DS518 - Revision by amendment of 2 Specific Safety Guides on Nuclear Fuel Cycle
Status: STEP 5
Revision von SSG-42 (Ex DS360) und SSG-43 (Ex DS381)
- SSG-42: "Safety of Nuclear Fuel Reprocessing Facilities"
- SSG-43: "Safety of Nuclear Fuel Cycle Research and Development Facilities"
Beteiligte IAEO-Komitees: NUSSC, RASSC, WASSC, EPReSC, NSGC
Specific Safety Guides
STEP 12 | ||
STEP 11 | Kommentare der SSCs und IAEO-Bewertung | IAEO-Zusammenfassung nach STEP 11 |
STEP 8 | Kommentare der Mitgliedsstaaten und IAEO-Bewertung |
IAEO-Zusammenfassung nach STEP 8 |
STEP 7 | Kommentare der SSCs | IAEO-Zusammenfassung nach STEP 7 |
STEP 4 | ||
STEP 3 | Kommentare der SSCs und IAEO-Bewertung | IAEO-Zusammenfassung nach STEP 3 |
Document Preparation Profile "DPP"
Zurück zur Übersicht "In Entwicklung befindliche Safety Standards"
Background Information
Under this DPP will be revised two Guides: SSG-42 “Safety of Nuclear Fuel Reprocessing Facilities” and SSG-43 “Safety of Nuclear Fuel Cycle Research and Development Facilities” (Group 2). According to criteria of grouping the Safety Guides by three DPPs, Safety Guides in Group 2 were published recently (2017), they considered lessons learned from Fukushima Daiichi NPP Accident and need only minor modification.
The following specific issues will be addressed for SSG-42:
-
New section on management and verification of safety, aligned with SSR-4 and relevant management safety guide GS-G-3.5;
-
Include auxiliary activities such as sampling within scope;
-
Include safety culture aspects specific for nuclear fuel reprocessing facilities;
-
Include information on support systems and analytical laboratories.
The following specific issues will be addressed for SSG-43:
-
New section on management and verification of safety, aligned with SSR-4 and relevant management safety guide GS-G-3.1;
-
Include sampling within scope;
-
Review the safety culture aspects already covered in SSG-43;
-
Include information on support systems.