ML14010A291
| ML14010A291 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 12/30/2013 |
| From: | Energy Northwest |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML14010A476 | List:
|
| References | |
| GO2-13-174 | |
| Download: ML14010A291 (5) | |
Text
COLUMBIA GENERATING STATION Amendment 58 FINAL SAFETY ANALYSIS REPORT December 2005 GENERAL TABLE OF CONTENTS LDCN-05-050 i
Chapter 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 1.1 Introduction 1.2 General Plant Description 1.3 Comparison Tables 1.4 Identification of Agents and Contractors 1.5 Requirements for Further Technical Information 1.6 Material Incorporated by Reference 1.7 Acronyms 1.8 Conformance to NRC Regulatory Guides Chapter 2 SITE CHARACTERISTICS 2.1 Geography and Demography 2.2 Nearby Industrial, Transportation, and Military Facilities 2.3 Meteorology 2.4 Hydrology Engineering 2.5 Geology, Seismology, and Geotechnical Engineering Chapter 3 DESIGN CRITERIA - STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS 3.1 Conformance with NRC General Design Criteria 3.2 Classification of Structures, Components, and Systems 3.3 Wind and Tornado Loadings 3.4 Water Level (Flood) Design 3.5 Missile Protection 3.6 Protection Against Dynamic Effects Associated with the Postulated Rupture of Piping 3.7 Seismic Design 3.8 Design of Seismic Category I Structures 3.9 Mechanical Systems and Components 3.10 Seismic and Dynamic Qualification of Safety-Related Instrumentation and Electrical Equipment 3.11 Environmental Design of Mechanical and Electrical Equipment 3.12 Computer Programs for Structural Analysis and Design 3A Plant Design Assessment Report (DAR) for SRV and LOCA Loads
COLUMBIA GENERATING STATION Amendment 58 FINAL SAFETY ANALYSIS REPORT December 2005 GENERAL TABLE OF CONTENTS ii Chapter 4 REACTOR 4.1 Summary Description 4.2 Fuel System Design 4.3 Nuclear Design 4.4 Thermal-Hydraulic Design 4.5 Reactor Materials 4.6 Functional Design of Reactivity Control Systems Chapter 5 REACTOR COOLANT SYSTEMS AND CONNECTED SYSTEMS 5.1 Summary Description 5.2 Integrity of Reactor Coolant Pressure Boundary 5.3 Reactor Vessel 5.4 Component and Subsystem Design Chapter 6 ENGINEERED SAFETY FEATURES 6.1 Engineered Safety Feature Materials 6.2 Containment Systems 6.3 Emergency Core Cooling System 6.4 Habitability Systems 6.5 Fission Product Removal and Control Systems 6.6 Inservice Inspection of ASME Code Class 2 and Class 3 Components 6.7 Main Steam Isolation Valve Leakage Control System
COLUMBIA GENERATING STATION Amendment 58 FINAL SAFETY ANALYSIS REPORT December 2005 GENERAL TABLE OF CONTENTS (Continued) iii Chapter 7 INSTRUMENTATION AND CONTROL SYSTEMS 7.1 Introduction 7.2 Reactor Protection (Trip) System 7.3 Engineered Safety Feature Systems 7.4 Systems Required for Safe Shutdown 7.5 Safety-Related Display Instrumentation 7.6 All Other Instrumentation Systems Required for Safety 7.7 Control Systems Not Required for Safety Chapter 8 ELECTRIC POWER 8.1 Introduction 8.2 Offsite Power System 8.3 Onsite Power Systems 8A Station Blackout Chapter 9 AUXILIARY SYSTEMS 9.1 Fuel Storage and Handling 9.2 Water Systems 9.3 Process Auxiliaries 9.4 Heating, Ventilating, and Air Conditioning Systems 9.5 Other Auxiliary Systems Chapter 10 STEAM AND POWER CONVERSION SYSTEM 10.1 Summary Description 10.2 Turbine Generator 10.3 Main Steam Supply System 10.4 Other Features of Steam and Power Conversion System
COLUMBIA GENERATING STATION Amendment 58 FINAL SAFETY ANALYSIS REPORT December 2005 GENERAL TABLE OF CONTENTS (Continued) iv Chapter 11 RADIOACTIVE WASTE MANAGEMENT 11.1 Source Terms 11.2 Liquid Waste Management System 11.3 Gaseous Waste Management Systems 11.4 Solid Waste Management System 11.5 Process and Effluent Radiological Monitoring and Sampling Systems 11.6 Postaccident Sampling System Chapter 12 RADIATION PROTECTION 12.1 Ensuring that Occupational Radiation Exposures and Radiation Exposures to Members of the Public are As Low As Is Reasonably Achievable 12.2 Radiation Sources 12.3 Radiation Protection Design Features 12.4 Dose Assessment 12.5 Radiation Protection Program Chapter 13 CONDUCT OF OPERATIONS 13.1 Organization Structure 13.2 Training 13.3 Emergency Planning 13.4 Review and Audit 13.5 Plant Procedures 13.6 Industrial Security Chapter 14 INITIAL TEST PROGRAM 14.1 Specific Information Included in Preliminary Safety Analysis Reports 14.2 System Lineup, Preoperational, and Initial Startup Test Program
COLUMBIA GENERATING STATION Amendment 62 FINAL SAFETY ANALYSIS REPORT December 2013 GENERAL TABLE OF CONTENTS (Continued) v Chapter 15 ACCIDENT ANALYSES 15.0 General 15.1 Decrease in Reactor Coolant Temperature 15.2 Increase in Reactor Pressure 15.3 Decrease in Reactor Coolant System Flow Rate 15.4 Reactivity and Power Distribution Anomalies 15.5 Increase in Reactor Coolant Inventory 15.6 Decrease in Reactor Coolant Inventory 15.7 Radioactive Release from Subsystems and Components 15.8 Anticipated Transients without Scram Chapter 16 TECHNICAL SPECIFICATIONS (Separate Volume)
Chapter 17 QUALITY ASSURANCE 17.1 Quality Assurance During the Design and Construction Phases 17.2 Quality Assurance During the Operations Phase APPENDIXES A
Supplement Aging Management Programs and Activities Credited for Columbia License Renewal B
Response to Regulatory Issues Resulting from TMI-2 F
Fire Protection Evaluation I
Licensing Review Group Issues J
Shielding Evaluation Report