Page 104 - AERB

6.4.5 IAEA Draft DPPs & Documents (CSS) (m) Safety Guide Schedules of Provisions of the IAEA
Regulations for ‘Safe Transport of Radioactive Material’
(a) Radiation Safety in Well Logging (DS 419) (20xx Edition), revision of SSG-33 (DS 506)
(b) Radiation Safety in the use of Nuclear Gauges (DS (n) DPP on ‘Leadership, Management and Culture for
420) Safety’, revision of GS-G-3.l (DS 513)

(c) Radiation Safety of Accelerator Based Radioisotope (o) Safety Guide on ‘Criticality Safety in the Handling of
Production Facilities (DS 434) Fissile Material’, revision of SSG-27 (DS 516)

(d) Design of Auxiliary and Supporting Systems for NPPs (p) Revision of Safety Guides SSG-5 on ‘Safety of
(DS 440) Conversion Facilities and Uranium Enrichment

(e) Format and Content of the Safety Analysis Report for Facilities’, SSG-6 on ‘Safety of Uranium Fuel
Nuclear Installations (DS 449) Fabrication Facilities’ and SSG-7 on ‘Safety of Uranium
and Plutonium Mixed Oxide Fuel Fabrication Facilities’
(f) Management of Radioactive Residues from Mining, (DS 517)
Mineral Processing, and other NORM related Activities
(DS 459) (q) Revision of SSG-42 on ‘Safety of Fuel Reprocessing
Facilities’ and SSG-43 on ‘Safety of Nuclear Fuel
(g) Safety Guide on ‘Preparedness and Response for Cycle Research and Development Facilities’ (DS 518)
an Emergency during the Transport of Radioactive
Material’, Revision of TS-G.1.2 (DS 469) (r) DPP on ‘Protection of Workers against Exposure due
to Radon’ (DS 519)
(h) Arrangements for Public Communications in
Preparedness and Response for a Nuclear or (s) DPP on ‘External Human Induced Hazards in Site
Radiological Emergency (DS 475) Evaluation for Nuclear Installations’, revision of NS-G-
3.1 (DS 520)
(i) Design of Fuel Handling and Storage Systems for
Nuclear Power Plants (DS 487) (t) DPP on ‘Evaluation of Seismic Safety for Existing
Nuclear Installations’, revision of NS-G-2.13 (DS 522)
(j) Storage of Spent Nuclear Fuel (DS 489)
(u) DPP on ‘Development and Application of Level 1
(k) Safety Guide on ‘Protection against Internal Hazards Probabilistic Safety Assessment for Nuclear Power
in the Design of Nuclear Power Plants’, revision and Plants’, revision of SSG-3 (DS 523)
combination of NS-G-1.7 and NS-G-1.11 (DS 494)
(v) DPP on ‘Radiation Protection Aspects of Design for
(l) Safety Guide Advisory Material for IAEA Regulations Nuclear Power Plants’, revision of NS-G-1.13 (DS
for ‘Safe Transport of Radioactive Material’ - Edition 524).
for the SSR-6 (Rev. 1) (DS 496)

76 AERB Annual Report 2019