Format and Content of the Safety Analysis Report for Nuclear Power Plants : Specific Safety Guide.

Format:

Book

Author/Creator:

IAEA.

Series:

IAEA Safety Standards

IAEA Safety Standards ; v.SSG-61

Language:

English

Subjects (All):

Nuclear power plants--Design and construction.

Nuclear power plants--Safety measures.

Nuclear reactors--Safety measures.

Physical Description:

1 online resource (215 pages)

Edition:

1st ed.

Place of Publication:

Havertown : International Atomic Energy Agency, 2021.

Summary:

This Safety Guide provides recommendations on the structure and content of the safety analysis report to be submitted by the operating organization to the regulatory body for authorization of the siting, construction, commissioning, operation and decommissioning of a nuclear power plant. It is intended to facilitate both the development of the safety analysis report by the operating organization and the checking of its completeness and adequacy by the regulatory body. The publication is a revision of IAEA Safety Standards Series No. GS-G-4.1, Format and Content of the Safety Analysis Report for Nuclear Power Plants, which it supersedes. The revision reflects feedback experience from the Fukushima Daiichi accident and the subsequent stress tests performed. It also describes good practices and experience from the use of safety analysis reports for newly built nuclear power plants in different States and informs on recent progress made in approaches to safety assessment.

Contents:

Intro

1. Introduction

Background

Objective

Scope

Structure

2. General considerations

Role of the safety analysis report

Safety rules of different origins

Structure of the safety analysis report for various stages of the lifetime of a nuclear power plant

Structure of the safety analysis report

Unified description of the design of plant structures, systems and components

Use, review and updating of the safety analysis report during plant operation

Formal aspects regarding the documentation of the safety analysis report

Relationship of the safety analysis report to other licensing documents

Treatment of sensitive information

Structure of the safety analysis report for different types of nuclear installation

3. Content and structure of individual chapters of the safety analysis report

Chapter 1: Introduction and general considerations

Introduction

Project implementation

Identification of interested parties regarding design, construction and operation

Information on the plant layout and other aspects

General plant description

Comparison with other plant designs

Drawings and other more detailed information

Modes of normal operation of the plant

Principles of safety management

Additional supporting or complementary documents to the safety analysis report

Conformance with applicable regulations, codes and standards

Chapter 2: Site characteristics

Geography and demography

Evaluation of site specific hazards

Proximity of industrial, transportation and other facilities

Activities at the plant site that might influence the safety of the plant

Hydrology

Meteorology

Geology, seismology and geotechnical engineering

Site characteristics and the potential effects of the nuclear power plant in the region.

Radiological conditions due to external sources

Site related issues in emergency preparedness and accident management

Monitoring of site related parameters

Chapter 3: Safety objectives and design rules for structures, systems and components

General safety design basis

Classification of structures, systems and components

Protection against external hazards

Protection against internal hazards

General design aspects for civil engineering works of safety classified buildings and civil engineering structures

General design aspects for mechanical systems and components

General design aspects for instrumentation and control systems and components

General design aspects for electrical systems and components

Equipment qualification

In-service monitoring, tests, maintenance and inspections

Compliance with national and international standards

Chapter 4: Reactor

Summary description

Fuel design

Nuclear design

Thermohydraulic design

Design of the reactor control, shutdown and monitoring systems

Evaluation of the combined performance of reactivity control systems

Core components

Chapter 5: Reactor coolant system and associated systems

Materials

Reactor coolant system and reactor coolant pressure boundary

Reactor vessel

Reactor coolant pumps or recirculation pumps

Primary heat exchangers (steam generators) in pressurized water reactors

Reactor coolant piping

Reactor pressure control system

Reactor coolant system component supports and restraints

Reactor coolant system and connected system valves

Access and equipment requirements for in-service inspection and maintenance

Reactor auxiliary systems

Chapter 6: Engineered safety features

Emergency core cooling systems and residual heat removal systems

Emergency reactivity control system.

Safety features for stabilization of the molten core

Containment and associated systems

Habitability systems

Systems for the removal and control of fission products

Other engineered safety features

Chapter 7: Instrumentation and control

Description of the instrumentation and control system

Design basis, overall architecture and functional allocation of the instrumentation and control system

General design considerations for instrumentation and control systems

Control systems important to safety

Reactor protection system

Actuation systems for engineered safety features

Systems required for safe shutdown

Information systems important to safety

Interlock systems important to safety

Diverse actuation system

Data communication systems

Instrumentation and control in the main control room

Instrumentation and control in supplementary control rooms

Emergency response facilities

Automatic control systems not important to safety

Digital instrumentation and control systems

Hazard analysis for instrumentation and control systems

Chapter 8: Electrical power

Description of the electrical power system

General principles and design approach

Electrical equipment, cables and raceways

Grounding, lightning protection and electromagnetic compatibility

Chapter 9: Auxiliary systems and civil structures

Chapter 9A: Auxiliary systems

Fuel storage and handling systems

Water systems

Process and post-accident sampling systems

Air and gas systems

Heating, ventilation and air-conditioning systems

Fire protection systems

Supporting systems for diesel generators or for gas turbine generators

Overhead lifting equipment

Miscellaneous auxiliary systems

Chapter 9B: Civil engineering works and structures

Foundations and buried structures

Reactor building.

Other structures

Chapter 10: Steam and power conversion systems

Role and general description

Main steam supply system

Feedwater systems

Turbine generator

Turbine and condenser systems

Steam generator blowdown processing system

Implementation of break preclusion for the main steam and feedwater lines

Chapter 11: Management of radioactive waste

Sources of waste

Systems for management of liquid radioactive waste

Systems for management of gaseous radioactive waste

Systems for management of solid radioactive waste

Process and effluent radiological monitoring and sampling systems, including on-site and off-site monitoring

Chapter 12: Radiation protection

Optimization of protection and safety

Sources of radiation

Design features for radiation protection

Dose constraints and dose assessment

Radiation protection programme

Chapter 13: Conduct of operations

Organizational structure of the operating organization

Training

Implementation of the operational safety programme

Plant procedures and guidelines

Nuclear safety and nuclear security interfaces

Chapter 14: Plant construction and commissioning

Specific information to be included in the safety analysis report prior to construction

Specific information to be included in the safety analysis report prior to commissioning

Chapter 15: Safety analysis

General considerations

Identification, categorization and grouping of postulated initiating events and accident scenarios

Safety objectives and acceptance criteria

Human actions

Deterministic safety analyses

Analysis of internal and external hazards

Probabilistic safety assessment

Summary of results of the safety analyses

Chapter 16: Operational limits and conditions for safe operation

Scope and application

Bases for development

Safety limits.

Requirements for limits and conditions for normal operation, surveillance and testing

Administrative requirements

Chapter 17: Management for safety

General characteristics of the management system

Specific elements of the management system

Quality management

Measurement, assessment and improvement of the management system

Fostering a culture for safety

Chapter 18: Human factors engineering

Management of the human factors engineering programme

Human factors engineering analysis

Design of the human-machine interface

Verification and validation of human factors engineering analysis results

Design implementation

Human performance monitoring

Chapter 19. Emergency preparedness and response

Arrangements for performing functions essential for the emergency response

Capability of the operating organization to assess potential radioactive releases in accident conditions

Emergency preparedness for multiple unit sites

Chapter 20: Environmental aspects

General aspects of the environmental impact assessment

Site characteristics that are important in terms of environmental impact

Plant features that minimize the environmental impact

Environmental impact of construction

Environmental impact of normal operation

Environmental impact of postulated accidents involving radioactive releases

Environmental impact of plant decommissioning

Environmental measurements and monitoring programmes

Records of radioactive releases and availability of information to the authorities and the public

Chapter 21: Decommissioning and end of life aspects

General principles and regulations

Decommissioning strategy

Facilitating decommissioning during design and operation

Decommissioning plan

Provisions for safety during decommissioning.

End of life aspects of the decommissioned site.

Notes:

Description based on publisher supplied metadata and other sources.

Other Format:

Print version: IAEA Format and Content of the Safety Analysis Report for Nuclear Power Plants

ISBN:

9789201173201

OCLC:

1319224214