Status: STEP 5
Revision von SSG-18 (Ex DS417)
Beteiligte IAEO-Komitees: NUSSC, WASSC
Specific 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 | IAEO-Zusammenfassung nach STEP 4 | |
| STEP 3 | Kommentare der SSCs und IAEO-Bewertung | IAEO-Zusammenfassung nach STEP 3 |
Zurück zur Übersicht "In Entwicklung befindliche Safety Standards"
Background Information
This revised Specific Safety Guide will supersede the IAEA Specific Safety Guide SSG-18, “Meteorological and Hydrological Hazards in Site Evaluation for Nuclear Installations”, which was published in 2011.
Because the current version of this Specific Safety Guide was in print when the Great East Japan Earthquake and Tsunami occurred in 2011, a Note by the Secretariat was added to SSG-18, which clearly supported the need for the revision by stating that the “lessons learned from studying the accident at the Fukushima Daiichi NPP in Japan following the disastrous earthquake and tsunami of 11 March 2011 will be reflected in this IAEA safety standard as revised and issued in the future”.
Meanwhile the External Events Safety Section has updated several relevant Safety Standards and Safety Guides by adding further recommendations in terms of:
- the uncertainties in hazard estimation,
- beyond design basis external events and safety margins, and
- multiple hazard combination issues
This revision aims at updating SSG-18 for compatibility with the updated Safety Requirements and supporting technical documents. Considerations of the recent advances in research and development for tsunami hazard estimation will also be included.
This revision is not intended to significantly change the scope of the Specific Safety Guide, that is primarily concerned with hazards associated with meteorological and hydrological phenomena external to nuclear installations over their entire lifetime. A draft plan for possible revisions is provided in the Feedback Analysis Reports given in the Annex.