ML12011A150

Amendment 61 to Final Safety Analysis Report, General Table of Contents

ML12011A150
Person / Time
Site:	Columbia
Issue date:	12/14/2011
From:	Energy Northwest
To:	Office of Nuclear Reactor Regulation
References
GO2-11-201
Download: ML12011A150 (5)

Text

C OLUMBIA G ENERATING S TATION Amendment 58 F INAL S AFETY A NALYSIS R EPORT 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 Furthe r Technical Information 1.6 Material Incorporated by Reference

1.8 Conformance

to NRC Regulatory Guides

Chapter 2 SITE CHARACTERISTICS

2.1 Geography

a nd Demography 2.2 Nearby Industrial, Transpor tation, and Military Facilities

2.4 Hydrology

Engineering 2.5 Geology, Seismology, a nd Geotechnical Engineering Chapter 3 DESIGN CRITERIA - STRUCTURES, COMPONENTS, EQUIPMENT, AND SYSTEMS

3.1 Conformance

with NRC General Design Criteria

3.2 Classification

of Structur es, 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 Qualif ication of Safety-Related In strumentation and Electrical Equipment 3.11 Environmental Design of Mech anical and Electrical Equipment 3.12 Computer Programs for Stru ctural Analysis and Design 3A Plant Design Assessment Report (D AR) for SRV and LOCA Loads

C OLUMBIA G ENERATING S TATION Amendment 58 F INAL S AFETY A NALYSIS R EPORT 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 C ode Class 2 and Class 3 Components 6.7 Main Steam Isolation Valve Leakage Control System

C OLUMBIA G ENERATING S TATION Amendment 58 F INAL S AFETY A NALYSIS R EPORT December 2005

GENERAL TABLE OF CONTENTS (Continued)

iii Chapter 7 INSTRUMENTATION AND CONTROL SYSTEMS

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

8.2 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

C OLUMBIA G ENERATING S TATION Amendment 58 F INAL S AFETY A NALYSIS R EPORT 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 Protec tion 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 Pr eliminary Safety Analysis Reports 14.2 System Lineup, Preoperational, and Initial Startup Test Program

C OLUMBIA G ENERATING S TATION Amendment 58 F INAL S AFETY A NALYSIS R EPORT December 2005

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 Duri ng the Operations Phase APPENDIXES

B Response to Regulatory Issues Resulting from TMI-2 F Fire Protection Evaluation I Licensing Review Group Issues J Shielding Evaluation Report