Status: STEP 3
Revision von GSG-3
Beteiligte IAEO-Komitees: WASSC, NUSSC, RASSC, EPReSC, NSGC
Genaral Safety Guide
| 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 und IAEO-Bewertung | IAEO-Zusammenfassung nach STEP 7 |
| STEP 4 | ||
| STEP 3 | Kommentare der SSCs und IAEO-Bewertung | IAEO-Zusammenfassung nach STEP 3 Track changes Clean |
Zurück zur Übersicht "In Entwicklung befindliche Safety Standards"
Background Information
The objective of this Safety Guide is to provide recommendations for the development and review of the safety case and supporting safety assessments for facilities and activities dealing with the predisposal management of radioactive waste.
The proposed publication will provide coherent recommendations for complying with the requirements for the safe predisposal management of radioactive waste based on the latest revisions of other IAEA safety standards in this area and operational experience.
The revised Safety Guide will elaborate more on the elements and application of a graded approach in the development and review of the safety case and supporting safety assessment for all predisposal radioactive waste management facilities and activities.
The proposed publication will incorporate recommendations on the implementation of requirements for preparedness and response to a nuclear or radiological emergency pertaining to the design and implementation of safety measures in the safety case and supporting safety assessments.
The superseded references in GSG-3 will be updated with new publications to ensure consistency and provide up-to-date information.
The sequential construction of new power reactors or other nuclear facilities will be considered during the revision of GSG-3 based on the experience of Member States. In addition, the link between the safety assessment for predisposal waste management facilities and the safety analysis for the power reactors or other nuclear facilities at the single site will be considered.