Design Safety Review The objective of the Design Safety Review, performed at the request of a Member State organization, is to evaluate the completeness and comprehensiveness of a reactors’ safety documentation by an international team of senior experts.
In principle, the DSR is based on IAEA Fundamental Safety Principles
(SF-1) Safety Requirements for Safety Assessment for Facilities and Activities (GSR Part4), and Safety of Nuclear Power Plants: Design
(SSR-2/1). These Safety Requirements are high level standards addressing broadly the safety issues for nuclear installations and activities. The GS-R Part 4 requirements are generic and technology independent, therefore they are applicable at different stages of design evolution as well as to operating plants. The depth of the review and selection of requirements also depends on the design maturity and available documentation.
The design safety review is done using one of two available modules, depending on the design stage. For pre-licensing stage the review is done using the Generic Reactor Safety Review (GRSR) module, while during the licensed stages the review is done using the Design Safety Review (DSR) module.

The aims of the DSR are to:
Provide advice regarding the design’s ability to meet the IAEA Fundamental Safety Principles
Determine whether the safety requirements are being addressed in the design safety case and identify any that have been omitted
For those requirements that are addressed, form a view on whether they are being addressed in a way that is consistent with the spirit of the IAEA requirements
For the safety requirements that are not being addressed or are partially addressed, form a view on their relative significance and highlight their importance to safety.
As a response to renewed interest in the development of nuclear energy capacity across the globe, vendors are designing new reactors, with innovative systems, to meet the growing demand for safety and more economical nuclear power generation.
A specific model of DSR, the Generic Reactor Safety Review (GRSR), provides for the review of safety cases (completely or partially developed) of new concepts that are not at the licensing stage yet. This review is focused on checking the status of the documentation (completeness and comprehensiveness).
The GRSR provides for an early harmonized appraisal of safety cases made by vendors as a basis for an individual evaluation or the licensing process, which remains a sovereign activity of the Member States. Consequently, such safety evaluations, conducted against selected sets of Safety Standards, contribute to more effective management of subsequent activities within a global framework consistent with a harmonized approach to safety worldwide.
It should be noted that the IAEA Safety Standards applied in the DSR and GRSR, at the fundamental and requirements level, are generic and apply to all nuclear installations. Therefore, it is neither intended nor possible to cover or substitute licensing activity, or to constitute any kind of design certification.

Status of Reviews:
DSR
Member State |
Year |
Service |
Pakistan |
2006 |
Chashma 2 NPP: PSAR Chapters 11 & 12 (PAK/9/030) |
Ukraine |
2008 |
• Khmelnitski 2 |
2009 |
• Rivne 1, 2, 3 & 4 • South Ukraine 1, 2 & 3 • Zaporozhe 1-6 • Khmelnitski 1 |
Bulgaria |
2008 |
Follow-up mission to Kozloduy NPP: “Programme for modernization of Units 5 & 6" (BUL/4/013) |
Armenia |
2009 |
Follow-up mission: “Assess the resolution of IAEA safety issues at the Armenian Nuclear Power Plant” (ARM/9/020P) |
GRSR
Note: GRSR Reports are proprietary information and are not available for distribution.
Reactor type/Requesting Organization/Country |
Status |
ACR1000 (CANDU)/NII-HSC/UK1 |
Completed March 2008 |
AP1000 (Westinghouse)/NII-HSC/UK1 |
Completed March 2008 |
ESBWR (GE/Toshiba)/NII-HSC/UK1 |
Completed March 2008 |
EPR (AREVA)/NII-HSC/UK1 |
Completed March 2008 |
ATMEA1 (Conceptual)/AREVA-MHI/France2 |
Completed June 2008 |
| AP1000/Westinghouse/USA |
Completed January 2009 |
APR1400/KHNP/Korea |
Completed August 2009 |
APR1000/KEPCO Research Institute/Korea |
Completed August 2010 |
AES 2006/Rosenergoatom Concern OJSC/Russia3 |
Completed January 2013 |
ACPR 1000+ (Conceptual Design)/China Guangdong Nuclear Power Holding Co., LTD/China |
Started October 2012 |
VVER-TOI/Rosenergoatom Concern OJSC/Russia |
Planned for 2013 |
1 Utilized GSR Part 4 only
2 First review to include NSR-1
3 First review to include SSR-2/1(replaced NSR-1)