The Regulatory Framework for Safe Decommissioning of Nuclear Power Plants in Korea

2013 ◽  
Author(s):  
Sangmyeon Ahn ◽  
Jungjoon Lee ◽  
Chanwoo Jeong ◽  
Kyungwoo Choi
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Regulatory Framework ◽  
International Standards ◽  
Current Status ◽  
Nuclear Facilities ◽  
Safety Requirement ◽  
Regulatory Review ◽  
Safety Standards

We are having 23 units of nuclear power plants in operation and 5 units of nuclear power plants under construction in Korea as of September 2012. However, we don’t have any experience on shutdown permanently and decommissioning of nuclear power plants. There are only two research reactors being decommissioned since 1997. It is realized that improvement of the regulatory framework for decommissioning of nuclear facilities has been emphasized constantly from the point of view of IAEA’s safety standards. It is also known that IAEA will prepare the safety requirement on decommissioning of facilities; its title is the Safe Decommissioning of Facilities, General Safety Requirement Part 6. According to the result of IAEA’s Integrated Regulatory Review Service (IRRS) mission to Korea in 2011, it was recommended that the regulatory framework should require decommissioning plans for nuclear installations to be constructed and operated and these plans should be updated periodically. In addition, after the Fukushima nuclear disaster in Japan in March of 2011, preparedness for early decommissioning caused by an unexpected severe accident became important issues and concerns. In this respect, it is acknowledged that the regulatory framework for decommissioning of nuclear facilities in Korea need to be improved. First of all, we focus on identifying the current status and relevant issues of regulatory framework for decommissioning of nuclear power plants compared to the IAEA’s safety standards in order to achieve our goal. And then the plan is established for improvement of regulatory framework for decommissioning of nuclear power plants in Korea. It is expected that if the things will go forward as planned, the revised regulatory framework for decommissioning could enhance the safety regime on the decommissioning of nuclear power plants in Korea in light of international standards.

INTERCOMPARISON ON INTERNAL DOSE ASSESSMENT FOR NUCLEAR POWER PLANTS IN KOREA

2019 ◽  
Vol 186 (4) ◽  
pp. 524-529
Author(s):  
Si Young Kim
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Evaluation Method ◽  
Dose Assessment ◽  
Assessment Procedure ◽  
Internal Dose ◽  
Nuclear Facilities ◽  
International Intercomparison ◽  
Selection Of

Abstract The intercomparison test is a quality assurance activity performed for internal dose assessment. In Korea, the intercomparison test on internal dose assessment was carried out for nuclear facilities in May 2018. The test involved four nuclear facilities in Korea, and seven exposure scenarios were applied. These scenarios cover the intake of 131I, a uranium mixture, 60Co and tritium under various conditions. This paper only reviews the participant results of three scenarios pertinent to the operation of nuclear power plants and adopts the statistical evaluation method, used in international intercomparison tests, to determine the significance values of the results. Although no outliers were established in the test, improvements in the internal dose assessment procedure were derived. These included the selection of intake time, selection of lung absorption type according to the chemical form and consideration of the contribution of previous intake.

Canadian Nuclear Safety Commission: Readiness to Regulate SMRs in Canada

2011 ◽  
Author(s):  
S. Herstead ◽  
M. de Vos ◽  
S. Cook
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Safety Analysis ◽  
Reactor Power ◽  
Nuclear Safety ◽  
Regulatory Framework ◽  
Nuclear Industry ◽  
Plant Design ◽  
Regulatory Documents

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.

scholarly journals Spesifikasi, Kode dan Standar Baja Nasional dan Potensinya untuk Mendukung Program PLTN Tipe LWR di Indonesia

2019 ◽  
Vol 20 (2) ◽  
pp. 111 ◽  
Author(s):  
Dharu Dewi ◽  
Sriyana Sriyana
Keyword(s):  
Literature Review ◽  
Structural Steel ◽  
Research Methodology ◽  
Steel Industry ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
International Standards ◽  
Code Standard ◽  
Standard Steel

SPESIFIKASI, KODE DAN STANDAR BAJA NASIONAL DAN POTENSINYA UNTUK MENDUKUNG PROGRAM PLTN TIPE LWR DI INDONESIA. Spesifikasi, kode dan standar baja nasional sangat penting diidentifkasi agar dapat dicocokkan atau dibandingkan  dengan spesifikasi, kode dan standar internasional untuk komponen PLTN sehingga industri baja diharapkan dapat berpartisipasi dalam pembangunan Pembangkit Listrik Tenaga Nuklir (PLTN). Spesifikasi kode dan standar  baja mengacu pada ASTM, ASME, AISC dan lain - lain. Tujuan studi ini adalah mengidentifikasi  spesifikasi, kode dan standar baja yang dimiliki industri nasional dan kemudian dicocokkan dengan spesifikasi, kode dan standar baja sesuai standar internasional untuk PLTN. Metodologi penelitian adalah kajian literatur, pengiriman kuesioner, survei dan kunjungan teknis ke industri baja. Disimpulkan bahwa baja struktur pada dasarnya memenuhi persyaratan untuk konstruksi PLTN.Kata kunci: spesifikasi, kode, standar, baja, industriSPECIFICATION, CODE AND STANDARD OF NATIONAL STEEL AND THE POTENCY TO SUPPORT THE NUCLEAR POWER PROGRAMME OF LWR TYPE IN INDONESIA. Specification, codes and standards are important to identify in order to be matched or compared to international specifications, codes and standards for NPP components so that the steel industry is expected to participate in the construction of Nuclear Power Plants (NPPs). The specifications, code and standards of steel refer to ASTM, ASME, AISC and others. The purpose of this study is to identify specifications, codes and steel standards owned by national industries and then compared it to international standards for nuclear power plants. The research methodology is literature review, questionnaire submission, surveys and technical visits to the steel industry. It was concluded that the structural steel basically meets the requirements for NPP construction.Keywords: specification, code, standard, steel, industry

scholarly journals On Geological and Geophysical Safety of the New Safe Confinement for ChNPP-4

2016 ◽  
pp. 44-50
Author(s):  
V. Shestopalov ◽  
Iu. Shybetskyi
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Nuclear Facilities ◽  
Traditional Methods ◽  
Local Depression ◽  
Fault Structures ◽  
Potential Impact

The paper considers evidences and mechanisms of potential impact of local depression (microgeodynamic) zones on NPP safety. The depression forms were revealed within the Chornobyl NPP site, including location of the new safe confinement. Nature of zones and character of their influence is determined by fault structures and conjugated deep degassing processes, which cannot be detected and studied by traditional methods of engineering and exploration works during NPP siting. The assumption was made that significant and still unexplored risks for nuclear facilities are related to probable release of deep hydrogen through the bottom of depressions along sub-bottom channels. The approaches were proposed to studying the system of “depression with its sub-bottom channel” within the sites of Chornobyl NPP and other nuclear power plants.

scholarly journals The Work Results of the Institute for Safety Problems of Nuclear Power Plants of the NAS of Ukraine in 2020

2021 ◽  
Vol 20 ◽  
pp. 96-105
Author(s):  
V. S. Havrylenko ◽  
◽  
I. V. Kutsyna ◽  
D. I. Кhvalin ◽  
◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Spent Nuclear Fuel ◽  
Scientific Work ◽  
Development Effort ◽  
Nuclear Facilities ◽  
Energy Agency ◽  
Public Authorities ◽  
Organizational Activities

The year 2020 has become a real challenge for almost all aspects of life all over the world. Under these conditions, Ukrainian science, which has been in a state of crisis for more than a year, has been forced to overcome additional difficulties. However, due to the efforts of scientists, scientific work not only did not stop, but also received a large development effort in new directions and formats. In 2020, the Institute for Safety Problems of Nuclear Power Plants was one of the scientific institutions that under the new conditions made every effort to carry out the planned scientific researches and perform works in accordance with its activities. The main results of scientific and scientific-organizational activities of the Institute for Safety Problems of Nuclear Power Plants in 2020 are presented in the article. Despite the difficult economic situation due to the epidemic, the staff of the Institute obtained important results in studies of nuclear and radiation safety of the Shelter object, and in works aimed at improving the reliability and safety of existing Ukrainian and foreign nuclear power plants. The results of works in the field of the Shelter object transformation into an ecologically safe system, safe operation of nuclear facilities, decommissioning of nuclear facilities, spent nuclear fuel and radioactive waste management are presented in the article. The results of the work performed under the International Atomic Energy Agency (IAEA) grant and the Ukrainian-Japanese Science and Technology Research Partnership for Sustainable Development (SATREPS) project are described. The implementation of the results of these studies in practice is indicated. Scientific and expert activities in the interests and at the request of public authorities, cooperation with national and foreign scientific organizations as well as scientific and organizational activities in 2020 are described. Information on internal certification of employees, participation in international and national events, publishing and etc. is presented.

Sign in / Sign up

Export Citation Format

Share Document