Information Technology and the Development of a Global Safety Culture

2011 ◽  
pp. 558-581
Author(s):  
Susan L. Rothwell
Keyword(s):  
Information Technology ◽  
Safety Culture ◽  
Nuclear Power ◽  
Power Plants ◽  
Health And Safety ◽  
Lessons Learned ◽  
Energy Independence ◽  
Power Safety ◽  
Under Construction ◽  
Culture Development

A nuclear power plant is one of the most complex sociotechnical systems ever created, with operation requiring multiple organizations, extensive interaction, and a mission to protect public health and safety. A strong global nuclear power safety culture is important, with over 400 nuclear power plants worldwide and more under construction to reduce fossil fuel dependency. We increasingly rely on technology, stressing our need for energy independence, security, reliability, education, and safety. Lessons learned from nuclear power safety culture development have a large potential audience. Unfortunately, the complexity of nuclear power and restricted access to operational data have limited outside research on and understanding of nuclear power safety culture. This chapter provides a conceptual, methodological, empirical, and operational perspective on the development of commercial nuclear power safety culture, focusing on the role of information technology (IT) in building, maintaining, and expanding global nuclear power safety culture.

The IMS Development Plan in Construction Phase for Nuclear Power Plants

2010 ◽  
Author(s):  
Kyung Hwa Chung ◽  
Jae Hee Han
Keyword(s):  
Information Technology ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Construction Projects ◽  
Nuclear Power ◽  
Power Plants ◽  
Information Management System ◽  
Lessons Learned ◽  
3D Cad ◽  
Plant Construction

The implementation of advanced information technology for nuclear power plant construction industry in the Republic of Korea is a challenging task to improve the competitive edge for APR1400 across the global nuclear business market. This paper will briefly describe the phases of development of an information management system (hereinafter IMS) in nuclear power construction during the last 40 years in Korea. Additional development task which strengthen the IMS capability will be described from our experience. It will analyze the IMS development and implementation stages for Korean nuclear power plant construction projects such as YGN 3&4, UCN 3&4, YGN 5&6 and UCN 5&6, and the successful application case of the UCN 5&6 Radwaste Building in which 3D CAD technology was implemented for the first time. By reviewing lessons learned, this paper will define the Information Technology advancements resulting the reduction of project costs and construction schedule both by project execution procedures and IT systems including 3D CAD application. The future plan will include integrating project management systems based on data-centric approach and handover strategy for better O&M phase through configuration management technology. In this report, we address the functions to be developed and added in the new IMS.

scholarly journals Safety as Absolute Priority of Nuclear Power

10.12737/104 ◽  
2012 ◽  
Vol 1 (5) ◽  
pp. 10-18
Author(s):  
Пристер ◽  
B. Prister
Keyword(s):  
Safety Culture ◽  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Safe Operation ◽  
Absolute Priority ◽  
Severe Accidents ◽  
Fast Development ◽  
Power Safety

Nuclear power safety problems are considered. Need of continuous safety culture increasing and readiness of response to nuclear power plants failures which fast development leads to accident is shown. Analysis of severe accidents on nuclear power plants over last 50 years is presented. Necessity of development of systems for preventive readiness to failures, emergency reaction and ensuring the execution mechanism of international rules of nuclear power plants safe operation is proved.

Use of HFE Guidance for the Review of Nuclear Power Plants

2020 ◽  
Vol 64 (1) ◽  
pp. 1-5
Author(s):  
John O’Hara ◽  
Stephen Fleger
Keyword(s):  
Interface Design ◽  
Nuclear Power ◽  
Power Plants ◽  
Health And Safety ◽  
Nuclear Regulatory Commission ◽  
Program Review ◽  
Human Factors Engineering ◽  
Plant Design ◽  
Review Model ◽  
Regulatory Commission

The U.S. Nuclear Regulatory Commission (NRC) evaluates the human factors engineering (HFE) of nuclear power plant design and operations to protect public health and safety. The HFE safety reviews encompass both the design process and its products. The NRC staff performs the reviews using the detailed guidance contained in two key documents: the HFE Program Review Model (NUREG-0711) and the Human-System Interface Design Review Guidelines (NUREG-0700). This paper will describe these two documents and the method used to develop them. As the NRC is committed to the periodic update and improvement of the guidance to ensure that they remain state-of-the-art design evaluation tools, we will discuss the topics being addressed in support of future updates as well.

Expectations for Inservice Testing Programs at New Nuclear Power Plants

2017 ◽  
Author(s):  
Thomas G. Scarbrough
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Reactor Core ◽  
Nuclear Regulatory Commission ◽  
Lessons Learned ◽  
Mechanical Equipment ◽  
American Society ◽  
Regulatory Commission ◽  
Safety Systems

In a series of Commission papers, the U.S. Nuclear Regulatory Commission (NRC) described its policy for inservice testing (IST) programs to be developed and implemented at nuclear power plants licensed under 10 CFR Part 52. This paper discusses the expectations for IST programs based on those Commission policy papers as applied in the NRC staff review of combined license (COL) applications for new reactors. For example, the design and qualification of pumps, valves, and dynamic restraints through implementation of American Society of Mechanical Engineers (ASME) Standard QME-1-2007, “Qualification of Active Mechanical Equipment Used in Nuclear Power Plants,” as accepted in NRC Regulatory Guide (RG) 1.100 (Revision 3), “Seismic Qualification of Electrical and Active Mechanical Equipment and Functional Qualification of Active Mechanical Equipment for Nuclear Power Plants,” will enable IST activities to assess the operational readiness of those components to perform their intended functions. ASME has updated the Operation and Maintenance of Nuclear Power Plants (OM Code) to improve the IST provisions for pumps, valves, and dynamic restraints that are incorporated by reference in the NRC regulations with applicable conditions. In addition, lessons learned from performance experience and testing of motor-operated valves (MOVs) will be implemented as part of the IST programs together with application of those lessons learned to other power-operated valves (POVs). Licensee programs for the Regulatory Treatment of Non-Safety Systems (RTNSS) will be implemented for components in active nonsafety-related systems that are the first line of defense in new reactors that rely on passive systems to provide reactor core and containment cooling in the event of a plant transient. This paper also discusses the overlapping testing provisions specified in ASME Standard QME-1-2007; plant-specific inspections, tests, analyses, and acceptance criteria; the applicable ASME OM Code as incorporated by reference in the NRC regulations; specific license conditions; and Initial Test Programs as described in the final safety analysis report and applicable RGs. Paper published with permission.

scholarly journals Improvement of turbogenerators as a technical basis for ensuring the energy independence of Ukraine

2021 ◽  
pp. 19-30
Author(s):  
V. V. Shevchenko ◽  
A. N. Minko ◽  
M. Dimov
Keyword(s):  
Renewable Energy ◽  
Electric Power ◽  
Energy Security ◽  
Nuclear Power ◽  
Power Plants ◽  
Renewable Energy Sources ◽  
Electric Power Industry ◽  
Energy Sources ◽  
The World ◽  
Energy Independence

The paper defines the directions of improving turbogenerators as the basis for ensuring the energy independence of Ukraine. The analysis of the state, problems and prospects for the development of modern electric power industry. Goal of the work is to identify promising directions for sustainable development of the national electric power industry in order to ensure energy security of Ukraine, to conduct a comparative analysis of electricity sources, to confirm the need to improve the main sources – turbogenerators. Methodology. During the research, an analytical analysis of the electricity sources, which are installed at power plants in Ukraine and the world, was carried out, taking into account the growth of the planet's population and its energy activity. Cyclic theory was chosen as the theoretical basis for forecasting. On the basis of this theory, global development trends, advantages and disadvantages of currently used sources of electricity - thermal (including nuclear) power plants and stations that operate from renewable energy sources - have been established. A review of literary sources on the methods of the energy sector forecasting the development, including the development of the energy sector in Ukraine, has been carried out. Originality. It has been established that due to the active growth of the planet's population, with the increase in its energy activity, obtaining electricity from renewable energy sources is not enough, that for the next 20-30 years nuclear power plants will be the main sources of electricity. The internal and external threats to the energy security of Ukraine, directions of development of turbogenerator construction, ways to improve turbogenerators, to increase their energy efficiency, power per unit of performance, to increase the readiness and maneuverability factors, and overload capacity have been identified. Practical significance. The need to continue the modernization and improvement of the turbogenerators of nuclear power plant units, as the main sources of electricity, has been proved. The directions of their improvement are established: increasing the power in the established sizes, making changes to the design of the turbogenerators inactive elements, replacing the cooling agent to keep Ukrainian turbogenerators at the world level, improving auxiliary systems, improving and increasing the reliability of the excitation system, introduction of automatic systems for monitoring the state turbogenerators. Possible limits of use, advantages, disadvantages and problems of using renewable energy sources for Ukraine have been established.

scholarly journals Reactor performance, system reliability, instrumentation and control

2020 ◽  
Vol 6 ◽  
pp. 43
Author(s):  
Andreas Schumm ◽  
Madalina Rabung ◽  
Gregory Marque ◽  
Jary Hamalainen
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Nuclear Power Plants ◽  
Lessons Learned ◽  
Software Systems ◽  
Reactor Performance ◽  
Horizon 2020 ◽  
Term Operation ◽  
In The Beginning ◽  
Electrical Cables

We present a cross-cutting review of three on-going Horizon 2020 projects (ADVISE, NOMAD, TEAM CABLES) and one already finished FP7 project (HARMONICS), which address the reliability of safety-relevant components and systems in nuclear power plants, with a scope ranging from the pressure vessel and primary loop to safety-critical software systems and electrical cables. The paper discusses scientific challenges faced in the beginning and achievements made throughout the projects, including the industrial impact and lessons learned. Two particular aspects highlighted concern the way the projects sought contact with end users, and the balance between industrial and academic partners. The paper concludes with an outlook on follow-up issues related to the long term operation of nuclear power plants.

Research of Screening and Grading Method of Ageing Sensitive Objectives in Nuclear Power Plant

2014 ◽  
Vol 543-547 ◽  
pp. 858-861
Author(s):  
Xiao Tian Liu ◽  
Yong Wang ◽  
Shao Rui Niu ◽  
Yan Zhao Zhang ◽  
Zhen Hao Shi ◽  
...  
Keyword(s):  
Fuzzy Logic ◽  
Power Plant ◽  
Nuclear Power Plant ◽  
Nuclear Power ◽  
Power Plants ◽  
Lessons Learned ◽  
Nonlinear Coupling ◽  
Highly Nonlinear ◽  
Ageing Management ◽  
First Time

This first step of ageing management in nuclear power plant is to determine the objectives and their priorities. The characteristics of the objectives are complex and highly nonlinear coupling. A fuzzy logic based screening and grading method have been developed in this research for the first time which combined the genetic ageing lessons learned and field expert experience to resolve the problem. The method have been approved of highly applicability and applied to ageing management in multiple nuclear power plants.

Regulatory Issues of Digital I&C System in Lungmen Project

2004 ◽  
Author(s):  
C. F. Chuang ◽  
H. P. Chou
Keyword(s):  
Nuclear Power ◽  
State Of The Art ◽  
Lessons Learned ◽  
Digital Design ◽  
Regulatory Requirements ◽  
Power Station ◽  
Fully Integrated ◽  
Regulatory Issues ◽  
Under Construction ◽  
And Control

The Lungmen Nuclear Power Station (LNPS) is currently under construction in Taiwan, which consists of two advanced boiling water reactor (ABWR) units. The instrumentation and control (I&C) systems of the LNPS are based on the state-of-the-art modernized fully integrated digital design. This paper presents regulatory overviews, regulatory requirements, current major regulatory issues, as well as the areas of regulatory concerns and the lessons learned on the digital I&C systems in the Lungmen Project.

Post-Fukushima Research and Development Strategies and Priorities for Water Cooled Reactor Technology Development

2016 ◽  
Author(s):  
Katsumi Yamada ◽  
Abdallah Amri ◽  
Lyndon Bevington ◽  
Pal Vincze
Keyword(s):  
Research And Development ◽  
International Organizations ◽  
Nuclear Power ◽  
Power Plants ◽  
Development Strategies ◽  
Lessons Learned ◽  
Member States ◽  
North East ◽  
Severe Accidents ◽  
Fukushima Daiichi

The Great East Japan Earthquake and the subsequent tsunami on 11 March 2011 initiated accident conditions at several nuclear power plants (NPPs) on the north-east coast of Japan and developed into a severe accident at the Fukushima Daiichi NPP, which highlighted a number of nuclear safety issues. After the Fukushima Daiichi accident, new research and development (R&D) activities have been undertaken by many countries and international organizations relating to severe accidents at NPPs. The IAEA held, in cooperation with the OECD/NEA, the International Experts’ Meeting (IEM) on “Strengthening Research and Development Effectiveness in the Light of the Accident at the Fukushima Daiichi Nuclear Power Plant” at IAEA Headquarters in Vienna, Austria, 16–20 February 2015. The objective of the IEM was to facilitate the exchange of information on these R&D activities and to further strengthen international collaboration among Member States and international organizations. One of the main conclusions of the IEM was that the Fukushima Daiichi accident had not identified completely new phenomena to be addressed, but that the existing strategies and priorities for R&D should be reconsidered. Significant R&D activities had been already performed regarding severe accidents of water cooled reactors (WCRs) before the accident, and the information was very useful for predicting and understanding the accident progression. However, the Fukushima Daiichi accident highlighted several challenges that should be addressed by reconsidering R&D strategies and priorities. Following this IEM, the IAEA invited several consultants to IAEA Headquarters, Vienna, Austria, 12–14 May 2015, and held a meeting in order to discuss proposals on possible IAEA activities to facilitate international R&D collaboration in relation to severe accidents and how to effectively disseminate the information obtained at the IEM. The IAEA also held Technical Meeting (TM) on “Post-Fukushima Research and Development Strategies and Priorities” at IAEA Headquarters, Vienna, Austria, 15–18 December 2015. The objective of this meeting was to provide a platform for experts from Member States and international organizations to exchange perspectives and information on strategies and priorities for R&D regarding the Fukushima Daiichi accident and severe accidents in general. The experts discussed R&D topic areas that need further attention and the benefits of possible international cooperation. This paper discusses lessons learned from the Fukushima Daiichi accident based on the presentations and discussions at the meetings mentioned above, and identifies the needs for further R&D activities to develop WCR technologies to cope with Fukushima Daiichi-type accidents.

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