​Design Safety Review (DSR)/Generic Reactor Safety Review (GRSR) 

The objective of the Design Safety Review (DSR), performed at the request of a Member State organization, is to evaluate the completeness and comprehensiveness of a reactor's safety documentation by an international team of senior experts.

The DSR is based on IAEA Fundamental Safety Principles (SF-1), Safety Requirements for Safety Assessment for Facilities and Activities (GS-R Part 4), 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 the 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 DSR module.

 

 
 

 

The aims of the DSR are:

  • To provide advice regarding the design’s ability to meet the IAEA Fundamental Safety Principles

  • To 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 designs that are not at the licensing stage yet. This review is focussed on checking the status of the documentation for completeness and comprehensiveness against the IAEA Safety Standards. 

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: Most 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

ESBWR (GE/Toshiba)/NII-HSC/UK1

EPR (AREVA)/NII-HSC/UK1

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

Completed May 2013

VVER-TOI/Rosenergoatom Concern OJSC/Russia

​Submitted to Rosenergoatom June 2014

 1 Utilized GS-R Part 4 only

2 First review to include NSR-1

3 First review to include SSR-2/1(replaced NSR-1)