IAEA draft safety standards by number
Current safety standards under development
The table below lists all safety standards series currently under development. Where available, the latest draft is provided.
| DS421 | Protection of the public against exposure to natural sources of radiation including NORM residues DPP421 |
| DS417 | Hydrological and Meteorological Hazards in Site Evaluation for Nuclear Installations DPP417 |
| DS416 | Licensing process for nuclear installations DPP416 |
| DS415 | Governmental and Regulatory Framework for Nuclear, Radiation, Radioactive Waste and Transport Safety DPP415 |
| DS414 | Safety of Nuclear Power Plants: Design DPP414 |
| DS413 | Safety of Nuclear Power Plants: Operation DPP413 |
| DS412 | Ageing management for Research Reactors DPP412 |
| DS411 | Orphan Radioactive Sources and Radioactively Contaminated Material in the Metal Recycling Industry DPP411 |
| DS410 | Development of a national strategy for regaining control over orphan sources and improving control over vulnerable radioactive sources DPP410 |
| DS409 | Radiation Safety of Gamma, Electron and X Ray Irradiation Facilities DPP409 |
| DS408 | Radiation Safety in Industrial Radiography DPP408 |
| DS407 | Criticality Safety DPP407 |
| DS404 | Decommissioning of Nuclear Fuel Cycle Facilities DPP404 |
| DS403 | Decommissioning of Medical, Industrial and Research Facilities DPP403 |
| DS402 | Decommissioning of Nuclear Power Plants and Research Reactors DPP402 |
| DS401 | Justification of Practices DPP401 |
| DS399 | Radiation Protection in Medical Radiation Exposure DPP399 |
| DS397 | Safety in the Use and Modification of Research Reactors DPP397 |
| DS396 | Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report DPP396 |
| DS395 | Deterministic Safety Analysis and their Application for Nuclear Power Plants DPP395 |
| DS394 | Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Reactors DPP394 |
| DS393 | Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants DPP393 |
| DS390 | Classification of Radioactive Waste DPP390 |
| DS388 | Chemistry Programme for Water Cooled Nuclear Power Plants DPP388 |
| DS387 | Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material DPP387 |
| DS385 | Severe Accident Management Programmes for Nuclear Power Plants DPP385 |
| DS383 | Seismic Evaluation of Existing Nuclear Facilities DPP383 |
| DS382 | Ageing Management for Nuclear Power Plants DPP382 |
| DS381 | Safety of Fuel Cycle R&D Facilities DPP381 |
| DS379 | International Basic Safety Standards for Protection against Ionizing Radiation (revision of the BSS) DPP379 |
| DS376 | Safety Assessment for Decommissioning of Facilities Using Radioactive Material DPP376 |
| DS371 | Storage of Spent Fuel DPP371 |
| DS367 | Safety Classification of Structures, Systems and Components in Nuclear Power Plants DPP367 |
| DS365 | Risk-Informed Decision Making DPP365 |
| DS360 | Safety of Reprocessing Facilities DPP360 |
| DS357 | Monitoring and Surveillance of Radioactive Waste Disposal Facilities DPP357 |
| DS356 | Near Surface Disposal Facilities DPP356 |
| DS355 | Safety Assessment of Radioactive Waste Disposal Facilities DPP355 |
| DS354 | Disposal of Radioactive Waste DPP354 |
| DS353 | Predisposal Management of Radioactive Waste DPP353 |
| DS351 | Grading the Application of Safety Requirements - A guidance for Research Reactors DPP351 |
| DS350 | Core Management and Fuel Handling at Research Reactors DPP350 |
| DS349 | Application of the Management Systems for Nuclear Facilities DPP349 |
| DS348 | Safety Assessment and Verification of Nuclear Facilities and Activities DPP348 |
| DS347 | Conduct of Operations at Nuclear Power Plants DPP347 |
| DS346 | Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material |
| DS345 | Regulations for the Safe Transport of Radioactive Material, TS-R-1 DPP345 |
| DS344 | Conversion and Enrichment Facilities DPP344 |
| DS340 | Radiation Protection and Radioactive Waste Management in the Design and Operation of Research Reactors DPP340 |
| DS337 | Management System for the Safety of Radioactive Waste Disposal Facilities and Activities DPP337 |
| DS336 | Management Systems for Treatment Handling and storage of Radioactive Material DPP336 |
| DS335 | Borehole Facilities for the Disposal of Radioactive Waste DPP335 |
| DS334 | Geological Disposal of Radioactive Waste DPP334 |
| DS327 | Compliance Assurance For The Safe Transport Of Radioactive Material, TS-G-1.4 DPP327 |
| DS326 | TS-G-1.3 Management Systems For The Safe Transport Of Radioactive Material DPP326 |
| DS325 | The Operating Organization and the Recruitment, Training and Qualification of Personnel for Research Reactors DPP325 |
| DS318 | Safety of MOX Fuel Fabrication Facilities DPP318 |
| DS317 | Safety of Uranium Fuel Fabrication Facities DPP317 |
| DS316 | Safety of Fuel Cycle Facilities DPP316 |
| DS315 | Management Systems for Technical Services in Radiation Safety DPP315 |
| DS284 | Safety Assessment for Nuclear and Radiation Facilities other than Reactors and Waste repositories |
| DS261 | Operational Limits and Conditions and Operating Procedures for Research Reactors |
| DS44 | Criteria for Use in Planning Response to Nuclear and Radiological Emergencies DPP44 |
