A Normal Accident or a Sea-Change? Nuclear Host Communities Respond to the 3/11 Disaster

2013 ◽  
Vol 14 (2) ◽  
pp. 261-276 ◽  
Author(s):  
DANIEL P. ALDRICH

AbstractWhile 3/11 has altered energy policies around the world, insufficient attention has focused on reactions from local nuclear power plant host communities and their neighbors throughout Japan. Using site visits to such towns, interviews with relevant actors, and secondary and tertiary literature, this article investigates the community crisis management strategies of two types of cities, towns, and villages: those which have nuclear plants directly in their backyards and neighboring cities further away (within a 30 mile radius). Responses to the disaster have varied with distance to nuclear facilities but in a way contrary to the standard theories based on the concept of the ‘distance decay function’. Officials in communities directly proximal to nuclear power plants by and large remain supportive of Japan's nuclear power program, while those in cities and towns at a distance (along with much of the general public) have displayed strong opposition to the pre 3/11 status quo. Using qualitative data, this article underscores how national energy and crisis response policies rest strongly on the political economy, experiences of, and decisions made at the subnational level.

2021 ◽  
Vol 19 (6) ◽  
pp. 541-559
Author(s):  
Ekong J. Peters, PhD ◽  
Caroline S. Hackerott, PhD ◽  
Weijia Jia, PhD

High-reliability organizations (HROs) including commercial airlines, the NASA Space Shuttle engineering team, US Naval aircraft carrier and nuclear submarine crews, and US nuclear power plants are relatively safe. However, these organizations experience system breakdowns often with catastrophic outcomes. This study focuses on risk information management strategies employed by a nuclear energy power plant located within 10 miles of a population center. The evacuation planning zone (EPZ) includes a hospital, several schools, and a public university. The nuclear plant provides written preparedness and evacuation information for all residents within the EPZ in the event of a radiological emergency. Focusing on the campus community within the EPZ, this study investigates individual awareness regarding the potential of a radiological event, the emergency information booklet, and the information provided within the booklet. We use descriptive statistics, frequency distribution, and cross tabulations (contingency tables) to establish awareness levels. Our study determines those participants who read the emergency instructions booklet are prepared to make an informed decision in the event of a radiological incident. We find college affiliation, educational level, university role, and age significantly related to emergency instruction booklet utilization. We also find gender is significantly linked to overall risk perception regarding a radiological event. Findings support previous research regarding women’s higher levels of risk aversion and pessimism involving dangerous new risky technologies and activities like nuclear energy plants. These findings support modifying policy to ensure nuclear facilities assess the efficacy of their warning systems in alerting the public. Furthermore, our findings provide guidance regarding the evaluation of the effectiveness of emergency instruction booklet distribution.


2020 ◽  
Vol 20 (2) ◽  
pp. 127-132
Author(s):  
Namjin Cho ◽  
Dongsu Im ◽  
Jungdon Kwon ◽  
Teayeon Cho ◽  
Junglim Lee

Nuclear power plants store and use flammable gases and liquids and consequently risk explosions. Therefore, nuclear plants employ explosion-proof equipment; however, this equipment is not always sufficiently maintained. This lack of maintenance can affect the safety-related equipment intended to shut down the reactor, because the explosion-proof equipment itself can act as an ignition source. Radio-frequency identification (RFID) technology should be explored as a tool to improve both the convenience and efficiency of maintenance. We analyzed and compared explosion-proof RFID technology that can be used in nuclear power plants.


Author(s):  
Steve Thomas

- UK electricity consumers have paid provisions for decommissioning since before 1980 but by 2002, there were still negligible funds available to pay for decommissioning civil nuclear facilities. By then, the two major UK nuclear companies, British Energy and British Nuclear Fuels Limited (BNFL), were both effectively bankrupt. This paper examines: the pre-2002 provisions for decommissioning and how they were lost; the Nuclear Decommissioning Authority, a new public body which took over ownership of BNFL's facilities including the duty to manage their decommissioning and how it expects to carry out and fund decommissioning of its sites; how the re-launched British Energy will contribute to decommissioning its eight plants; and government plans for collecting decommissioning provisions for any new plants.JEL classifications: L50, L38, H23, H44, L71Key words: Nuclear power, decommissioning cost, funding and polluter pays.


Author(s):  
Oleksandr Klevtsov ◽  
Artem Symonov ◽  
Serhii Trubchaninov

The chapter is devoted to the issues of cyber security assessment of instrumentation and control systems (I&C systems) of nuclear power plants (NPP). The authors examined the main types of potential cyber threats at the stages of development and operation of NPP I&C systems. Examples of real incidents at various nuclear facilities caused by intentional cyber-attacks or unintentional computer errors during the maintenance of the software of NPP I&C systems are given. The approaches to vulnerabilities assessment of NPP I&C systems are described. The scope and content of the assessment and periodic reassessment of cyber security of NPP I&C systems are considered. An approach of assessment to cyber security risks is described.


2019 ◽  
Vol 186 (4) ◽  
pp. 524-529
Author(s):  
Si Young Kim

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.


2016 ◽  
Vol 7 (2) ◽  
pp. 42-49
Author(s):  
Nick Shykinov ◽  
Robert Rulko ◽  
Dariusz Mroz

Abstract In the context of energy demands by growing economies, climate changes, fossil fuel pricing volatility, and improved safety and performance of nuclear power plants, many countries express interest in expanding or acquiring nuclear power capacity. In the light of the increased interest in expanding nuclear power the supply chain for nuclear power projects has received more attention in recent years. The importance of the advanced planning of procurement and manufacturing of components of nuclear facilities is critical for these projects. Many of these components are often referred to as long-lead items. They may be equipment, products and systems that are identified to have a delivery time long enough to affect directly the overall timing of a project. In order to avoid negatively affecting the project schedule, these items may need to be sourced out or manufactured years before the beginning of the project. For nuclear facilities, long-lead items include physical components such as large pressure vessels, instrumentation and controls. They may also mean programs and management systems important to the safety of the facility. Authorized nuclear operator training, site evaluation programs, and procurement are some of the examples. The nuclear power industry must often meet very demanding construction and commissioning timelines, and proper advanced planning of the long-lead items helps manage risks to project completion time. For nuclear components there are regulatory and licensing considerations that need to be considered. A national nuclear regulator must be involved early to ensure the components will meet the national legal regulatory requirements. This paper will discuss timing considerations to address the regulatory compliance of nuclear long-lead items.


Author(s):  
David Bradbury ◽  
George R. Elder ◽  
John C. Ritchie ◽  
Robert G. Ward

Decommissioning of retired nuclear plants and facilities demands the proper management of the process, both for economic reasons and for retaining public confidence in the continued use of nuclear power for electricity generation. There are significant potential benefits, both economic and environmental, in recycling materials from retired nuclear facilities for new uses rather than disposing of them as radioactive waste. Although it is technically possible to decontaminate many retired nuclear components to reduce contamination levels to below those appropriate for free release into the public domain, there is some public unease at the prospect of formerly contaminated materials passing into unrestricted public use. Greater support for recycle can be achieved by converting decontaminated materials into products for new controlled uses, particularly within the nuclear industry. Irrespective of the future of nuclear power, the industry has a need for many new items such as waste containers, replacement components etc. Good economics can be achieved by decontaminating the materials and then using existing non-radioactive manufacturing facilities for fabrication of new components. Provided that materials have first been decontaminated to below unrestricted release levels, there is no objection in principle to using non-radioactive facilities for recycling and manufacturing activities, so long as the materials are properly tracked to prevent their uncontrolled release. Surface decontamination has an important role to play in these activities. Efficient and economic decontamination processes are needed to prepare materials for recycle. The EPRI DFDX Process is a process for achieving these objectives. Recent progress with this process is described.


Author(s):  
Sangmyeon Ahn ◽  
Jungjoon Lee ◽  
Chanwoo Jeong ◽  
Kyungwoo Choi

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.


Author(s):  
Danying Gu ◽  
Shuhui Zhang ◽  
Zhonghe Ning

The reviewing of operating experience at nuclear power plants (NPP) is not only critically important to safe and reliable operations, but also useful to guide the design of new plants which are similar to the current one under review. How to identify and analyze the safety-related operating experience and then implement a more extensive review is a vital and challengeable issue. In this paper, a methodology of human factor engineering (HFE) operating experience review (OER) is proposed for NPP. The need for the application of HFE in the life cycle activities of NPP and other nuclear facilities has been demonstrated by plant operating histories and regulatory and industry reviews. As a very important element of HFE, the OER is performed from the beginning of the design process. The main purpose of performing an OER is to verify that the applicant has identified and analyzed HFE-related safety problems and issues in previous designs that are similar to the current one. In this way, negative features associated with predecessor designs may be avoided in the current NPP design while retaining positive features. The research of OER concentrates on the aspect of review criterion, scope and implementation procedure of the HFE-related operating experience. As the NRC requirement, the scope of operating experience can be divided into six types in accordance with sources of information. The implementation procedures of USA and China are introduced, respectively. The resolution of HFE OER issues involve function allocation, changes in automation, HSI equipment design, procedures, training, and so forth. The OER conclusions can contribute to other HFE activities and improve the safety, reliability and usability of the HSI design in NPP.


Author(s):  
J. Douglas Hill ◽  
Paul Moore

Nuclear power plants rely on Instrumentation and Control (I&C) systems for control, monitoring and protection of the plant. The original, analog designs used in most nuclear plants have become or soon will be obsolete, forcing plants to turn to digital technology. Many factors affect the design of replacement equipment, including long-term and short-term economics, regulatory issues, and the way the plant operates on a day-to-day basis. The first step to all modernization projects should involve strategic planning, to ensure that the overall long and short-term goals of the plant are met. Strategic planning starts with a thorough evaluation of the existing plant control systems, the available options, and the benefits and consequences of these options.


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