - IN-CONTAINMENT REFUELING WATER STORAGE TANK......................................... 19.12-1 19.13 PASSIVE CONTAINMENT COOLING............................................ 19.13-1 19.14 MAIN AND STARTUP FEEDWATER SYSTEM.............................. 19.14-1 19.15 CHEMICAL AND VOLUME CONTROL SYSTEM........................... 19.15-1 19.16 CONTAINMENT HYDROGEN CONTROL SYSTEM...................... 19.16-1 19.17 NORMAL RESIDUAL HEAT REMOVAL SYSTEM......................... 19.17-1 19.18 COMPONENT COOLING WATER SYSTEM.................................. 19.18-1 19.19 SERVICE WATER SYSTEM........................................................... 19.19-1 19.20 CENTRAL CHILLED WATER SYSTEM.......................................... 19.20-1 19.21 AC POWER SYSTEM..................................................................... 19.21-1 19.22 CLASS 1E DC & UPS SYSTEM...................................................... 19.22-1 19.23 NON-CLASS 1E DC & UPS SYSTEM............................................ 19.23-1 19.24 CONTAINMENT ISOLATION.......................................................... 19.24-1 19.25 COMPRESSED AND INSTRUMENT AIR SYSTEM....................... 19.25-1 19.26 PROTECTION AND SAFETY MONITORING SYSTEM................. 19.26-1 19.27 DIVERSE ACTUATION SYSTEM................................................... 19.27-1 19.28 PLANT CONTROL SYSTEM........................................................... 19.28-1 19.29 COMMON CAUSE ANALYSIS........................................................ 19.29-1 19.30 HUMAN RELIABILITY ANALYSIS.................................................. 19.30-1 19.31 OTHER EVENT TREE NODE PROBABILITIES............................. 19.31-1
Bellefonte Nuclear Plant, Units 3 & 4 COL Application Part 2, FSAR MASTER TABLE OF CONTENTS (Continued)
Section Title Page Revision 3 viii 19.32 DATA ANALYSIS AND MASTER DATA BANK.............................. 19.32-1 19.33 FAULT TREE AND CORE DAMAGE QUANTIFICATION............... 19.33-1 19.34 SEVERE ACCIDENT PHENOMENA TREATMENT...................... 19.34-1 19.35 CONTAINMENT EVENT TREE ANALYSIS................................... 19.35-1 19.36 REACTOR COOLANT SYSTEM DEPRESSURIZATION.............. 19.36-1 19.37 CONTAINMENT ISOLATION......................................................... 19.37-1 19.38 REACTOR VESSEL REFLOODING.............................................. 19.38-1 19.39 IN-VESSEL RETENTION OF MOLTEN CORE DEBRIS............... 19.39-1 19.40 PASSIVE CONTAINMENT COOLING........................................... 19.40-1 19.41 HYDROGEN MIXING AND COMBUSTION ANALYSIS................. 19.41-1 19.42 CONDITIONAL CONTAINMENT FAILURE PROBABILITY DISTRIBUTION............................................................................... 19.42-1 19.43 RELEASE FREQUENCY QUANTIFICATION................................. 19.43-1 19.44 MAAP4.0 CODE DESCRIPTION AND AP1000 MODELING.......... 19.44-1 19.45 FISSION PRODUCT SOURCE TERMS......................................... 19.45-1 19.46 NOT USED...................................................................................... 19.46-1 19.47 NOT USED...................................................................................... 19.47-1 19.48 NOT USED...................................................................................... 19.48-1 19.49 OFFSITE DOSE EVAULATION...................................................... 19.49-1 19.50 IMPORTANCE AND SENSITIVITY ANALYSIS.............................. 19.50-1 19.51 UNCERTAINTY ANALYSIS............................................................ 19.51-1 19.52 NOT USED...................................................................................... 19.52-1 19.53 NOT USED...................................................................................... 19.53-1 19.54 LOW POWER AND SHUTDOWN PRA ASSESSMENT................. 19.54-1 19.55 SEISMIC MARGIN ANALYSIS........................................................ 19.55-1 19.56 PRA INTERNAL FLOODING ANALYSIS........................................ 19.56-1 19.57 INTERNAL FIRE ANALYSIS........................................................... 19.57-1 19.58 WINDS, FLOODS, AND OTHER EXTERNAL EVENTS................. 19.58-1 19.59 PRA RESULTS AND INSIGHTS..................................................... 19.59-1 APP. 19A THERMAL HYDRAULIC ANALYSIS TO SUPPORT SUCCESS CRITERIA............................................................19A-1 APP. 19B EX-VESSEL SEVERE ACCIDENT PHENOMENA................19B-1 APP. 19C ADDITIONAL ASSESSMENT OF AP1000 DESIGN FEATURES............................................................................19C-1 APP. 19D EQUIPMENT SURVIVABILITY ASSESSMENT....................19D-1 APP. 19E SHUTDOWN EVALUATION.................................................19E-1 APP. 19F MALEVOLENT AIRCRAFT IMPACT.....................................19F-1