DS509 - Revision by amendment of 8 SSGs on RReactors

Status: SSG-80 "Commissioning of Research Reactors" (DS509A)
              SSG-81 "Maintenance, Periodic Testing and Inspection of Research Reactors" (DS509B)
              SSG-82 "Core Management and Fuel Handling for Research Reactors" (DS509C)
              SSG-83 "Operational Limits and Conditions and Operating Procedures for Research Reactors" (DS509D)
              SSG-84 "The Operating Organization and the Recruitment, Training and Qualification of Personnel for
                             Research Reactors" (DS509E)
              SSG-85 "Radiation Protection and Radioactive Waste Management in the Design and Operation of Research Reactors" (DS509F)
              SSG-10, Rev.1 "Ageing Management for Research Reactors" (DS509G)
              SSG-37, Rev.1 "Instrumentation and Control Systems and Software Important to Safety for Research Reactors" (DS509H)

Veröffentlichung  2023

Revision durch Änderung von  NS-G-4.1,  NS-G-4.2, NS-G-4.3NS-G-4.4, NS-G-4.5 , NS-G-4.6, SSG-10  (Ex DS412) und SSG-37 (Ex DS436)

Beteiligte IAEO-Komitees: NUSSC, EPReSC, RASSC, TRANSSC, WASSC, NSGC

Specific Safety Guide

STEP 13
DS509A
DS509B
DS509C
DS509D
DS509E
DS509F
DS509G
DS509H

   

STEP 12
DS509A
DS509B
DS509C
DS509D
DS509E
DS509F
DS509G
DS509H

   

STEP 11

DS509A
DS509B
DS509C
DS509D
DS509E
DS509F
DS509G
DS509H

Kommentare der SSCs und IAEO-Bewertung

DS509 IAEO-Bewertung

IAEO-Zusammenfassung nach STEP 11

DS509A nach STEP 11
DS509B nach STEP 11
DS509C nach STEP 11
DS509D nach STEP 11
DS509E nach STEP 11
DS509F nach STEP 11
DS509G nach STEP 11
DS509H nach STEP 11

STEP 8
DS509A
DS509B
DS509C
DS509D
DS509E
DS509F
DS509G
DS509H

Kommentare der SSCs und IAEO-Bewertung

IAEO-Zusammenfassung nach STEP 8

STEP 7

DS509-NS-G-4.1
DS509-NS-G-4.2
DS509-NS-G-4.3
DS509-NS-G-4.4
DS509-NS-G-4.5
DS509-NS-G-4.6
DS509-SSG-10
DS509-SSG-37

Kommentare der SSCs und IAEO-Bewertung

DS509-NS-G-4.1 IAEO-Bewertung
DS509-NS-G-4.2 IAEO-Bewertung
DS509-NS-G-4.3 IAEO-Bewertung
DS509-NS-G-4.4 IAEO-Bewertung
DS509-NS-G-4.5 IAEO-Bewertung
DS509-NS-G-4.6 IAEO-Bewertung
DS509-SSG-10 IAEO-Bewertung
DS509-SSG-37 IAEO-Bewertung

IAEO-Zusammenfassung nach STEP 7

DS509-NS-G-4.1 nach STEP 7
DS509-NS-G-4.2 nach STEP 7
DS509-NS-G-4.3 nach STEP 7
DS509-NS-G-4.4 nach STEP 7
DS509-NS-G-4.5 nach STEP 7
DS509-NS-G-4.6 nach STEP 7
DS509-SSG-10 nach STEP 7
DS509-SSG-37 nach STEP 7

STEP 4 Kommentare der SSCs und IAEO-Bewertung IAEO-Zusammenfassung nach STEP 4
STEP 3 Kommentare der SSCs und IAEO-Bewertung IAEO-Zusammenfassung nach STEP 3

Document Preparation Profile "DPP"

Zurück zu „IAEO Safety Standards Series“ (Übersicht aller derzeit gültigen Sicherheitsstandards)

Background Information

The revision of the Guides proposed in this DPP is timely because they predate SSR-3 and most of the General Safety Requirements publications, and as such, the Guides contain many references to superseded requirements, do not fully address all of the current requirements and do not cover the safety of subcritical assemblies. Also, some of the Guides are ten or more years old. In addition, guidance in similar NPP safety standards will be considered to ensure overall consistency. The added value of the revised Guides will be to provide target users with comprehensive, consistent and up-to-date guidance for implementing the safety requirements in SSR-3 and the General Safety Requirements as they apply to research reactors.

The revision of the eight Guides covered by this DPP will benefit from revisions to take into consideration the following:

  • Revisions implemented in the General Safety Requirements, other IAEA Safety Standards and, in particular, the new and modified requirements in SSR-3 since publication of the Guides;
  • Long Term Structure of the IAEA Safety Standards;
  • Feedback from the users of the IAEA Safety Standards related to research reactors;
  • Use of these Guides for subcritical assemblies, which are now in the scope of SSR-3;
  • Lessons from the accident at the Fukushima Daiichi nuclear power plant and other events in the nuclear industry, including those occurring at research reactors that were reported to the Incident Reporting System for Research Reactors;
  •  Experience gained with INSARR missions.

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