DS517 - Revision by amendment of 3 Specific Safety Guides on Nuclear Fuel Cycle Facilities

Status: STEP 3

Revision von SSG-5 (Ex DS344), SSG-6 (Ex DS317) und SSG-7 (Ex DS318)

  • SSG-5: "Safety of Conversion Facilities and Uranium Enrichment Facilities"
  • SSG-6: "Safety of Uranium Fuel Fabrication Facilities"
  • SSG-7: "Safety of Uranium and Plutonium Mixed Oxide Fuel Fabrication 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"

Under this DPP will be revised three Guides: SSG-5 “Safety of Conversion Facilities and Uranium Enrichment Facilities”, SSG-6 “Safety of Uranium Fuel Fabrication Facilities“ and SSG-7 “Safety of Uranium and Plutonium Mixed Oxide Fuel Fabrication Facilities” (Group 1).

According to criteria of grouping the Safety Guides by three DPPs, Safety Guides in Group 1 were developed before publishing most of IAEA General Safety Requirements and before the accident at the Fukushima Daiichi nuclear power plant and require significant revision.

The following specific issues will be addressed for SSG-5:

  • The scope can be reduced to centrifuges in design and operation with gas diffusion only decommissioning;
  • Include auxiliary activities such as sampling, homogenization and blending within scope;
  • Include guidance on use of water for cleaning cylinders with heels;
  • Consider hazardous material assessments for uranium hexafluoride;
  • Include safety culture aspects specific for conversion facilities and uranium enrichment facilities;
  • Include the information on support systems and analytical laboratories.

 

The following specific issues will be addressed for SSG-6:

  • Keep the scope to commercial uranium below 6% and confirm that fuel fabrication with reprocessed U containing traces of Pu is covered;
  • Include auxiliary activities such as sampling, homogenization and blending within scope;
  • Consider hazardous material assessments for uranium hexafluoride;
  • Include the information on support systems and analytical laboratories;
  • Include safety culture aspects specific for uranium fuel fabrication facilities;
  • Check for consistency with SSG-27 (which is being updated in parallel).

 

The following specific issues will be addressed for SSG-7:

  • Include auxiliary activities such as sampling, homogenization and blending within scope;
  • Include safety culture aspects specific for uranium and plutonium mixed oxide fuel fabrication facilities;
  • Include the information on support systems and analytical laboratories;
  • Check for consistency with SSG-27 (which is being updated in parallel).