LUNGMEN UNITS 1 & 2 Preliminary Safety Analysis Report

Safety Analysis Reports

Nuclear power plant operators, i.e. licensees, are expected to maintain updated safety analysis reports on how the plant is designed, operated, and maintained. Initially, a Preliminary Safety Analysis Report (PSAR) must be filed with the regulatory agency. The agency reviews the information, asks questions, and may specify changes in the plant design or additional requirements. After the plant receives its operating license, the report is often referred to as the Final (or Updated) Safety Analysis Report.

Updated copies of these reports are maintained in the local public document center, usually a public library near the plant. In the United States, the safety analyses reports are reviewed using NUREG-0800, Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, as a guide. NUREG-0800 identifies the requirements that the NRC expects the power plant operator to comply with.

No Nukes Asia Forum Japan has graciously provided the Lungmen Power Plant Units 1 and 2 Preliminary Safety Analysis Report on their website. The Table of Contents links below lead to the various chapters of the report that are available. This report is typical of the information that a utility is expected to provide to the regulatory agency. In this specific case, the Taiwan nuclear laws require compliance with the same US Nuclear Regulatory Commission standards as US plants must meet.

The table of contents below provides additional information unavailable on the linked site. Total volume of the PSAR is about 87 MB and includes hundreds of drawings and tables. Practically all the documents are PDF files that can be read using Adobe Acrobat. In a few cases, the documents are DOC files that can be read using Microsoft Word. The DOC type documents are identified in the table of contents (e.g. Chapter 11).

Complete PSAR Table of Contents and Acronyms

Preliminary Safety Analysis Report (PSAR)

Courtesy DOE and TVA

1.0 Introduction and General Description of Plant

Chapter 1 Table of Contents
Chapter 1 List of Tables Chapter 1 List of Figures
1.1 Introduction and General Description of Plant 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 GE Topical Reports and Other Documents 1.7 Drawings 1.8 Conformance with Standard Review Plan and Applicability of Codes and Standards
1A. Response to TMI Related Matters 1AA. Plant Shielding to Provide Access to Vital Areas and Protective Safety Equipment for Post-Accident Operation [II.B.2] 1B. Response to Construction Permit or Manufacturing License (CP/ML) Rule 10 CFR 50.34(f) 1C. Resolution of Applicable Unresolved Safety Issues and Generic Safety Issues 1D. Lungmen Nuclear Power Station (NPS) Station Blackout Considerations (SBO)

2.0 Site Characteristics

Chapter 2 Table of Contents
Chapter 2 List of Tables
Chapter 2 List of Figures

2.1 Geography and Demography 2.2 Nearby Industrial, Transportatioon, and Military Facilities 2.3 Meteorology
2.3 Tables
2.4 Hydrologic Engineering 2.5 Geology, Seismology, and Geotechnical Engineering 2.5 Tables
3.0 Design of Structures, Components, Equipment and Systems
Chapter 3 Table of Contents
Chapter 3 List of Tables
Chapter 3 List of Figures
3.1 Conformance with USNRC Design Criteria 3.2 Classification of Structures, Components, and Systems 3.3 Wind and Typhoon Loadings 3.4 Winter 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 Seismic Category I Structures 3.9 Mechanical Systems and Components 3.10 Seismic and Dynamic Qualification of Mechanical and Electrical Equipment 3.11 Environmental Qualification of Safety-Related Mechanical and Electrical Equipment
3A Seismic Soil Structure Interaction Analysis 3B Containment Hydrodynamic Loads 3C Computer Programs Used in the Design and Analysis of Seismic Category I Structures 3D Computer Programs Used in the Design of Components, Equipment and Structures 3E Not Used 3F Not Used 3G Response of Structures to Containment Loads 3H Design Details and Evaluation Results of Seismic Category I Structures 3I Equipment Qualification Environmental Design Criteria 3J Not Used 3K Not Used 3L Evaluation of Postulated Ruptures in High Energy Pipes 3M Intersystem Loss Of Coolant Accident For Lungmen NPS.......................................................... 3MA System Evaluation For ISLOCA

4.0 Reactor Chapter 4 Table of Contents
Chapter 4 List of Tables
Chapter 4 List of Figures
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 System
4A Typical Control Rod Patterns and Associated Power Distribution for Lungmen NPS 4B Not Used 4C Control Rod Licensing Acceptance Criteria 4D Reference Fuel Design Compliance with Acceptance Criteria

5.0 Reactor Coolant System and Connected Systems

Chapter 5 Table of Contents
Chapter 5 List of Tables
Chapter 5 List of Figures
5.1 Summary Description
5.2 Integrity of Reactor Coolant Pressure Boundary (RCPB) 5.3 Reactor Vessel 5.4 Component and Subsystem Design
5A Method of Compliance for Regulatory Guide 1.150 5B RHR Injection Flow and Heat Capacity Analysis Outlines

6 Engineered Safety Features
Chapter 6 Table of Contents Chapter 6 List of Tables
Chapter 6 List of Figures

6.0 Engineered Safety Features
6.1 Engineered Safety Feature Materials
6.2 Containment Systems
6.3 Emergency Core Cooling Systems
6.4 Habitability Systems
6.5 Fission Products Removal and Control Systems
6.6 Preservice and Inservice Inspection and Testing of Class 2 and 3 Components and Piping
6.7 High Pressure Nitrogen Gas Supply System

6A Regulatory Guide 1.52, Section C, Compliance Assessment
6B SRP 6.5.1, Table 6.5.1-1 Compliance Assessment
6C Containment Debris Protection for ECCS Strainers
6D.Additional Bypass Leakage Considerations

7.0 Instrumentation and Control Systems
Chapter 7 Table of Contents Chapter 7 List of Tables
Chapter 7 List of Figures
7.1 Introduction 7.2 Reactor Trip System - Instrumentation and Controls 7.3 Engineered Safety Feature Systems - Instrumentation and Control 7.4 Safe Shutdown Systems 7.5 Information Systems Important to Safety 7.6 Interlock Systems Important to Safety 7.7 Control Systems 7.8 Diverse Instrumentation and Control Systems 7.9 Data Communication Systems

8.0 Electric Power
Chapter 8 Table of Contents
Chapter 8 List of Tables
Chapter 8 List of Figures
Chapter 8 Proprietary Information
8.1 Introduction 8.2 Offsite Power Systems 8.3 Onsite Power Systems Figure 8.3-1 Electrical Power Distribution System Plant One Line Diagram
8A Miscellaneous Electrical Systems
8A.1 Station Grounding and Surge Protection 8A.2 Cathodic Protection 8A.3 Electric Heat Tracing 8A.4 References

9.0 Auxiliary Systems
Chapter 9 Table of Contents
Chapter 9 List of Tables Chapter 9 List of Figures
9.1 Fuel Storage and Handling 9.2 Water Systems 9.3 Process Auxiliaries 9.4 Air Conditioning, Heating, Cooling, and Ventilating Systems 9.5 Other Auxiliary Systems

9A Fire Hazard Analysis
9A.1 Introduction 9A.2 Analysis Criteria 9A.3 Analysis Approach 9A.4 Analysis 9A.4 Figures - Turbine Building Fire Protections 9A.5 Special Cases 9A.6 Fire Hazard Analysis Database 9B Summary of Analysis Supporting Fire Protection Design Requirements 9C Regulatory Guide 1.52, Section C, Compliance Assessment 9D SRP 6.5.2, Table 6.5.1-1 Compliance Assessment

10.0 Steam and Power Conversion System Chapter 10 Table of Contents Chapter 10 List of Tables
Chapter 10 List of Figures

10.1 Summary Description 10.2 Turbine Generator 10.3 Main Steam Supply System 10.4 Other Features of Steam and Power Conversion System

Heat Balance Diagrams for Design Flow and 105% Design Flow Conditions

11.0 Radioactive Waste Management
Chapter 11 Table of Contents (Word file)
Chapter 11 List of Tables (Word file) Chapter 11 List of Figures (Word file) 11.1 Source Terms
11.2 Liquid Radwaste System 11.3 Gaseous Radioactive Waste Processing System 11.4 Solid Waste Management System 11.5 Process and Effluent Radiological Monitoring and Sampling System 11.6 Offsite Radiological Monitoring Program

12.0 Radiation Protection Chapter 12 Table of Contents
Chapter 12 List of Tables Chapter 12 List of Figures
12.1 Ensuring that Occupational Radiation Exposures are ALARA 12.2 Radiation Sources 12.3 Radiation Protection Design Features 12.4 Dose Assessment 12.5 Health Physics Program
12A Calculation of Airborne Radionuclides Chapter 12 Figures (currently inaccessible - corrupted file)
13.0 Conduct of Operations
Chapter 13 Table of Contents
Chapter 13 List of Tables Chapter 13 List of Figures 13.1 Organizational Structure of Applicant 13.2 Training 13.3 Emergency Planning 13.4 Review and Audit 13.5 Plant Procedures 13.6 Physical Security
14.0 Initial Test Program
Chapter 14
Table of Contents
List of Tables
List of Figures
14.0 Initial Test Program
14.1 Specific Information to be Included in Preliminary Safety Analysis Reports
14.2 Specific Information to be Included in Final Safety Analysis Reports

15.0 Accident and Analysis

Chapter 15 Table of Contents Chapter 15 List of Tables Chapter 15 List of Figures 1 Chapter 15 List of Figures 2
15.0 Accident and Analysis General 15.1 Decrease in Reactor Coolant Temperature 15.2 Increase in Reactor Coolant 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 Component 15.8 Anticipated Transients Without Scram
15A Plant Nuclear Safety Operational Analysis (NSOA) 15B Failure Modes and Effects Analysis (FMEA) 15 C Not Used 15D Probability Analysis of Pressure Regulator Downscale Failure 15E ATWS Performance Evaluation

16.0 Preliminary Technical Specifications (PSAR)

Volume 2 Technical Specification Bases

17 Quality Assurance
Table of Contents
17.1 Introduction
17.1A Quality Assurance During Design and Construction (TPC) 17.1B Quality Assourance During Design and Construction (GE) 17.1C Quality Assurance During Design and Construction (S&W) 17.2 Quality Assurance During the Operations Phase 17.3 Reliability Assurance Program
Attachments 17A, 17B, 17C
17A TPC Nuclear Projects Quality Assurance Program
17B Quality Assurance Program for Lungmen Nuclear Power Project (GE)
17C Quality Assurance Program for Lungmen Nuclear Power Project (S&W)

18.0 Human Factors Engineering

Chapter 18
18.0 Human Factors Engineering
18.1 Introduction
18.2 Design Goals and Design Bases
18.3 Planning, Development, and Design
18.4 Control Room Standard Design Features
18.5 Remote Shutdown System
18.6 Systems Integration
18.7 Human-System Interface (HSI) Design Implementation

19.0 Severe Accident Analysis Chapter 19 Table of Contents
Chapter 19 List of Tables Chapter 19 List of Figures
19.1 Introduction 19.2 Overview 19.3 Assessment of Severe Accident Prevention 19.4 Assessment of Severe Accident Mitigation 19.5 Containment Performance 19.6 Severe Accident Management 19.7 Capacity of Primary Containment

Appendices

Appendix A Probabilistic Risk Assessment A1 Executive Summary A2 Purpose and Scope A3 Plant Design Features and Operator Actions Included in the Risk Model A4 Initiating Events and Systems Success Criteria A5 Internal Events Analysis A6 External Events Analysis A7 Shutdown Analysis A8 Systems Fault Tree Analysis A9 Level 1 PRA Input Data A10 Human Reliability Analysis A11 Core Damage Frequency A12 Accident Sequence Grouping And Containment Reliability Analysis A13 Containment Event Tree Analysis and Release Categories A14 Source Term and Containment Release Categories A15 Off-Site Consequences and Risk Analysis A16 Design Features and Operator Actions Important to Risk A17 Conclusion
AA Fault Tree Analysis AB Event Tree Analysis AC Seismic Analysis AD Probabilistic Fire Analysis AE Flooding Analysis AF Analysis of Accident Sequences Resulting From Typhoons AG Shutdown Risk AH Human Reliability Analysis AI Common Cause Failure AJ Severe Accident Phenomenology AK Source Term and Release Categories AL Consequences and Risk Analysis AM Design Features and Operator Actions Important to Risk
Appendix B Integrated Reliability Analysis Report
Appendix C Emergency Plan
Appendix D Backend Program
Appendix E Experience Feedback