Status: STEP 3
Beteiligte IAEO-Komitees: NUSSC, EPReSC, NSGC
Specific Safety Guide
|STEP 11||Kommentare der SSCs und IAEO-Bewertung||IAEO-Zusammenfassung nach STEP 11|
|STEP 8||Kommentare der Mitgliedsstaaten
|IAEO-Zusammenfassung nach STEP 8|
|STEP 7||Kommentare der SSCs und IAEO-Bewertung||IAEO-Zusammenfassung nach STEP 7|
|STEP 3||Kommentare der SSCs und IAEO-Bewertung|
Document Preparation Profile "DPP"
Zurück zur Übersicht "In Entwicklung befindliche Safety Standards"
Recommendations related to the safety assessment process for nuclear power plants (NPPs) were previously provided in IAEA Safety Standards Series No. NS-G-1.2, Safety Assessment and Verification for Nuclear Power Plants, published in 2001.
The recommendations in NS-G-1.2 mainly focused on the deterministic safety analysis, the probabilistic safety assessment and the engineering aspects of items important to safety for nuclear power plants. This Safety Guide was superseded by IAEA Safety Standards Series Nos GSR Part 4, Safety Assessment for Facilities and Activities, and SSG-2, Deterministic Safety Analysis for Nuclear Power Plants. These are now GSR Part 4 (Rev. 1) and SSG-2 (Rev. 1).
In addition, IAEA Safety Standards Series Nos SSG-3, Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants, and SSG-4, Development and Application of Level 2 Probabilistic Safety Assessment for Nuclear Power Plants, were developed to provide recommendations for the development and application of Level 1 and Level 2 PSA for NPPs.
As a result of these developments, IAEA Safety Standards provide recommendations for conducting probabilistic safety assessments and the deterministic safety analyses but not for the safety assessment and verification of engineering aspects of items important to safety of NPPs from a design perspective.
The proposed new Safety Guide aims at providing recommendations to meet the requirements established in GSR Part 4 (Rev. 1) for conducting a comprehensive and cross-cutting safety assessment and verification process with regard to engineering aspects of items important to safety of NPPs. The recommendations will target the phases of review for authorization (licensing) of the construction, modification and operation of new NPPs, and the re-evaluation of safety of existing NPPs during periodic safety reviews (e.g. for incorporating operating experience feedback, research and technical results and developments, improvements related to ageing effects as well as to in-service inspection, testing, monitoring and maintenance activities, site environmental changes, and new regulatory requirements).
In addition, the recommendations provided in this Safety Guide will focus on the assessment and verification of compliance with the requirements for the design and operation of items important to safety of NPPs established in SSR-2/1 (Rev. 1) and SSR-2/2 (Rev. 1), the requirements for radiation protection established in GSR Part 3, as well as requirements established in SSR-1 for the protection of items important to safety against hazards from site characteristics.
These recommendations will complement the recommendations in the IAEA Safety Guides on deterministic safety analysis as well as on probabilistic safety assessment.
It is expected that the Safety Guide will promote consistency in conducting the safety assessment and the verification of the design of engineering aspects of items important to safety of NPPs.
In addition, this Safety Guide will provide a standard framework to facilitate regulatory reviews and independent or peer reviews (e.g. Technical Safety Review - TSR) of the safety assessment and its applications.