IAEA安全标准目录-中文 - 图文

Status on 20 August 2015 - Double-Click on the relevant cover page to open the corresponding pdf file – You may also search for words or SS number in the title

Draft standards recently endorsed by the CSS are also available at the following address: http://www-ns.iaea.org/committees/css/default.asp?fd=1084&dt=0 The Standards under revision are also highlighted by “UR” followed by the number of the project

Fundamental Safety Principles SPESS A SPESS B

GSR Part 1 Rev.1

Governmental, Legal and Regulatory Framework for Safety

NS-R-3 Rev.1 Site Evaluation for Nuclear Installations UR (DS484)

GS-R-3 The Management System for Facilities and Activities UR DS456

SSR-2/1 Rev.1 Safety of Nuclear Power Plants: Design

GSR Part 3 Radiation GSR Part 4 Rev.1 Safety

Protection and Safety of Assessment for Facilities and Radiation Sources:

Activities

International Basic Safety Standards (Final Edition available only in English)

SSR-2/2 Rev.1 Safety of NS-R-4 Safety of Research Nuclear Power Plants:

Reactors UR DS476

Commissioning and Operation

GSR Part 5 Predisposal

GSR Part 6 Decommissioning GSR-Part 7 Preparedness and Management of Radioactive of Facilities Response for a Nuclear or Waste

Radiological Emergency

NS-R-5 (Rev.1) Safety of

SSR-5 Disposal of Radioactive SSR-6 Regulations for the

Nuclear Fuel Cycle Facilities Waste Safe Transport of Radioactive

UR DS478

Material

Governmental, Legal and Regulatory Framework – Safety Infrastructure

GS-G-1.1 Organization and Staffing of the Regulatory Body for Nuclear Facilities UR DS472

WS-G-2.3 Regulatory Control of

Radioactive Discharges to the Environment UR DS442

GS-G-1.2 Review and

Assessment of Nuclear Facilities by the Regulatory Body UR DS473

GSG-4 Use of External Experts by the Regulatory Body UR DS472

GS-G-1.3 Regulatory Inspection of Nuclear

Facilities and Enforcement by the Regulatory Body UR DS473

GS-G-1.4 Documentation for Use in Regulating Nuclear Facilities UR DS473

GS-G-1.5 Regulatory Control of Radiation Sources

Partial revision DS472 and DS473

SSG-12 Licensing Process for Nuclear Installations Partial revision DS473

SSG-16 Establishing the Safety Infrastructure for a Nuclear Power Programme UR DS486

Management Systems

GS-G-3.1 Application of the GS-G-3.2 The Management GS-G-3.3 The Management GS-G-3.4 The Management Management System for System for Technical Services System for the Processing, System for the Disposal of Facilities and Activities in Radiation Safety Handling and Storage of

Radioactive Waste UR DS477UR DS453

Radioactive Waste UR DS477

Radiation Protection and Safety of Radiation Sources Remediation

RS-G-1.1 Occupational

RS-G-1.2 Assessment of

RS-G-1.3 Assessment of

RS-G-1.4 Building

Radiation Protection Occupational Exposure Due Occupational Exposure Due Competence in

UR DS453

to Intakes of to External

Radiation Protection and the Radionuclides Sources of Radiation Safe Use of Radiation UR DS453

UR DS453

Sources UR DS455

GS-G-3.5 The Management System for Nuclear Installations

RS-G-1.5 Radiological

Protection

for Medical Exposure to Ionizing Radiation UR DS399

TS-G-1.4 The Management

System for the Safe

Transport of Radioactive Material

RS-G-1.6 Occupational Radiation

Protection in the Mining and Processing of Raw Materials UR DS453

RS-G-1.7 Application of the Concepts of Exclusion, Exemption and Clearance

RS-G-1.8 Environmental and Source Monitoring for Purposes of Radiation Protection

TS-G-1.3 Radiation Protection

Programmes for the Transport of Radioactive Material

RS-G-1.9 Categorization of Radioactive Sources

WS-G-3.1 Remediation Process for Areas Affected by Past Activities and Accidents UR DS468

RS-G-1.10 Safety of Radiation Generators and Sealed Radioactive Sources

GSG-5 Justification of Practices, Including Non-Medical Imaging SSG-8 Radiation Safety of

Gamma, Electron and X Ray Irradiation Facilities

SSG-32 Protection of the

Public against Exposure Indoors due to Radon and Other Natural Sources of Radiation

SSG-11 Radiation Safety in

Industrial Radiography

SSG-36 Radiation Safety for Consumer Products (DS458)

SSG-17 Control of Orphan

Sources and Other

Radioactive Material in the Metal Recycling and Production Industries

SSG-19 National Strategy for

Regaining Control over Orphan Sources and Improving Control over Vulnerable Sources

Safety Assessment

GS-G-4.1 Format and Content

of the Safety Analysis Report for Nuclear Power Plants UR DS449

GSG-3 The Safety Case and

Safety Assessment for the Predisposal Management of Radioactive Waste

SSG-2 Deterministic Safety Analysis for Nuclear Power Plants

SSG-3 Development and Application of Level 1 Probabilistic Safety Assessment for

Nuclear Power Plants

SSG-4 Development and Application of Level 2 Probabilistic Safety Assessment for

Nuclear Power Plants

WS-G-5.2 Safety Assessment for the Decommissioning of Facilities Using Radioactive Material

SSG-20 Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report

SSG-27 Criticality Safety in the Handling of Fissile Material

Radioactive Waste Management, Decommissioning & Remediation

GSG-1 Classification of Radioactive Waste

WS-G-2.7 Management of Waste from the Use of Radioactive Material in Medicine, Industry,

Agriculture, Research and Education UR DS454

WS-G-2.3 Regulatory Control of Radioactive Discharges to the Environment UR DS442

GSG-3 The Safety Case and Safety Assessment for the Predisposal Management of Radioactive Waste

DS448 Predisposal

Management of Radioactive Waste from Nuclear Power Plants and Research Reactors

WS-G-2.1 Decommissioning of Nuclear Power Plants and Research Reactors UR DS452

DS447 Predisposal

Management of Radioactive Waste from Fuel Cycle Facilities

WS-G-2.4 Decommissioning of Nuclear Fuel Cycle Facilities UR DS452

WS-G-6.1 Storage of Radioactive Waste

WS-G-2.2 Decommissioning

of Medical, Industrial and Research Facilities UR DS403

SSG-15 Storage of Spent Nuclear Fuel

WS-G-5.2 Safety Assessment for the

Decommissioning of Facilities Using Radioactive Material

WS-G-1.2 Management of Radioactive Waste from the Mining and Milling of Ores UR DS459

WS-G-5.1 Release of Sites from Regulatory Control on Termination of Practices UR partly with DS473

WS-G-3.1 Remediation Process for Areas Affected by Past Activities and Accidents UR DS468

Emergency Preparedness and Response

GS-G-2.1 Arrangements for Preparedness for a Nuclear or Radiological Emergency

GSG-2 Criteria for Use in Preparedness and Response for a Nuclear or Radiological Emergency

TS-G-1.2 Planning and Preparing for

Emergency Response to Transport Accidents Involving Radioactive Material UR DS469

Site Evaluation

NS-G-3.1 External Human NS-G-3.2 Dispersion of Induced

Radioactive

Events in Site Evaluation Material in Air and Water for Nuclear Power Plants

and Consideration of Population Distribution in Site Evaluation for Nuclear Power Plants UR DS427

Nuclear Power Plants

SSG-39 (DS431) Design of

Instrumentation and Control Systems for Nuclear Power Plants

SSG-9 Seismic Hazards in Site Evaluation for Nuclear Installations

NS-G-1.4 Design of Fuel Handling

and Storage Systems for Nuclear Power Plants UR DS487

SSG-18 Meteorological and Hydrological Hazards in Site Evaluation for

Nuclear Installations

NS-G-1.5 External Events Excluding

Earthquakes in the Design of Nuclear Power Plants

SSG-21 Volcanic Hazards in Site Evaluation for Nuclear Installations

NS-G-1.6 Seismic Design and Qualification for Nuclear Power Plants

NS-G-3.6 Geotechnical

Aspects of Site Evaluation and Foundations for Nuclear Power Plants

NS-G-1.7 Protection against Internal Fires and

Explosions in the Design of Nuclear Power Plants

SSG-35 Site Survey and Site

Selection for Nuclear Installations

SSG-34 Design of Electrical

Power Systems for Nuclear Power Plants (DS430)

NS-G-1.9 Design of the

Reactor

Coolant System and Associated Systems in Nuclear Power Plants UR DS481

SSG-4 Development and Application of Level 2 Probabilistic Safety Assessment for

Nuclear Power Plants

NS-G-2.7 Radiation Protection and Radioactive Waste Management

in the Operation of

NS-G-1.10 Design of Reactor

Containment Systems

for Nuclear Power Plants UR DS482

NS-G-2.1 Fire Safety in the

Operation of Nuclear Power Plants

NS-G-2.8 Recruitment, Qualification and

Training of Personnel for Nuclear Power Plants

NS-G-1.11 Protection against

Internal Hazards other than Fires and Explosions in the Design of

Nuclear Power Plants

NS-G-2.2 Operational Limits

and

Conditions and

Operating Procedures for Nuclear Power Plants

SSG-28 Commissioning for

Nuclear Power Plants

NS-G-1.12 Design of the

Reactor Core for

Nuclear Power Plants UR DS488

NS-G-2.3 Modifications to Nuclear Power Plants

SSG-25 Periodic Safety Review for Nuclear Power Plants

NS-G-1.13 Radiation Protection

Aspects of Design

for Nuclear Power Plants

NS-G-2.4 The Operating

Organization for

Nuclear Power Plants

NS-G-2.11 A System for the Feedback of Experience from Events in Nuclear

Installations UR DS479

SSG-2 Deterministic Safety Analysis for Nuclear Power Plants

NS-G-2.5 Core Management

and Fuel Handling

for Nuclear Power Plants

NS-G-2.12 Ageing

Management for Nuclear Power Plants UR DS485

SSG-3 Development and Application of Level 1 Probabilistic Safety Assessment for

Nuclear Power Plants

NS-G-2.6 Maintenance, Surveillance

and In-service Inspection in Nuclear Power Plants

NS-G-2.13 Evaluation of Seismic

Safety for Existing Nuclear Installations

Nuclear Power Plants

NS-G-2.14 Conduct of Operations at

Nuclear Power Plants

NS-G-2.15 Severe Accident Management Programmes for

Nuclear Power Plants UR DS483

SSG-13 Chemistry Programme

for Water Cooled Nuclear Power Plants

SSG-30 Safety Classification

of Structures, Systems and Components in Nuclear Power Plants

SSG-38 Construction for

Nuclear Installations

SSG-27 Criticality Safety in

the Handling of Fissile Material

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