IAEA draft safety standards by number

Current safety standards under development

The table below lists all safety standards series currently under development.

DS431 Design of I & C Systems for NPPs
DS430 Design of Electric Power Systems for NPPs
DS429 External Support on Safey Issues DPP429
DS427 Radiological Environmental Impact Analysis for Facilities and Activities DPP427
DS426 Periodic Safety Review of Nuclear Power Plants DPP426
DS424 Establishing a Safety Infrastructure for a National Nuclear Power Programme DPP424
DS422 Seismic Hazards in Site Evaluation for Nuclear Installations DPP422
DS421 Protection of the public against exposure to natural sources of radiation including NORM residues DPP421
DS420 Radiation Safety for Nuclear Gauges DPP420
DS419 Radiation Safety for Well Logging Sources DPP419
DS417 Meteorological and Hydrological Hazards in Site Evaluation for Nuclear Installations DPP417
DS416 Licensing process for nuclear installations DPP416
DS415 Goveremental and Regulatory Framework for Safety DPP415
DS414 Safety of Nuclear Power Plants: Design DPP414
DS413 Safety of Nuclear Power Plants: Commissioning and Operation DPP413
DS412 Ageing management for Research Reactors DPP412
DS411 Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries DPP411
DS410 National Strategy for Regaining Control over Orphan Sources and Improving Control over Vulnerable 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
DS405 Volcanic Hazards in Site Evaluation for Nuclear Insatallations
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
DS381 Safety of Fuel Cycle R&D Facilities DPP381
DS379 International Basic Safety Standards for Protection against Ionizing Radiation (revision of the BSS) DPP379
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 of Radioactive Waste DPP356
DS355 The Safety Case and Safety Assessment for Radioactive Waste Disposal DPP355
DS354 Disposal of Radioactive Waste DPP354
DS351 The Use of a Graded Approach in the Application of the Safety Requirements for Research Reactors DPP351
DS344 Conversion and Enrichment Facilities DPP344
DS335 Borehole Facilities for the Disposal of Radioactive Waste DPP335
DS334 Geological Disposal of Radioactive Waste DPP334
DS318 Safety of MOX Fuel Fabrication Facilities DPP318
DS317 Safety of Uranium Fuel Fabrication Facilities DPP317
DS284 Safety Assessment for Radioactive waste predisposal facilities and activities
DS44 Criteria for Use in Planning Response to Nuclear and Radiological Emergencies DPP44


Back to top