DS524 - Radiation Protection Aspects of Design for Nuclear Power Plants
Status: STEP 7
Revision von NS-G-1.13 (Ex DS313)
Beteiligte IAEO-Komitees: NUSSC, RASSC, WASSC, EPReSC, NSGC
Specific Safety Guide
|STEP 11||Kommentare der SSCs und IAEO-Bewertung||IAEO-Zusammenfassung nach STEP 11|
|STEP 8||Kommentare der Mitgliedsstaaten
|IAEO-Zusammenfassung nach STEP 8|
|STEP 7||Kommentare der SSCs||IAEO-Zusammenfassung nach STEP 7|
|STEP 3||Kommentare der SSCs und IAEO-Bewertung||IAEO-Zusammenfassung nach STEP 3|
Document Preparation Profile "DPP"
The Safety Guide NS-G-1.13 on “Radiation Protection Aspects of Design for Nuclear Power Plants” was published in 2005. This revision will provide recommendations to meet the revised requirements according to:
- Revision of the Specific Safety Requirements publication on the Safety of Nuclear Power Plants: Design - SSR-2/1 (Rev.1) in 2016 (in particular Requirement 5)
- Publication of the Generic Safety Requirements GSR Part 4, Safety Assessment for Facilities and Activities in 2009
- Publication of the most recent version GSR Part 4 (Rev.1) in 2016.
In addition, the revision is needed to address the concepts of optimization of protection and safety and application of dose limits into design based on relevant requirements set out in GSR Part 3 Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards (2014).
The revision will incorporate experience of Member States on the application of safety standards and operating experience and feedback from the accident at the Fukushima Daiichi NPP.
Since the publication of NS-G-1.13, improvements have been introduced to plant designs for new NPPs and modifications to existing NPPs in different areas that affect radiation protection of workers and members of public such as outages, maintenance, communication technologies, automation and management of plant operations. This revision will take into account these improvements and will include the latest information about contemporary technical and management solutions implemented in the latest designs and modifications of NPPs regarding radiation protection.
For nuclear power plants designed according to earlier standards, it is expected that in the safety assessments of such designs a comparison will be made with the current standards (for example as part of the safety reassessment of the plant), to determine whether the radiation protection measures and arrangements of the plant could be further enhanced by means of reasonably practicable safety improvements: see para. 1.3 of SSR-2/1 (Rev.1).