scholarly journals Approach to Regulatory Pre-Licensing SMR Vendor Design Review

2020 ◽  
pp. 4-13
Author(s):  
O. Zhabin ◽  
O. Pecherytsia ◽  
S. Tarakanov ◽  
I. Shevchenko

The Canadian Nuclear Safety Commission (CNSC) has recently completed the first phase of the pre-licensing vendor design review (VDR) for the SMR-160 small modular reactor (SMR) designed by Holtec International (USA). This event is an example of early involvement of the regulatory authority into review of the safety assessment for SMR design developed in compliance with standards and rules of another country. This example deserves a detailed analysis considering that the introduction of SMR technology is potentially attractive for Ukraine and there is national interest in this area. The paper presents an overview of the regulatory framework governing the pre-licensing VDR by CNSC: objective, initial conditions, main stages, technical content and general expected results of this process. According to the first phase of the review performed for the SMR-160 design, information on the main aspects addressed for each technical area and the main review findings are provided. Since the implementation of relevant advanced practices is reasonable and relevant, the paper proposes to consider the development and implementation of regulatory framework for the national nuclear regulatory authority to perform further pre-licensing reviews of designs using the latest foreign technologies.

Author(s):  
Kevin Lee

Over the course of the last several years the Canadian Nuclear Safety Commission (CNSC) has engaged with numerous vendors and potential licenses of small modular reactors (SMR) technology. This paper describes why Canada, and the CNSC, is of such interest to the international SMR community for prelicensing engagement and potential licensing of SMRs. It discusses what an SMR is and what potentially differentiates them from standard nuclear power plants (NPP). Readiness activities for the potential licensing of SMRs are described as well as modifications being made to the CNSC’s existing regulatory framework to facilitate the same, without reducing safety. The role of the CNSC’s discussion paper (DIS-16-04, Small Modular Reactors: Regulatory Strategy, Approaches and Challenges) and how feedback received on it helped confirm the CNSC’s modifications to be undertaken to the regulatory framework, as well as areas requiring further clarity, are highlighted. Finally, The CNSC Vendor Design Review (VDR) process is described as well as its part in ensuring a state of readiness to evaluate a licence application.


2020 ◽  
Vol 9 (1) ◽  
pp. 99-106
Author(s):  
Kevin W. Lee

Over the course of the last several years the Canadian Nuclear Safety Commission (CNSC) has engaged with numerous vendors and potential licenses of small modular reactor (SMR) technology. This paper discusses what an SMR is and what potentially makes them different from standard nuclear power plants (NPP). Readiness activities for the potential licensing of SMRs are described as well as modifications being made to the CNSC’s existing regulatory framework to facilitate the same, without reducing safety. The role of the CNSC’s discussion paper DIS-16-04, Small Modular Reactors: Regulatory Strategy, Approaches and Challenges (DIS 16-04) and how feedback received on it helped confirm the CNSC’s modifications to be undertaken to the regulatory framework, as well as areas requiring further clarity, are highlighted. Finally, the role of the CNSC Vendor Design Review process is described as well as other readiness activities undertaken by the CNSC that are helping to ensure that the CNSC will be ready to accept and evaluate a license application for an SMR.


2011 ◽  
Vol 219-220 ◽  
pp. 937-940
Author(s):  
Bin Yu ◽  
Yong Xing Jin ◽  
Bin Zheng ◽  
Xiao Dong Zhang

Based on detailed analysis of the risk of bulk chemical tanker transportation, a societal risk acceptance criterion is established. The criterion takes advantage of formal safety assessment (FSA) methodology, which is widely used to analyze risk in maritime industry. In the end of this paper, the negligible range, the ALARP range and the intolerable range of bulk chemical tanker in China are estimated in the criterion.


Author(s):  
Lei Wan ◽  
Guiyong Li ◽  
Min Rui ◽  
Yongkang Liu ◽  
Jue Yang

A floating nuclear power plant (FNPP) with small modular reactor (SMR) is a combination of a civilian nuclear infrastructure and an offshore installation, which is defined as a floating nuclear facility. The article draws the lessons from studying of the engineer combination like Floating Production Storage and Offloading (FPSO) under the regulation of several government departments. It puts forward recommendations for license application and government regulation as follows in consideration with current license application for nuclear power plant and ship survey. A FNPP shall follow the requirements of construction, fueling and operation for civil nuclear installation combined with ship survey. Application is submitted to nuclear safety regulator for construction permit, while the design drawings shall be submitted to department of ship survey which checks the drawings whether meet the requirements of ship survey, considering some nuclear safety needs. The result of ship survey shall be represented in the safety analysis reports. The construction and important devices manufacturing shall be under the supervision of nuclear installation regulators and ship survey departments. In conclusion, National Nuclear Safety Administration (NNSA) and Maritime Safety Administration of the People’s Republic of China (MSA) shall establish united supervisory system for SMR on sea in China. It is suggested that NNSA is in charge of the overall safety of a FNPP, while MSA is responsible of the ship survey. The operator shall undertake obligation of a FNPP and evaluate the ship cooperating with experienced agency. It is suggested that government departments build the mutual recognition agreement of safety review. It is better to solve the vague questions by coordination.


2019 ◽  
Author(s):  
Akira Tokunaga ◽  
Akie Sotoguchi ◽  
Koji Shimoyama ◽  
Keiichiro Fujimoto

Author(s):  
Zhilin Chen ◽  
Ping Huang ◽  
Chunhui Wang ◽  
Zhiyuan Chi ◽  
Fangjie Shi ◽  
...  

It’s the trend to extend the operating license time, called Operating License Extension (OLE) in China, of nuclear power plants (NPPs) in the future. It needs to be adequately demonstrated by licensees and approved by the regulator to gain an extended license time, such as 20 years. The demonstration methods for OLE are different among countries due to the different management systems for NPPs. Safety assessment, environment effect evaluation and update of the final safety analysis report (FSAR) will be the main aspects during OLE demonstration of NPPs in China according to the technical policy issued by National Nuclear Safety Administration (NNSA). Technical methods for scoping and screening, aging management review and time-limited aging analyses, which are the main contents of safety assessment are established based on the technical policy drafted by NNSA and international experiences in order to assist the operators to implement the safety assessment for OLE of NPP.


Author(s):  
S. Herstead ◽  
M. de Vos ◽  
S. Cook

The success of any new build project is reliant upon all stakeholders — applicants, vendors, contractors and regulatory agencies — being ready to do their part. Over the past several years, the Canadian Nuclear Safety Commission (CNSC) has been working to ensure that it has the appropriate regulatory framework and internal processes in place for the timely and efficient licensing of all types of reactor, regardless of size. This effort has resulted in several new regulatory documents and internal processes including pre-project vendor design reviews. The CNSC’s general nuclear safety objective requires that nuclear facilities be designed and operated in a manner that will protect the health, safety and security of persons and the environment from unreasonable risk, and to implement Canada’s international commitments on the peaceful use of nuclear energy. To achieve this objective, the regulatory approach strikes a balance between pure performance-based regulation and prescriptive-based regulation. By utilizing this approach, CNSC seeks to ensure a regulatory environment exists that encourages innovation within the nuclear industry without compromising the high standards necessary for safety. The CNSC is applying a technology neutral approach as part of its continuing work to update its regulatory framework and achieve clarity of its requirements. A reactor power threshold of approximately 200 MW(th) has been chosen to distinguish between large and small reactors. It is recognized that some Small Modular Reactors (SMRs) will be larger than 200 MW(th), so a graded approach to achieving safety is still possible even though Nuclear Power Plant design and safety requirements will apply. Design requirements for large reactors are established through two main regulatory documents. These are RD-337 Design for New Nuclear Power Plants, and RD-310 Safety Analysis for Nuclear Power Plants. For reactors below 200 MW(th), the CNSC allows additional flexibility in the use of a graded approach to achieving safety in two new regulatory documents: RD-367 Design of Small Reactors and RD-308 Deterministic Safety Analysis for Small Reactors. The CNSC offers a pre-licensing vendor design review as an optional service for reactor facility designs. This review process is intended to provide early identification and resolution of potential regulatory or technical issues in the design process, particularly those that could result in significant changes to the design or analysis. The process aims to increase regulatory certainty and ultimately contribute to public safety. This paper outlines the CNSC’s expectations for applicant and vendor readiness and discusses the process for pre-licensing reviews which allows vendors and applicants to understand their readiness for licensing.


2020 ◽  
Vol 149 ◽  
pp. 107775
Author(s):  
Alan Matias Avelar ◽  
Marcelo Breda Mourão ◽  
Marcos Maturana ◽  
Claudia Giovedi ◽  
Alfredo Yuuitiro Abe ◽  
...  

Author(s):  
Лариса Чернухина ◽  
Larisa Chernukhina

The article deals with the issues of the delineation of authority between Federal legislative bodies and legislative bodies of the provinces and territories in the sphere of child protection from the domestic violence. The author analyzes the area of competence of the legislative bodies of mentioned levels, paying particular attention to their complementarity and possible conflicts between rules. In accordance with the Constitution of Canada the Federal, provincial and territorial governments have a shared responsibility for many aspects concerning the situation of children in society. However, criminalization of some unlawful acts, including the act of domestic violence, is an exclusive scope of jurisdiction of Federal agencies. On the basis of the analysis of the amendments to the criminal code of Canada the author comes to the conclusion that the Federal government is moving towards stricter sanctions for crimes related to domestic violence that target children. On the basis of detailed analysis of normative legal acts of the provinces and territories regulating social relations in the sphere of combating domestic violence and child protection the author concludes that the provincial laws on protection against domestic violence are intended to support and complement the Federal measures to protect victims of domestic violence under the criminal code of Canada. In general, provinces and territories have extensive regulatory framework in this area that allows to pursue a consistent policy aimed at improving the retaliatory measures against domestic violence, when the victims are children, as well as the maximum leveling of the consequences of such acts.


Author(s):  
C. Queral ◽  
L. Mena-Rosell ◽  
G. Jimenez ◽  
M. Sánchez-Perea ◽  
J. Hortal ◽  
...  

The integrated Safety Assessment (ISA) methodology, developed by the Spanish Nuclear Safety Council (CSN), has been applied to a thermal-hydraulic analysis of PWR Station Blackout (SBO) sequences in the context of the IDPSA (Integrated Deterministic-Probabilistic Safety Assessment) network objectives. The ISA methodology allows obtaining the damage domain (the region of the uncertain parameters space where the damage limit is exceeded) for each sequence of interest as a function of the operator actuations times. Given a particular safety limit or damage limit, several data of every sequence are necessary in order to obtain the exceedance frequency of that limit. In this application these data are obtained from the results of the simulations performed with MAAP code transients inside each damage domain and the time-density probability distributions of the manual actions. Damage limits that have been taken into account within this analysis are: local cladding damage (PCT>1477 K); local fuel melting (T>2499 K); fuel relocation in lower plenum and vessel failure. Therefore, to every one of these damage variables corresponds a different damage domain. The operation of the new passive thermal shutdown seals developed by several companies since Fukushima accident is considered in the paper. The results show the capability and necessity of the ISA methodology, or similar, in order to obtain accurate results that take into account time uncertainties.


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