Emergency power systems at nuclear power plants

International Nuclear Information System (INIS)

1982-01-01

This Guide applies to nuclear power plants for which the total power supply comprises normal power supply (which is electric) and emergency power supply (which may be electric or a combination of electric and non-electric). In its present form the Guide provides general guidance for all types of emergency power systems (EPS) - electric and non-electric, and specific guidance (see Appendix A) on the design principles and the features of the emergency electric power system (EEPS). Future editions will include a second appendix giving specific guidance on non-electric power systems. Section 3 of this Safety Guide covers information on considerations that should be taken into account relative to the electric grid, the transmission lines, the on-site electrical supply system, and other alternative power sources, in order to provide high overall reliability of the power supply to the EPS. Since the nuclear power plant operator does not usually control off-site facilities, the discussion of methods of improving off-site reliability does not include requirements for facilities not under the operator's control. Sections 4 to 11 of this Guide provide information, recommendations and requirements that would apply to any emergency power system, be it electric or non-electric

Planning of emergency medical treatment in nuclear power plant

International Nuclear Information System (INIS)

Kusama, Tomoko

1989-01-01

Medical staffs and health physicists have shown deep concerning at the emergency plans of nuclear power plants after the TMI nuclear accident. The most important and basic countermeasure for accidents was preparing appropriate and concrete organization and plans for treatment. We have planed emergency medical treatment for radiation workers in a nuclear power plant institute. The emergency medical treatment at institute consisted of two stages, that is on-site emergency treatment at facility medical service. In first step of planning in each stage, we selected and treatment at facility medical service. In first step of planning in each stage, we selected and analyzed all possible accidents in the institute and discussed on practical treatments for some possible accidents. The manuals of concrete procedure of emergency treatment for some accidents were prepared following discussion and facilities and equipment for medical treatment and decontamination were provided. All workers in the institute had periodical training and drilling of on-site emergency treatment and mastered technique of first aid. Decontamination and operation rooms were provided in the facillity medical service. The main functions at the facility medical service have been carried out by industrial nurses. Industrial nurses have been in close co-operation with radiation safety officers and medical doctors in regional hospital. (author)

A study on emergency preparedness for nuclear power plant/ Establishment of emergency communication network system

International Nuclear Information System (INIS)

Yang, Y. K.; Jung, Y. D.; Kim, S. Y.

1991-12-01

The objective of this study was to develop an emergency database search system for nuclear power plants during nuclear incidents / accidents. Image data reported from nuclear power plants to the regulatory body and other related data will be stored systematically in the computer. The data will be utilized during nuclear emergency to prevent the accident from spreading out and to minimize its effect. It will also be used in exchanging information on accident or incidents with the foreign countries. The operational documents in the Kori-4 nuclear power plant are used as the major source for the categorization and analysis in performing this research. It was not easy to access the detailed operational data due to its unique characteric for the security. Therefore, we strongly suggest to increase manpower for this project in Korea Institute of Nuclear Safety (KINS) and archive involvement from Korea Electric Power Company to establish better database retrieval system

A study on emergency preparedness for nuclear power plant/ Establishment of emergency communication network system

Energy Technology Data Exchange (ETDEWEB)

Yang, Y K; Jung, Y D; Kim, S Y [Korea Institute of Science and Technology, Seoul (Korea, Republic of)

1991-12-15

The objective of this study was to develop an emergency database search system for nuclear power plants during nuclear incidents / accidents. Image data reported from nuclear power plants to the regulatory body and other related data will be stored systematically in the computer. The data will be utilized during nuclear emergency to prevent the accident from spreading out and to minimize its effect. It will also be used in exchanging information on accident or incidents with the foreign countries. The operational documents in the Kori-4 nuclear power plant are used as the major source for the categorization and analysis in performing this research. It was not easy to access the detailed operational data due to its unique characteric for the security. Therefore, we strongly suggest to increase manpower for this project in Korea Institute of Nuclear Safety (KINS) and archive involvement from Korea Electric Power Company to establish better database retrieval system.

Emergency preparedness post-9/11 enhancements at US nuclear plants

International Nuclear Information System (INIS)

Sullivan, R.L.

2005-01-01

Full text: In the wake of the terrorist attacks of 9-11, the US Nuclear Regulatory Commission (NRC) took several actions to improve the security profile and emergency response of its licensees. In early 2002 the commission issued orders to its nuclear power plant licensees which included changes to emergency plans, the performance of staffing adequacy reviews, changes to augmentation practices and the establishment of alternative facilities. Since that time NRC has implemented a force-on-force exercise program that includes emergency response. This program has helped licensees improve their response by testing procedures under simulated attack conditions. More recently, licensees have begun a program to enhance drills and exercises through the use of security event based scenarios. These drills will enhance previous practice and focus on two emerging issues: improving the interface between emergency response, security response and operations during security events and recovery from the loss of plant equipment due to terrorist acts. Additional areas of enhancement such as protective actions for plant personnel will also be discussed and the status of actions to date will be provided. (author)

National radiological emergency response to the Fukushima Daiichi Nuclear Power Plant accident

International Nuclear Information System (INIS)

Dela Rosa, Alumanda M.

2011-01-01

The Fukushima nuclear power plant accident occurred on March 11, 2011, when two natural disasters of unprecedented strengths, an earthquake with magnitude 9 followed one hour later by a powerful tsunami struck northeastern Japan and felled the external power supply and the emergency diesel generators of the Fukushima Daiichi nuclear power station, resulting in a loss of coolant accident. There were core meltdowns in three nuclear reactors with the release of radioactivity estimated to be 1/10 of what was released to the environment during the Chernobyl nuclear power plant accident in April 1986. The Fukushima nuclear accident tested the capability of the Philippine Nuclear Research Institute (PNRI) and the National Disaster Risk Reduction and Management Council (NDRRMC) in responding to such radiological emergency as a nuclear power plant accident. The PNRI and NDRRMC activated the RADPLAN for possible radiological emergency. The emergency response was calibrated to the status of the nuclear reactors on site and the environmental monitoring undertaken around the site and off-site, including the marine environment. This orchestrated effort enabled the PNRI and the national agencies concerned to reassure the public that the nuclear accident does not have a significant impact on the Philippines, both on the health and safety of the people and on the safety of the environment. National actions taken during the accident will be presented. The role played by the International Atomic Energy Agency as the central UN agency for nuclear matters will be discussed. (author)

The nuclear emergency plans

International Nuclear Information System (INIS)

Fuertes Menendez, M. J.; Gasco Leonarte, L.; Granada Ferrero, M. J.

2007-01-01

Planning of the response to emergencies in nuclear plants is regulated by the Basic Nuclear Emergency Plan (PLABEN). This basic Plan is the guidelines for drawing up, implementing and maintaining the effectiveness of the nuclear power plant exterior nuclear emergency plans. The five exterior emergency plans approved as per PLABEN (PENGUA, PENCA, PENBU, PENTA and PENVA) place special emphasis on the preventive issues of emergency planning, such as implementation of advance information programs to the population, as well as on training exercises and drills. (Author)

Emergency core cooling systems in CANDU nuclear power plants

International Nuclear Information System (INIS)

1981-12-01

This report contains the responses by the Advisory Committee on Nuclear Safety to three questions posed by the Atomic Energy Control Board concerning the need for Emergency Core Cooling Systems (ECCS) in CANDU nuclear power plants, the effectiveness requirement for such systems, and the extent to which experimental evidence should be available to demonstrate compliance with effectiveness standards

Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography

Energy Technology Data Exchange (ETDEWEB)

Youngen, G.

1988-10-01

The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant`s operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ``onsite`` response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world`s collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously.

Emergency Preparedness and Response at Nuclear Power Plants in Pakistan

Energy Technology Data Exchange (ETDEWEB)

Khan, L. A.; Qamar, M. A.; Liaquat, M.R., E-mail: samasl@yahoo.com [Pakistan Atomic Energy Commission, Islamabad (Pakistan)

2014-10-15

Emergency preparedness and response arrangements at Nuclear Power Plants (NPPs) in Pakistan have been reevaluated in the light of Fukushima Daiichi accident. Appropriate measures have been taken to strengthen and effectively implement the on-site and off-site emergency plans. Verification of these plans is conducted through regulatory review and by witnessing periodic emergency drills and exercises conducted by the NPPs in the fulfilment of the regulatory requirements. Emergency Planning Zones (EPZs) have been revised at NPPs. A multi discipline reserve force has been formed for assistance during severe accidents. Nuclear Emergency Management System (NEMS) has been established at the national level in order to make necessary arrangements for responding to nuclear and radiological emergencies. Training programs for first responders and medical professionals have been launched. Emergencies coordination centres have been established at national and corporate levels. Public awareness program has been initiated to ensure that the surrounding population is provided with appropriate information on emergency planning and response. To share national and international operational experience, Pakistan has arranged various workshops and developed a strong link with International Atomic Energy Agency (IAEA). (author)

Nuclear emergency buildings of Asco and Vandellos II nuclear power plants; Centros alternativos de emergencias de las centrales nucleares de Asco y Vandellos II

Energy Technology Data Exchange (ETDEWEB)

Massuet, J.; Sabater, J.; Mirallas Esteban, S.

2016-08-01

The Nuclear Emergency Buildings sited at Asco and Vandellos II Nuclear Power Plants (NPP) are designed to safety manage emergencies in extreme situations, beyond the design basis of the Nuclear Power Plants. Designed in accordance with the requirements of the Spanish Nuclear Regulator (Consejo de Seguridad Nuclear-CSN) these buildings are ready to operate over a period of 72 hours without external assistance and ensure habitability for crews of 120 and 70 people respectively. This article describes the architectural conception, features and major systems of the Nuclear Emergency Buildings sited at Asco and Vandellos II. (Author)

Development and application of emergency operating procedures for nuclear power plants

International Nuclear Information System (INIS)

Lin Chengge

1990-01-01

The development and application of emergency operating procedures (EOPs) is an important measure to assure the operational safety for nuclear power plants. Event-oriented, symptom-, function- and state-oriented EOPs with their structures, interfaces, development procedures and practical application are described. The ideas and approach can be available for the preparation of EOPs for nuclear power plants which are going to be in service

Improvements around nuclear power plants for effective implementation of emergency countermeasures

International Nuclear Information System (INIS)

Srivasista, K.; Ravi, K.; Gupta, S.K.

2011-01-01

The 5 km sterilized zone (SZ) and 16 km emergency planning zone (EPZ) were set up for Indian nuclear power plants in 1960s. There is also a requirement that the growth of population in SZ shall be controlled. In the current scenario where population growth in SZ at some of the sites is much above the natural growth, the distinction between the two zones may disappear. It is clear that emergency preparedness plans shall be in place for these zones. In today's context if these numbers have to be revised, there is a need to give a fresh look to the basis and growth of population in these zones. In view of this, the issue of size and requirement of SZ and EPZ in Indian context are revisited. Technological advances and emerging improvements in some of the elements of emergency response were reviewed to determine their potential effects on decisions of emergency protective actions. Some such elements which affect implementation of emergency countermeasures effectively in SZ and EPZ around Indian nuclear power plants are discussed in this paper. (author)

Comparison between Different Power Sources for Emergency Power Supply at Nuclear Power Plants

International Nuclear Information System (INIS)

Lenasson, Magnus

2015-01-01

Currently the Swedish nuclear power plants are using diesel generator sets and to some extent gas turbines as their emergency AC power sources and batteries as their emergency DC power sources. In the laws governing Swedish nuclear activity, no specific power sources are prescribed. On the other hand, diversification of safety functions should be considered, as well as simplicity and reliability in the safety systems. So far the choices of emergency power sources have been similar between different power plants, and therefore this project investigated a number of alternative power sources and if they are suitable for use as emergency power on nuclear power plants. The goals of the project were to: - Define the parameters that are essential for rending a power source suitable for use at a nuclear power plant. - Present the characteristics of a number of power sources regarding the defined parameters. - Compile the suitability of the different power sources. - Make implementation suggestions for the less conventional of the investigated power sources. (unconventional in the investigated application) 10 different power sources in total have been investigated and to various degrees deemed suitable Out of the 10 power sources, diesel generators, batteries and to some extent gas turbines are seen as conventional technology at the nuclear power plants. In relation to them the other power sources have been assessed regarding diversification gains, foremost with regards to external events. The power sources with the largest diversification gains are: Internal steam turbine, Hydro power, Thermoelectric generators. The work should first and foremost put focus on the fact that under the right circumstances there are power sources that can complement conventional power sources and yield substantial diversification gains. This paper is a shortened version of the report 'Comparison between different power sources for emergency power supply at nuclear power plants'. The

Community emergency response to nuclear power plant accidents: A selected and partially annotated bibliography

International Nuclear Information System (INIS)

Youngen, G.

1988-10-01

The role of responding to emergencies at nuclear power plants is often considered the responsibility of the personnel onsite. This is true for most, if not all, of the incidents that may happen during the course of the plant's operating lifetime. There is however, the possibility of a major accident occurring at anytime. Major nuclear accidents at Chernobyl and Three Mile Island have taught their respective countries and communities a significant lesson in local emergency preparedness and response. Through these accidents, the rest of the world can also learn a great deal about planning, preparing and responding to the emergencies unique to nuclear power. This bibliography contains books, journal articles, conference papers and government reports on emergency response to nuclear power plant accidents. It does not contain citations for ''onsite'' response or planning, nor does it cover the areas of radiation releases from transportation accidents. The compiler has attempted to bring together a sampling of the world's collective written experience on dealing with nuclear reactor accidents on the sate, local and community levels. Since the accidents at Three Mile Island and Chernobyl, that written experience has grown enormously

Meteorological considerations in emergency response capability at nuclear power plant

International Nuclear Information System (INIS)

Fairobent, J.E.

1985-01-01

Meteorological considerations in emergency response at nuclear power plants are discussed through examination of current regulations and guidance documents, including discussion of the rationale for current regulatory requirements related to meteorological information for emergency response. Areas discussed include: major meteorological features important to emergency response; onsite meteorological measurements programs, including redundant and backup measurements; access to offsite sources of meteorological information; consideration of real-time and forecast conditions and atmospheric dispersion modeling

Modifications of Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany based upon new version of Emergency Operating Procedures

International Nuclear Information System (INIS)

Aldorf, R.

1997-01-01

In the frame of 'living Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany Project' being performed by Nuclear Research Institute Rez during 1997 is planned to reflect on Probabilistic Safety Assessment-1 basis on impact of Emergency Response Guidelines (as one particular event from the list of other modifications) on Plant Safety. Following highlights help to orient the reader in main general aspects, findings and issues of the work that currently continues on. Older results of Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany have revealed that human behaviour during accident progression scenarios represent one of the most important aspects in plant safety. Current effort of Nuclear Power Plants Dukovany (Czech Republic) and Bohunice (Slovak Republic) is focussed on development of qualitatively new symptom-based Emergency Operating Procedures called Emergency Response Guidelines Supplier - Westinghouse Energy Systems Europe, Brussels works in cooperation with teams of specialist from both Nuclear Power Plants. In the frame of 'living Probabilistic Safety Assessment-1 Nuclear Power Plant Dukovany Project' being performed by Nuclear Research Institute Rez during 1997 is planned to prove on Probabilistic Safety Assessment -1 basis an expected - positive impact of Emergency Response Guidelines on Plant Safety, Since this contract is currently still in progress, it is possible to release only preliminary conclusions and observations. Emergency Response Guidelines compare to original Emergency Operating Procedures substantially reduce uncertainty of general human behaviour during plant response to an accident process. It is possible to conclude that from the current scope Probabilistic Safety Assessment Dukovany point of view (until core damage), Emergency Response Guidelines represent adequately wide basis for mitigating any initiating event

The knowledge-based off-site emergency response system for a nuclear power plant

International Nuclear Information System (INIS)

Ho, L.W.; Loa, W.W.; Wang, C.L.

1987-01-01

A knowledge-based expert system for a nuclear power plant off-site emergency response system is described. The system incorporates the knowledge about the nuclear power plant behaviours, site environment and site geographic factors, etc. The system is developed using Chinshan nuclear power station of Taipower Company, Taiwan, ROC as a representative model. The objectives of developing this system are to provide an automated intelligent system with functions of accident simulation, prediction and with learning capabilities to supplement the actions of the emergency planners and accident managers in order to protect the plant personnel and the surrounding population, and prevent or mitigate property damages resulting from the plant accident. The system is capable of providing local and national authorities with rapid retrieval data from the site characteristics and accident progression. The system can also provide the framework for allocation of available resources and can handle the uncertainties in data and models

Safety assessment of emergency power systems for nuclear power plants

International Nuclear Information System (INIS)

1992-01-01

This publication is intended to assist the safety assessor within a regulatory body, or one working as a consultant, in assessing the safety of a given design of the emergency power systems (EPS) for a nuclear power plant. The present publication refers closely to the NUSS Safety Guide 50-SG-D7 (Rev. 1), Emergency Power Systems at Nuclear Power Plants. It covers therefore exactly the same technical subject as that Safety Guide. In view of its objective, however, it attempts to help in the evaluation of possible technical solutions which are intended to fulfill the safety requirements. Section 2 clarifies the scope further by giving an outline of the assessment steps in the licensing process. After a general outline of the assessment process in relation to the licensing of a nuclear power plant, the publication is divided into two parts. First, all safety issues are presented in the form of questions that have to be answered in order for the assessor to be confident of a safe design. The second part presents the same topics in tabulated form, listing the required documentation which the assessor has to consult and those international and national technical standards pertinent to the topics. An extensive reference list provides information on standards. 1 tab

Development of computerized supporting system for emergency response in nuclear power plant

International Nuclear Information System (INIS)

Lee, Jae Il

1992-02-01

In emergency situation of nuclear power plants, effective use of emergency operating procedures (EOPs) is a crucial part of the emergency response process. However, there are several problems in the emergency operating procedures because of the form of the written procedures. They are voluminous and complicate for effective references under high stress situation. Inevitably, it takes time that could be better spent employing measures to control and stabilize to select the correct procedures and apply the decision logic. In this study, a computerized supporting system has been developed to reduce the operator error possibility under emergency situations of nuclear power plant. Using on-line input parameters, the system can determine the status of the critical safety functions and can find appropriate procedures and necessary operator actions automatically. Moreover, the system can help the operator decision making in the core melt accident situation. By tracking the EOP in an on-line mode, most steps concerning checking or verifying plant state are processed automatically without operator participations. Therefore, the interactions between the system and the operator are simplified significantly and the possibility of human error is reduced

Trend analyses of the emergency diesel generator problem events in Japanese and U.S. nuclear power plants

International Nuclear Information System (INIS)

Shimada, Yoshio

2011-01-01

Up to 2009, the author and a colleague conducted trend analyses of problem events related to main generators, emergency diesel generators, breakers, motors and transformers which are more likely to cause problems than other electric components in nuclear power plants. Among the electric components with high frequency of defect occurrence, i.e., emergency diesel generators, several years have passed since the last analyses. These are very important components needed to stop a nuclear reactor safely and to cool it down during external power supply loses. Then trend analyses were conducted for the second time. The trend analyses were performed on 80 problem events with emergency diesel generators which had occurred in U.S. nuclear power plants in the five years from 2005 through 2009 among events reported in the Licensee Event Reports (LERs: event reports submitted to NRC by U.S. nuclear power plants) which have been registered in the nuclear information database of the Institute of Nuclear Safety System, Inc. (INSS) , as well as 40 events registered in the Nuclear Information Archives (NUCIA), which occurred in Japanese nuclear power plants in the same time period. It was learned from the trend analyses of the problem events with emergency diesel generators that frequency of defect occurrence are high in both Japanese and US plants during plant operations and functional tests (that is, defects can be discovered effectively in advance), so that implementation of periodical functional tests under plant operation is an important task for the future. (author)

Emergency preparedness exercise ''Posavje 82'' in support of the Krsko Nuclear Power Plant, Krsko, Yugoslavia

International Nuclear Information System (INIS)

Collins, H.E.; Emmerson, B.W.

1983-06-01

In October 1982, the Yugoslavian Government requested the Agency's assistance in observing and evaluating an emergency preparedness exercise (code named ''POSAVJE 82'') on 5 and 6 November 1982, to test emergency plans and arrangements supportive of the KRSKO Nuclear Power Plant. The Krsko Nuclear Power Plant is a single unit pressurized water reactor of United States (Westinghouse) design rated at 664 MWe (Gross) and is located at Krsko, Socialist Republic of Slovenia, Yugoslavia. This assistance was provided by sending a Special Assistance Mission team of experts under the general provisions of the Agency's circular letter SC/651-3 of 7 April 1981 to Member States which offered such assistance upon request. This mission was a follow-up to a previous mission requested by the Yugoslavian Government which was conducted 24 June - 1 July 1981. At that time, the mission consisted of examining the then existing arrangements for emergency planning in support of the KRSKO Nuclear Power Plant at the National, Republic, local and nuclear power plant levels and discussing with Yugoslavian authorities criteria for emergency plan development and improvement. As a result of this 1981 mission, a ''Report to the Goverment of Yugoslavia'' (IAEA TA Report 1827 of 17 September 1981) was transmitted to the Yugoslavian Government. This report set forth a number of recommendations for improving and further developing the various emergency plans and arrangements for the KRSKO Nuclear Power Plant. A summary of the major recommendations contained in the report is given in Section 2.2. The entire report is listed as Reference 1 of Annex A

Emergency response and nuclear risk governance. Nuclear safety at nuclear power plant accidents; Notfallschutz und Risk Governance. Zur nuklearen Sicherheit bei Kernkraftwerksunfaellen

Energy Technology Data Exchange (ETDEWEB)

Kuhlen, Johannes

2014-07-01

The present study entitled ''Emergency Response and Nuclear Risk Governance: nuclear safety at nuclear power plant accidents'' deals with issues of the protection of the population and the environment against hazardous radiation (the hazards of nuclear energy) and the harmful effects of radioactivity during nuclear power plant accidents. The aim of this study is to contribute to both the identification and remediation of shortcomings and deficits in the management of severe nuclear accidents like those that occurred at Chernobyl in 1986 and at Fukushima in 2011 as well as to the improvement and harmonization of plans and measures taken on an international level in nuclear emergency management. This thesis is divided into a theoretical part and an empirical part. The theoretical part focuses on embedding the subject in a specifically global governance concept, which includes, as far as Nuclear Risk Governance is concerned, the global governance of nuclear risks. Due to their characteristic features the following governance concepts can be assigned to these risks: Nuclear Safety Governance is related to safety, Nuclear Security Governance to security and NonProliferation Governance to safeguards. The subject of investigation of the present study is as a special case of the Nuclear Safety Governance, the Nuclear Emergency governance, which refers to off-site emergency response. The global impact of nuclear accidents and the concepts of security, safety culture and residual risk are contemplated in this context. The findings (accident sequences, their consequences and implications) from the analyses of two reactor accidents prior to Fukushima (Three Mile Iceland in 1979, Chernobyl in 1986) are examined from a historical analytical perspective and the state of the Nuclear Emergency governance and international cooperation aimed at improving nuclear safety after Chernobyl is portrayed by discussing, among other topics, examples of &apos

Strainer device for an emergency cooling system in a nuclear power plant

International Nuclear Information System (INIS)

Trybom, J.

1997-01-01

The invention relates to a strainer device for separating contaminants from water in an emergency cooling system for a nuclear power plant. The nuclear power plant has a wet-well for water in the emergency cooling system and the strainer device comprises at least one strainer device, which is arranged in the wet-well. According to the invention the strainer is suspended in a desired position in the wet-well by means of at least a group of at least three tie rods arranged at angles to each other, each tie rod being fixed at one end to the strainer and its other end to the container or an anchor ring joined thereto. (author) figs

Emergency power systems at nuclear power plants

International Nuclear Information System (INIS)

1991-01-01

This Safety Guide was prepared as part of the Nuclear Safety Standards programme for establishing Codes and Safety Guides relating to nuclear power plants (NPPs). The first edition of the present Safety Guide was developed in the early 1980s. The text has now been brought up-to-date, refined in several details and amended to include non-electrical diverse and independent power sources. This Guide applies to NPP for which the total power supply comprises a normal power supply and an emergency power supply (EPS), which may be electrical or a combination of electrical and non-electrical. The Guide provides general guidance for all types of EPS and specific guidance on the design safety requirements and the features of the electrical and non-electrical portions of the EPS. 9 figs, 2 tabs

New fire and security rules change USA nuclear power plant emergency plans

International Nuclear Information System (INIS)

Garrou, A.L.

1978-01-01

New safety and security rules for nuclear power plants have resulted from the Energy Reorganisation Act and also from a review following the Browns Ferry fire. The content of the emergency plan which covers personnel, plant, site, as well as a general emergency, is outlined. New fire protection rules, the plan for security, local and state government assistance are also discussed, with a brief reference to the impact of the new rules on continuity of operations. (author)

Use of a life simulator and SPDS for a nuclear plant emergency preparedness exercise

International Nuclear Information System (INIS)

Thayer, D.; Anderson, J.; Goldman, S.

1990-01-01

This paper reports that in one of the first such efforts in the nuclear industry, Perry Nuclear Power Plant (PNPP) engineered its Control Room Simulator system to provide real-time live scenario data to the PNPP Safety Parameter Display System (SPDS) during its 1989 Nuclear Regulatory Commission (NRC) Evaluated Emergency Preparedness Exercise. A Scenario Team developed realistic scenarios built upon exercise objectives coupled with Simulator capabilities. Free play by participants was an underlying objective of the Scenario Team. For the exercise, the Simulator SPDS was connected via telephone lines and modems to actual SPDS display units in two remote facilities: the Technical Support Center (TSC) and Emergency Operations Facility (EOF). Since the PNPP Simulator does not presently model radiological parameters, radiological data was input separately from plant scenario thermodynamic/mechanical/electrical data. During the exercise, plant operators at the Simulator manipulated plant controls to start/stop components or systems as needed for the exercise conditions. Players in the TSC and EOF were able to see and track plant conditions on a real-time basis

A computerized assessment and response system for radiological emergency at Diablo Canyon Nuclear Power Plant

International Nuclear Information System (INIS)

Shih, C.C.; Thuillier, R.H.

1984-01-01

The U.S. Nuclear Regulatory Commission requires that nuclear power plants provide for rapid assessment and response in the event of a radiological emergency. At the Diablo Canyon Nuclear Power Plant, Pacific Gas and Electric Company uses a system of linked central minicomputer, satellite desktop computers and microprocessors to provide decision makers with timely and pertinent information in emergency situations. The system provides for data acquisition and microprocessing at meteorological and radiological monitoring sites. Current estimates or projections of offsite dose commitment are made in real-time by a dispersion/dose calculation model. Computerized dissemination of data and calculational results to decision makers at the government and utility levels is also available. The basic system in use is a commercially available Emergency Assessment and Response System (EARS). This generic system has been modified in-house to meet requirements specific to emergency situations at the plant. Distinctive features of the modification program includes: a highly professional man-machine interaction; consideration of site-specific factors; simulation of environmental radiology for development of drill scenarios; and concise, pertinent reports as input to decision making

Medical emergency planning in case of severe nuclear power plant accidents

International Nuclear Information System (INIS)

Ohlenschlaeger, L.

1980-01-01

This paper is an attempt to discuss a three-step-plan on medical emergency planning in case of severe accidents at nuclear power plants on the basis of own experiences in the regional area as well as on the basis of recommendations of the Federal Minister of the Interior. The medical considerations take account of the severity and extension of an accident whereby the current definitions used in nuclear engineering for accident situations are taken as basis. A comparison between obligatory and actual state is made on the possibilities of medical emergency planning, taking all capacities of staff, facilities, and equipment available in the Federal Republic of Germany into account. To assure a useful and quick utilization of the existing infra-structure as well as nation-wide uniform training of physicians and medical assistants in the field of medical emergency in case of a nuclear catastrophe, a federal law for health protection is regarded urgently necessary. (orig.) [de

The public opinion on emergency preparedness close to nuclear power plants

International Nuclear Information System (INIS)

Hultaaker, Oe.

1984-07-01

More than 1500 people have been interviewed on their attitudes towards and their knowledge of emergency actions on nuclear accidents at nuclear power plants. Of the people addressed, 768 lived in the inner zones close to the power plants. 775 were farmers near the four nuclear power sites in Sweden. The farmers lived both in inner zones and zones further away. A majority consider themselves not well-informed on health risks after a nuclear accident. More than a third would want more information on what to do in case of accident. Farmers outside the inner zones are more dissatisfied with the information status than other groups. Farmers from the inner zones consider the information given inadequate regarding risks to their health and also health risks for their live stock. The results of interviews are in some cases compared with the information given to the public. (Aa)

Nuclear power plants in Germany. Recent developments in off-site nuclear emergency preparedness and response; Kernkraftwerke in Deutschland. Neue Entwicklungen im anlagenexternen Notfallschutz

Energy Technology Data Exchange (ETDEWEB)

Gering, Florian [Bundesamt fuer Strahlenschutz, Oberschleissheim/Neuherberg (Germany). Abt. SW 2.2 Entscheidungshilfesysteme, Lageermittlung und Kommunikation

2014-10-15

The reactor accident in Fukushima, Japan, in 2011 triggered a thorough review of the off-site emergency preparedness and response for nuclear power plants in Germany. ''Off-site emergency preparedness and response'' includes all actions to protect the public outside the fence of a nuclear power plant. This review resulted in several changes in off-site emergency preparedness and response, which are briefly described in this article. Additionally, several recent activities are described which may influence emergency preparedness and response in the future.

Development of graphic display program of reactor operating parameters for emergency exercise at nuclear power plants

International Nuclear Information System (INIS)

Okuda, Yasunori; Yoshida, Yoshitaka; Gotou, Kazuko

2001-01-01

A scenario of nuclear emergency exercise based on the result of accident progress analysis is expected to ensure effective training. Thereupon a new graphic display program for reactor operating parameters has been developed to present real-time of plant process values (parameters), released radioactivities from the plant, and dose rate data around the site calculated by using the accident analysis code MAAP4 and other codes. This system has a trend graph screen displaying reactor operating parameters, an environmental dose rate summary screen indicating dose rate distribution around the site on the map, and a plant parameters summary screen showing important plant parameters on a simplified plant system diagram. One screen can be switched to another any time. It also has a jump-function easily accessing any stage during the exercise scenario in accordance with progress of the exercise. As a result of the application of this system to a real nuclear emergency exercise, it has been verified that this system is quite useful for confirming the parameters when the nuclear emergency exercise starts and the licensee reports the plant conditions to related bodied. (author)

Development of graphic display program of reactor operating parameters for emergency exercise at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Okuda, Yasunori; Yoshida, Yoshitaka [Institute of Nuclear Safety System Inc., Mihama, Fukui (Japan); Gotou, Kazuko [Kansai Electric Power Co., Inc., Osaka (Japan)

2001-09-01

A scenario of nuclear emergency exercise based on the result of accident progress analysis is expected to ensure effective training. Thereupon a new graphic display program for reactor operating parameters has been developed to present real-time of plant process values (parameters), released radioactivities from the plant, and dose rate data around the site calculated by using the accident analysis code MAAP4 and other codes. This system has a trend graph screen displaying reactor operating parameters, an environmental dose rate summary screen indicating dose rate distribution around the site on the map, and a plant parameters summary screen showing important plant parameters on a simplified plant system diagram. One screen can be switched to another any time. It also has a jump-function easily accessing any stage during the exercise scenario in accordance with progress of the exercise. As a result of the application of this system to a real nuclear emergency exercise, it has been verified that this system is quite useful for confirming the parameters when the nuclear emergency exercise starts and the licensee reports the plant conditions to related bodied. (author)

Reliability of emergency alternating-current power systems at nuclear power plants: a discussion of NUREG/CR-2989

International Nuclear Information System (INIS)

Battle, R.E.

1985-01-01

The reliability of emergency alternating-current power systems typical of most nuclear power plants was estimated by using fault-tree analysis of selected typical designs. The failure probabilities used in the fault trees were calculated from extensive historical data collected from Licensee Event Reports and from operating experience information obtained from nuclear plant licensees. Trends of diesel generator independent failure on demand are included. No one or two improvements can be made at all plants to increase significantly the industry-average emergency alternating-current power system reliability; the most beneficial improvements are varied and plant specific

Systematic preparation, execution and evaluation of emergency exercises at the Beznau nuclear power plant

International Nuclear Information System (INIS)

Tenschert, J.

2011-01-01

Based on federal acts and a specific guideline of the nuclear authority ENSI, strict requirements are imposed on emergency exercises at Swiss NPPs. The Beznau NPP has conducted emergency exercises for more than 30 years. Systematic exercise planning assures that all emergency cases defined in the plant-specific emergency plan are considered in the exercise scenarios. Technically oriented scenarios cover all groups of initiating events and all safety levels of the defense in depth principle. The exercise results are an important input for optimization measures in the areas of emergency organization, documentation and infrastructure. Due to the goal-oriented enforcement of laws and guidelines by the nuclear authority ENSI, emergency exercises serve as a motor of further optimization of emergency preparedness. (orig.)

Safety assessment of emergency electric power systems for nuclear power plants

International Nuclear Information System (INIS)

1986-09-01

This paper is intended to assist the safety assessor within a regulatory body, or one working as a consultant, in assessing a given design of the Emergency Electrical Power System. Those non-electric power systems which may be used in a plant design to serve as emergency energy sources are addressed only in their general safety aspects. The paper thus relates closely to Safety Series 50-SG-D7 ''Emergency Power Systems at Nuclear Power Plants'' (1982), as far as it addresses emergency electric power systems. Several aspects are dealt with: the information the assessor may expect from the applicant to fulfill his task of safety review; the main questions the reviewer has to answer in order to determine the compliance with requirements of the NUSS documents; the national or international standards which give further guidance on a certain system or piece of equipment; comments and suggestions which may help to judge a variety of possible solutions

Evaluation of nuclear data for emergency preparedness system of nuclear power plants. Comparison of radioactivity inventories by newest nuclear data and rather older nuclear data

International Nuclear Information System (INIS)

Yoshida, Yoshitaka; Kimura, Itsuro

2004-01-01

The radioactivity inventories for emergency preparedness systems of nuclear power plants calculated by the combination of the generally-used in Japan (general-version), the INSS used by the present authors (INSS-version) and the newest nuclear data library and codes (newest-version) were compared, and the maintaining of conservativeness of the general-version and the INSS-version against the newest-version was examined. And the influences of the radioactivity inventories by the difference between the nuclear cross section and fission yield data, decay data and calculation codes were investigated. As a result, (1) the radioactivity inventories calculated by general-version and INSS-version were not confirmed the conservativeness to the newest-version. But the difference was less than 10%, and it would not give large influence to the calculation of the emergency preparedness system of nuclear plants. (2) The influence of the radioactivity inventories such as 135 Xe build-up were observed by the difference of neutron flux level in an operation of reactors that occurred by the variety of nuclear cross section and fission yield data. (3) Little influence by the variety of decay data was confirmed. (4) The ORIGEN2.1 code underestimated the amount of fission products generated by fission of minor actinides. From these result, the radioactivity inventories for the emergency preparedness system of nuclear power plants are recommended to use the calculation results by the combination of the library for ORIGEN2 based on JENDL3.3 and the ORIGEN2.2 code. (author)

Report to Congress on status of emergency response planning for nuclear power plants

International Nuclear Information System (INIS)

1981-03-01

This report responds to a request (Public Law 96-295, Section 109) for the Nuclear Regulatory Commission (NRC) to report to Congress on the status of emergency response planning in support of nuclear power reactors. The report includes information on the status of this planning as well as on the Commission actions relating to emergency preparedness. These actions include a summary of the new regulatory requirements and the preliminary results of two comprehensive Evacuation Time Estimate studies; one requested by the NRC including 50 nuclear power plant sites and one conducted by the Federal Emergency Management Agency (FEMA) for 12 high population density sites. FEMA provided the information in this report on the status of State and local planning, including projected schedules for joint State/county/licensee emergency preparedness exercises. Included as Appendicies are the NRC Emergency Planning Final Regulations, 10 CFR Part 50 (45 FR 55402), the FEMA Proposed Rule, 'Review and Approval of State and Local Radiological Emergency Plans and Preparedness', 44 CFR Part 350 (45 FR 42341) and the NRC/FEMA Memorandums of Understanding

Guidance for emergency planning in nuclear power plants

International Nuclear Information System (INIS)

Magnusson, Tommy; Ekdahl, Maria

2008-06-01

Ringhals has been a model for this study, but the purpose has been to make the report applicable at all nuclear power plants in Sweden. The work has been done in close co-operation with the Swedish nuclear power plants and Rescue Services in the nuclear power municipalities Oesthammar, Oskarshamn, and Varberg. The internal fire brigade at the nuclear power plants has also been involved. A document will also be published as a further guidance at efforts of the type fires, which are mentioned in the enclosed document. After a fire in a switchgear room in 2005 the need of making the existing effort planning more effective at nuclear power plants was observed. The idea with the planning is to plan the effort in order to give the operational and emergency staff a good and actual support to come to a decision and to start the mission without delay. The risk information is showed by planning layouts, symbols and drawings as basis, give risk information and effort information. The effort information shows outer arrangements, manual action points, fire installations, passive fire safety etc. The risk information is shown by risk symbols. Their purpose is to give a fast overview of the existing risks. Reactor safety effects is the ruling influence if an effort has to be done in order to secure safety for a third person. In order to make an effort in an area personal risks for rescue staff, such as electricity risks, radiological risks, chemicals and gas bottles with compressed gases, has to be eliminated. For complicated missions detailed instructions are needed in order to handle specific risks. In a group discussion different people with pertinent knowledge has to value which problematic efforts need detailed instruction. Missions that have to be analyzed in a work group as above are: fire may affect the reactor safety, fire that may threaten the structural integrity, chemical discharge with big consequence on environment/third person and handling of gas system (compressed

Nuclear plant data systems - some emerging directions

International Nuclear Information System (INIS)

Johnson, R.D.; Humphress, G.B.; McCullough, L.D.; Tashjian, B.M.

1983-01-01

Significant changes have occurred in recent years in the nuclear power industry to accentuate the need for data systems to support information flow and decision making. Economic conditions resulting in rapid inflation and larger investments in new and existing plants and the need to plan further ahead are primary factors. Government policies concerning environmental control, as well as minimizing risk to the public through increased nuclear safety regulations on operating plants are additional factors. The impact of computer technology on plant data systems, evolution of corporate and plant infrastructures, future plant data, system designs and benefits, and decision making capabilities and data usage support are discussed. (U.K.)

Dose-projection considerations for emergency conditions at nuclear power plants

International Nuclear Information System (INIS)

Stoetzel, G.A.; Ramsdell, J.V.; Poeton, R.W.; Powell, D.C.; Desrosiers, A.E.

1983-05-01

The purpose of this report is to review the problems and issues associated with making environmental radiation-dose projections during emergencies at nuclear power plants. The review is divided into three areas: source-term development, characterization of atmospheric dispersion and selection of appropriate dispersion models, and development of dosimetry calculations for determining thyroid dose and whole-body dose for ground-level and elevated releases. A discussion of uncertainties associated with these areas is also provided

Dose-projection considerations for emergency conditions at nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Stoetzel, G.A.; Ramsdell, J.V.; Poeton, R.W.; Powell, D.C.; Desrosiers, A.E.

1983-05-01

The purpose of this report is to review the problems and issues associated with making environmental radiation-dose projections during emergencies at nuclear power plants. The review is divided into three areas: source-term development, characterization of atmospheric dispersion and selection of appropriate dispersion models, and development of dosimetry calculations for determining thyroid dose and whole-body dose for ground-level and elevated releases. A discussion of uncertainties associated with these areas is also provided.

Developing a taxonomy of coordination behaviours in nuclear power plant control rooms during emergencies.

Science.gov (United States)

Wang, Dunxing; Gao, Qin; Li, Zhizhong; Song, Fei; Ma, Liang

2017-12-01

This study aims to develop a taxonomy of coordination behaviours during emergencies in nuclear power plants (NPPs). We summarised basic coordination behaviours from literature in aviation, health care and nuclear field and identified coordination behaviours specific to the nuclear domain by interviewing and surveying control crew operators. The established taxonomy includes 7 workflow stages and 24 basic coordination behaviours. To evaluate the reliability and feasibility of the taxonomy, we analysed 12 videos of operators' training sessions by coding coordination behaviours with the taxonomy and the inter-rater reliability was acceptable. Further analysis of the frequency, the duration and the direction of the coordination behaviours revealed four coordination problems. This taxonomy provides a foundation of systematic observation of coordination behaviours among NPP crews, advances researchers' understanding of the coordination mechanism during emergencies in NPPs and facilitate the possibility to deepen the understanding of the relationships between coordination behaviours and team performance. Practitioner Summary: A taxonomy of coordination behaviours during emergencies in nuclear power plants was developed. Reliability and feasibility of the taxonomy was verified through the analysis of 12 training sessions. The taxonomy can serve as an observation system for analysis of coordination behaviours and help to identify coordination problems of control crews.

Health and safety impacts of nuclear, geothermal, and fossil-fuel electric generation in California. Volume 4. Radiological emergency response planning for nuclear power plants in California

International Nuclear Information System (INIS)

Yen, W.W.S.

1977-01-01

This report reviews the state of emergency response planning for nuclear power plants in California. Attention is given to the role of Federal agencies, particularly the Nuclear Regulatory Commission, in planning for both on and off site emergency measures and to the role of State and local agencies for off site planning. The relationship between these various authorities is considered. Existing emergency plans for nuclear power plants operating or being constructed in California are summarized. The developing role of the California Energy Resources Conservation and Development Commission is examined

Emergency preparedness for nuclear power plants in the USA

International Nuclear Information System (INIS)

Schwartz, S.A.

1986-01-01

In the case of an operating reactor, if it is determined that there are such deficiencies that a favourable NRC finding is not warranted and if the deficiencies are not corrected within four months of that determination, the Commission will determine whether the reactor should be shut down or whether some other enforcement action is appropriate. In any case, where the Commission believes that the public health, safety, or interest so requires, the plant will be required to shut down immediately. Emergency planning considerations must be extended to emergency planning zones, and these shall consist of an area of about 10 miles in radius for exposure to the radioactive plume that might result from an accident in a nuclear power reactor and an area of about 50 miles in radius for food that might become contaminated. To evaluate the effectiveness of the licensee programme to implement their emergency plan, a 'management oversight and risk tree' (MORT) approach was developed and used by NRC appraisal teams at all operating facilities and those close to licensing. Since April 1981, over 250 emergency preparedness exercises have been observed and annual inspections conducted at US commercial nuclear power generating facilities. As a result of this experience, licensees have generally progressed from a basic ability to implement their plan to a systematic demonstration of their emergency preparedness capabilities. Almost five years have elapsed since the inception of the upgraded emergency preparedness regulatory programme, and the NRC is evaluating the resources committed to the programme to determine if modifications are appropriate. Our goal is to ensure continued adequate readiness capability to protect the public health and safety in the event of an accident

Human-Machine interface for off normal and emergency situations in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee Choon [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-01-01

Many nuclear power plants (NPPs) have reported that a high percentage of all major failures in the plants are caused by human errors. Therefore, there has been much focus on elimination of human errors, enhancement of human performance, and general improvement of human machine interface (HMI). Both the utility management and the regulators are demanding improvement in this area. The International Atomic Energy Agency (IAEA) Specialists' Meeting on 'Human-Machine Interface for Off Normal and Emergency Situations in Nuclear Power Plants' was co-organized by the Korea Atomic Energy Research Institute (KAERI) and the Korea Power Engineering Company, INC (KOPEC), and took place in Taejeon, Republic of Korea, 1999 October 26-28. Fifty eight participants, representing nine member countries reviewed recent developments and discussed directions for future efforts in the Human-Machine Interface for Off Normal and Emergency Situations in NPPs. Twenty papers were presented, covering a wide spectrum of technical and scientific subjects including recent experience and benefits from Operational Experience with HMI, Development of HMI System, Licensing Issues for HMI and Future Development and Trends. (Author)

Human-Machine interface for off normal and emergency situations in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kwon, Kee Choon [Korea Atomic Energy Research Institute, Taejeon (Korea)

2000-01-01

Many nuclear power plants (NPPs) have reported that a high percentage of all major failures in the plants are caused by human errors. Therefore, there has been much focus on elimination of human errors, enhancement of human performance, and general improvement of human machine interface (HMI). Both the utility management and the regulators are demanding improvement in this area. The International Atomic Energy Agency (IAEA) Specialists' Meeting on 'Human-Machine Interface for Off Normal and Emergency Situations in Nuclear Power Plants' was co-organized by the Korea Atomic Energy Research Institute (KAERI) and the Korea Power Engineering Company, INC (KOPEC), and took place in Taejeon, Republic of Korea, 1999 October 26-28. Fifty eight participants, representing nine member countries reviewed recent developments and discussed directions for future efforts in the Human-Machine Interface for Off Normal and Emergency Situations in NPPs. Twenty papers were presented, covering a wide spectrum of technical and scientific subjects including recent experience and benefits from Operational Experience with HMI, Development of HMI System, Licensing Issues for HMI and Future Development and Trends. (Author)

Process improvement of the emergency operating procedures for Embalse Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Mariotti, A.D.; Pomerantz, M.; Moreno, C., E-mail: dmariotti@na-sa.com.ar, E-mail: mpomerantz@na-sa.com.ar, E-mail: cmoreno@na-sa.com.ar [Embalse Nuclear Power Plant, Nuclear Safety Dept., Embalse (Argentina)

2014-07-01

Emergency Operating Procedures (EOP) package of the Embalse Nuclear Power Plant (CNE) were made entirely by the plant staff since the beginning of its operation. With the emergence of Severe Accidents Guidelines (SAMG) and the latest events related to Fukushima, the EOP philosophy should include a new concept. It should consider that the EOP may be unsuccessful and an exit to the SAMG must be necessary. However, due to abnormal event mitigation using EOP is the way to prevent the beginning of a severe accident, EOP always had significant relevance in the plant documentation. For this reason, added to the overall requirement of an exit to the SAMG, it emerges a general review of the use efficiency of the EOP during an abnormal event. For this reason, a comprehensive process improvement has emerged using the operating experience, full-scope simulator training of the control room staff, advances in technology and the arrival of new generations. In this work, fundamental changes, new document format and ergonomic redesign for validation at full-scope simulator and use at main control room of new EOP for CNE are presented. (author)

Cross-connected onsite emergency A.C. power supplies for multi-unit nuclear power plant sites

International Nuclear Information System (INIS)

Martore, J.A.; Voss, J.D.; Duncil, B.

1987-01-01

Recently, utility management, both at the corporate and plant operations levels, have reinforced their commitment to assuring increased plant reliability and availability. One means of achieving this objective involves an effective preventive maintenance program with technical specifications which allow implementation of certain preventive maintenance without plant shutdown. To accomplish this, Southern California Edison Company (SCE) has proposed a design change for San Onofre nuclear generating station (SONGS) units 2 and 3 to permit on emergency diesel generator for one unit to perform as an available AC power source for both units. Technical specifications for SCE's SONGS units 2 and 3, as at most nuclear power plants, currently require plant shutdown should one of the two dedicated onsite emergency AC power sources (diesel generators) become inoperable for more than 72 hours. This duration hinders root cause failure analysis, tends to limit the flexibility of preventive maintenance and precludes plant operation in the event of component failure. Therefore, this proposed diesel generator cross-connect design change offers an innovative means for averting plant shutdown should a single diesel generator become inoperable for longer than 72 hours. (orig./GL)

Study of time-critical diagnostic method for emergency operation of nuclear power plant

International Nuclear Information System (INIS)

Gofuku, A.; Yoshikawa, H.; Itoh, K.; Wakabayashi, J.

1986-01-01

In order to support the emergency operation of nuclear power plant, the method of time-critical diagnostic plant analyzer has been investigated. The conception of the emergency operation support center is proposed and two types of plant analyzer may be installed in this center. One analyzer is a real-time tracking simulation code using the observed signals and another is a fast trend-prediction code. A real-time tracking code, TOKRAC, has been developed for analyzing the PWR primary loop thermo-hydraulics at SBLOCA, and the applicability of this code was examined by the numerical experiments for the initial phase transient of both TMI-2 accident and 6% coldleg SBLOCA of a Westinghouse-type PWR plant. The results showed that fairly good tracking was carried out by TOKRAC. The CPU time of TOKRAC was about 12-14 percent of real-time

Reliability evaluation of emergency AC power systems based on operating experience at U.S. nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Baranowsky, P. W. [U.S. Nuclear Regulatory Commission, Washington, DC (United States)

1986-02-15

The reliability of emergency AC power Systems has been under study at the U.S. Nuclear Regulatory Commission and by its contractors for several years. This paper provides the results of work recently performed to evaluate past U.S. nuclear power plant emergency AC power System reliability performance using system level data. Operating experience involving multiple diesel generator failures, unavailabilities, and simultaneous occurrences of failures and out of service diesel generators were used to evaluate reliability performance at individual nuclear power plants covering a 9 year period from 1976 through 1984. The number and nature of failures and distributions of reliability evaluation results are provided. The results show that plant specific performance varied considerably during the period with a large number achieving high reliability performance and a smaller number accounting for lower levels of reliability performance. (author)

Specification for self contained emergency luminiare and their qualification for a nuclear power plant

International Nuclear Information System (INIS)

Srinivasan, R.; Shanmugam, T.K.

1999-01-01

Self contained emergency luminiare (SCEL) for application in a nuclear plant shall meet the illumination level requirement of ANSI/NFPA 101-1988 (Life Safety Code) Section 5.8. The testing shall be done as per IS 9583-1981 requirements. In the selection of self contained emergency luminiare the Sealed Maintenance Free (SMF) battery characteristic and Ampere-Hour ratings are to be carefully evaluated

Nuclear emergency preparedness and management the international nuclear emergency exercise Inex 2000

International Nuclear Information System (INIS)

Mundigl, St.

2003-01-01

With the initiation of the first international nuclear emergency exercise INEX 1, performed as a table-top exercise in 1993, the international community tested, for the first time, approaches and policies in place to manage a nuclear or radiological emergency. INEX 1 with its related workshops led to a wealth of lessons learned and to an improvement in nuclear emergency management. The INEX 2 exercise series, initiated by the NEA and performed between 1996 and 1999, established an international nuclear emergency 'exercise culture' leading to a clear improvement of the international aspects of nuclear emergency preparedness and management. INEX 2 was a series of four command post exercises based on national nuclear emergency exercises in Switzerland, Finland, Hungary and Canada. Simulated accidents at nuclear power plants were used to test existing procedures in emergency response and management, and to analyse local, regional, national and international emergency plans under realistic conditions. In addition, the exercises allowed the participating countries to gain experience using new concepts and tools. The most significant result of INEX 2 and a major step forward in nuclear emergency management was the development of a new communication and information exchange strategy, which is currently implemented by various NEA member countries as well as by the international community in general. The objective of this new strategy is to assist the decision-maker by improving the selection of the data transmitted, by encouraging the transmission and reception of such data and information using modern communication methods, e.g. secure world wide web technologies, and by defining emergency monitoring and modelling needs. To test the validity and usefulness of the newly-developed strategy, the NEA proposed to organize an international nuclear emergency exercise, INEX 2000, similar in scope to the INEX 2 exercises. In addition, the NEA suggested to include, for the first

A Production-Rule Analysis System for Nuclear Plant monitoring and emergency response applications

International Nuclear Information System (INIS)

Ragheb, M.; Tsoukalas, L.; McDonough, T.; Parker, M.

1987-01-01

A Production-Rule Analysis System for Nuclear Power Plant Monitoring is presented. The signals generated by the Zion-1 Plant are considered for emergency Response applications. The integrity of the Plant Radiation, the Reactor Coolant, the Fuel Clad, and the Containment Systems, is monitored. Representation of the system is in the form of a goal-tree generating a Knowledge-Base searched by an Inference Engine functioning in the forward-chaining mode. The Gaol-tree is built from Fault-Trees based on plant operational information. The system is implemented on a VAX-8500 and is programmed in OPS-5

Planning and preparedness for radiological emergencies at nuclear power stations

International Nuclear Information System (INIS)

Thomson, R.; Muzzarelli, J.

1996-01-01

The Radiological Emergency Preparedness (REP) Program was created after the March 1979 accident at the Three Mile Island nuclear power station. The Federal Emergency Management Agency (FEMA) assists state and local governments in reviewing and evaluating state and local REP plans and preparedness for accidents at nuclear power plants, in partnership with the US Nuclear Regulatory Commission (NRC), which evaluates safety and emergency preparedness at the power stations themselves. Argonne National Laboratory provides support and technical assistance to FEMA in evaluating nuclear power plant emergency response exercises, radiological emergency plans, and preparedness

Nuclear Power Plants | RadTown USA | US EPA

Science.gov (United States)

2018-03-12

Nuclear power plants produce electricity from the heat created by splitting uranium atoms. In the event of a nuclear power plant emergency, follow instructions from emergency responders and public officials.

Brief introduction of nuclear power plant emergency system EmInfoSys

International Nuclear Information System (INIS)

Xiao Yuhua; Zhao Zhigang

2014-01-01

Nuclear safety is the lifeline of nuclear energy and nuclear technology, nuclear accident emergency response is the last line of nuclear security defense, and is one of the important measures to ensure the healthy development of the nuclear energy safety. The establishment of complete function, sensitive reaction and efficient emergency management system for operation of nuclear and radiation accidents is an important task of nuclear security. From 2001 China Techenergy Co., Ltd. participated in the Qinshan, Tianwan, Ministry of Environmental Protection, Haiyang, Taishan, Fangchenggang, Sanmen, etc. nuclear emergency projects, and the nuclear emergency EmInfoSys (emergency management information system) platform was developed with independent intellectual property rights. A brief introduction about EmInfoSys system was performed in this paper. (authors)

Tactical and strategic decision-making aids for nuclear power plant emergency response

International Nuclear Information System (INIS)

Cain, D.G.

1987-01-01

This paper examines the prospective role of computer-based decision aids for nuclear power plant emergency response. The role of these systems is subordinate to human activities, but in a complementary manner these systems process decision logic more accurately and foster a more thorough understanding of emergency situations than might other wise be possible. Within this context two decision support systems being developed are discussed. Both of these systems utilize technology derived from artificial intelligence, focussing on two different facets of emergency response. An automated emergency operating procedures (EOP) tracking expert system is described as a tactical aid for control room operator response. A reactor emergency action level monitor (REALM) expert system is proposed as a strategic decision aid for site emergency response. The discrimination between tactical and strategic decision-making is an intrinsic part of this examination

Emergency planning requirements and short-term countermeasures for commercial nuclear power plants in the United States

International Nuclear Information System (INIS)

Kantor, F.; Hogan, R.; Mohseni, A.

1995-01-01

Since the accident at the Three Mile Island Unit, the United States Nuclear Regulatory's Commission (NRC's) emergency planning regulations are now considered and an important part of the regulatory framework for protecting the public health and safety. Many aspects of the countermeasures are presented: Emergency Planning Zones (EPZ), off-Site emergency planning and preparedness, responsibilities of nuclear power plants operators and states and local government. Finally, protective action recommendations are given as well as the federal response to an emergency. The authors noted that the use of potassium iodide is not considered as an effective countermeasure for the public protection in the US. (TEC). 1 fig

Internal emergency organization in the Beznau nuclear power plant

International Nuclear Information System (INIS)

Wenger, H.

1989-01-01

The successful mastering of every emergency situation is based on the strict adherence to frequently reviewed emergency instruction and practice on simulators. This is the primary duty of all plant employees. In addition, executive bodies are necessary. The highest authority in the emergency organization is the emergency staff. Under the leadership of the plant manager, this staff consists of all department heads and several specialists. Outside normal working hours, it can be expected of the emergency staff that it is fully functional within, at most, one hour. Until the emergency staff can take over, the on-duty engineer leads emergency procedures. Several other different teams are responsible to the emergency staff. There are five emergency teams: off-duty plant employees; fire fighters; radiation defence; first-aid; plant guards. Then there is the technical support center (TSC). The responsibilities of the TSC are: giving technical advise to the emergency staff; working out different options for fighting the emergency; checking up on special methods; communication with the reactor manufacturer for additional support. 1 fig

Documents for designing the emergency system for the Temelin nuclear power plant

International Nuclear Information System (INIS)

Machek, J.; Fiser, V.

1993-12-01

The organizational structure of the emergency system at the Temelin nuclear power plant is described and the responsibilities, principal assignments and number of personnel and their qualification are outlined; these include the Emergency Staff, emergency organization of the operator shift, Technical Support Center, External Emergency Support Center, and Operating Support Center. The emergency information system to secure personnel activities in emergency situations is also described. This consists of a critical safety function display system, a post-accident monitoring system, and a post-accident sampling system. The performance of the emergency support centers, their equipment with communications and computer hardware, and the number and qualification of personnel are also dealt with. The emergency classification is as follows: anomaly, incident, accident, major accident. The information and warning system is briefly described. A decision flow-chart for the assessment of emergency situations and their classification, including the complete algorithm for classifying accidents in the accident classification system, is given in the annex. (J.B.)

Civil emergency preparedness at the Ignalina nuclear power plant

International Nuclear Information System (INIS)

1998-12-01

Workshop was held in the frame of Lithuania's cooperation with NATO on disasters management subject and was concentrated on the preparation of management of nuclear accident at Ignalina NPP. The following topics were covered: emergency preparedness inside Ignalina NPP, preparedness for nuclear accidents at national level, experience in Nordic countries and IAEA activities in harmonization of nuclear emergency preparedness in different countries

Barsebaeck power plant - safety and emergency measures

International Nuclear Information System (INIS)

Anon.

1981-01-01

A Swedish-Danish Committee on safety at the Swedish nuclear power plant Barsebaeck was established in 1979 in order to evaluate the nuclear safety at Barsebaeck with a view to the reactor accident at the Three-Mile-Island nuclear power plant March 28, 1979. According to the committees mandate the investigations of the Kemeny Commission, the Rogouin investigation, investigations of the American Nuclear Regulatory Commission, and the Swedish report ''Safe nuclear power'' have been taken into consideration by the Committee. Furthermore, it has formed the basis for the Committees work that the authority responsibility for the safety at Barsebaeck lies with the Swedish authorities, and that these authorities have evaluated the safety aspects before the permissions for operation of the Barsebaeck power plant were given and hereafter currently in connection with the inspection of the power plant. The report prepared by the Commission treats aspects as: a) Nuclear safety at the Barsebaeck power plant, b) reactor safety and emergency provisions, c) common elements in the emergency provision situation in Sweden and Denmark, d) ongoing investigations on course of events during accidents and release limiting safety systems. (BP)

Severe accident management at nuclear power plants - emergency preparedness and response actions

International Nuclear Information System (INIS)

Pawar, S.K.; Krishnamurthy, P.R.

2015-01-01

This paper describes the current level of emergency planning and preparedness and also improvement in the emergency management programme over the years including lessons learned from Fukushima accident, hazard analysis and categorization of nuclear facilities into hazard category for establishing the emergency preparedness class, classification of emergencies based on the Emergency Action Levels (EAL), development of EAL’s for PHWR, Generic Criteria in terms of projected dose for initiating protective actions (precautionary urgent protective actions, urgent protective actions, early protective actions), operational intervention levels (OIL), Emergency planning zones and distances, protection strategy and reference levels, use of residual dose for establishing reference levels for optimization of protection strategy, criteria for termination of emergency, transition of emergency exposure situation to existing exposure situation or planned exposure situation, criteria for medical managements of exposed persons and guidance for controlling the dose of emergency workers. This paper also highlights the EALs for typical PHWR type reactors for all types of emergencies (plant, site and offsite), transition from emergency operating procedures (EOP) to accident management guidelines (AMG) to emergency response actions and proposed implementation of guidelines

An Assessment for Emergency Preparedness Plan in Hanul Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Park, Sunghyun; Jae, Moosung [Hanyang University, Seoul (Korea, Republic of)

2016-10-15

The purpose of emergency preparedness aims to protect the accident and mitigate the radiation damage of public by setting emergency preparedness plan. In order to perform successfully the emergency preparedness plan, it should be optimized through a quantitative analysis. There are so many variables to analyze it quantitatively. It is mission to classify a realistic and suitable variables among these variables. The realistic variables is converted to the decision node in decision tree which is helpful to decide what evacuation or sheltering is effective to mitigate public damage. Base on it, it's idealistic method to analyze offsite consequences for each end points in the decision tree. In this study, we selected the reference plant which already has the emergency preparedness plan. Among the plan, we implemented offsite consequence analysis for a specific plan by using MACCS 2 code. In this study, target group is people who gathered in place 1 have sheltered and evacuated along the pathway. the offsite consequences analysis result of the group are 1.17·10-9 (early fatality), 1.77·10-7 (late fatality). Various cases need to be quantified for make an optimized decision. In the future, we will perform the verification and modification of decision node. After The assessment of emergency preparedness plan for Hanul nuclear power plant unit 5, 6 might be contribute to establish the optimized decision making of emergency prepared plan.

Principles of off-site nuclear emergency exercises

International Nuclear Information System (INIS)

Miska, H.

2011-01-01

Due to high safety standards at nuclear power plants, no experience exits with nuclear emergencies in Western Europe. Thus, emergency exercises are the only possibility to assure effective protective measures should the very unlikely severe accident occur. The main objectives of exercises are generally the check of response plans for suitability, the test of the equipment's applicability and training of personnel for the unusual task to manage a nuclear emergency. After an introduction into the different types of exercises, this contribution focuses on offsite nuclear emergency exercises, explaining frame conditions to ensure good practice and, finally, reports some experience from exercises. (orig.)

Hypothetical accidents of light-water moderated nuclear power plants in the framework of emergency planning

International Nuclear Information System (INIS)

1979-07-01

Hypothetical accidents in nuclear power plants are events which by definition can have a devastating impact on the surroundings of the plant. Apart from an adequate plant design, the protection of the population in case of an accident is covered by the emergency planning. Of major importance are the measures for the short-term emergency protection. The decision on whether these measures are applied has to be based on appropriate measurements within the plant. The aim and achieved result of this investigation is to specify accident types. They serve as operational decision making criteria to determine the necessary measurements for analysing the accident in the accident situation, and to provide indications for choosing the suitable strategy for the protection measures. (orig.) [de

Experiences in the development of an emergency response facility (ERF) system for a nuclear power plant

International Nuclear Information System (INIS)

Seisdedos, A.; Sanchez-Fornie, M.A.

1985-01-01

The TMI-2 accident gave rise to a series of new requirements with which Nuclear Power Plants must comply and amongst which the implementation of emergency response facilities, particularly the SPDS, has received special attention. This paper covers the experience and problems encountered in the developing of the engineering necessary for the detailed definition of the ERF in a Nuclear Power Plant in the commercial operation phase. Also, a real example is provided for the case of a plant in the last phase of construction and installation. This will serve to illustrate each of the topics covered. (author)

Future of Nuclear Power: NRC emergency preparedness licensing activities agenda

International Nuclear Information System (INIS)

Essig, T.H.

1995-01-01

This talk summary addresses the issue of how future policies of the NRC will affect nuclear power in areas such as construction, emergency preparedness, and licensing. Specific topics covered include the following: Emergent EP licensing issues for operating nuclear Power Plants; 10CFR Part 52 and the process for licensing of Advanced Light Water Reactors (ALWRs); and potential revisions to emergency preparedness programs for future nuclear power plants

Strengths of common resources for managing emergencies in the Spanish nuclear power plants (CAE y UME)

International Nuclear Information System (INIS)

Blas, J. de

2014-01-01

Following the accident at the Fukushima-Daiichi power plants, the electrical sector of nuclear generation recognised the need to reinforce the capacities that the nuclear power plants already had and which they were developing in order to satisfy the requisites of the stress tests, with the additional support of equipment and human resources common to all of them. Thus the idea arose to create a Spanish emergency Support centre. Its scope included an intervention unit, pumping equipment and electrical generation, a centralised warehouse and transfer logistics. UNESA-UME Collaboration Protocol With the collaboration of the CSN as a mediator, the UME reached an agreement with the nuclear electrical sector (UNESA) in order to be able to increase knowledge about the Spanish nuclear power plants and establish a means of collaboration to be able to act with their own human and equipment resources at a site that might suffer an accident such as the one at the Japanese plants of Fukushima-Daiichi. (Author)

Concept of voltage monitoring for a nuclear power plant emergency power supply system (PWR 1300 MWe)

International Nuclear Information System (INIS)

Andrade, R.B. de

1988-01-01

Voltage monitoring concept for a Nuclear Power Plant Emergency Power Supply Systems (PWR 1300 MWe) is described based on the phylosophy adopted for Angra 2 and 3 NPP's. Some suggested setpoints are only guidance values and can be modified during plant commissioning for a better performance of the whole protection system. (author) [pt

German risk study 'nuclear power plants, phase B'

International Nuclear Information System (INIS)

Heuser, F.W.

1989-01-01

The results of the German risk study 'Nuclear power plants, phase B' indicate that an accident in a nuclear power plant which cannot be managed by the safety systems according to design, is extremely improbable: Its probability is at about 3 to 100,000 per year and plant. Even if the safety systems fail, emergency measures can be effected in a nuclear power plant to prevent an accident. These in-plant emergency measures diminish the probability of a core meltdown to about 4 to 1,000,000 per year and plant. Hence, the accident risk is greatly reduced. The information given by the author are to smooth the emotional edge in the discussion about the safety of nuclear power plants. (orig.) [de

Evaluating the effectiveness of warning systems for nuclear power plant emergencies: criteria and application

International Nuclear Information System (INIS)

Sorensen, J.H.

1984-01-01

The accident at Three Mile Island Nuclear Power Plant in 1979 was an emergency management disaster. Chief among the problems was ineffective public warning and communications. While it is difficult to assign blame for that condition to any given party or determine if it was due to unique situational factors, the failure led to fairly significant regulatory changes in the arena of public warning and notification. These changes are intended to avoid the problems that arose during the TMI accident. This chapter reviews these regulations and suggests an alternative set of criteria for evaluating warning systems. The criteria are used to assess the effectiveness of the warning system at the Ft. St. Vrain nuclear power plant in Colorado. The paper concludes with some discussion of the lessons learned from the TMI experience as they apply to warning systems for all nuclear generating stations

Handbook for the planning, co-ordination and evaluation of emergency exercises in nuclear power plants

International Nuclear Information System (INIS)

Schmidtborn, I.; Bath, N.

1999-01-01

The efficiency of the on-site emergency organization in German nuclear power plants is tested regularly through emergency exercises. To achieve federal harmonization on a high level of quality a handbook for the planning, co-ordination and evaluation of such exercises has been developed in the frame of the regulatory investigation programme. In this handbook requirements are set out for emergency training. Key elements are a modular structure, rules to be observed and guidance for post-exercise evaluation. (orig.) [de

Emergency management and the nuclear terrorism threat

International Nuclear Information System (INIS)

DeVito, D.A.; Suiter, L.

1987-01-01

Counterterrorism is not the province of the emergency manager. Generally law enforcement has that role. Instead, the emergency manager's role is crisis management; the responsibility is to be the focal point for the chief executive officer (mayor, governor, or national executive) regarding the protection of the population. Managers must be able to gather and synthesize sufficient information, rapidly and accurately, on which to base sound decisions. To do so, they must have a highly efficient, coordinated emergency management organization in place at the state and local levels of government, and there must be a workable plan for emergency operations that integrates all public safety forces into an effective response to all types of emergencies. A major goal of emergency management is to ensure that government is in control and that the public perceives that the system is working. All states have an emergency management organization at the state level, as do most counties and large cities. However, some states and local governments, particularly those that have nuclear power plants within their borders, are better staffed, equipped, and trained than others to deal with nuclear incidents. States with nuclear facilities have an emergency management organization, an emergency plan, and adequate communications, equipment, and trained personnel to handle a nuclear accident or incident at a plant. 21 references

Emergency preparedness and response plan for nuclear facilities in Indonesia

International Nuclear Information System (INIS)

Nur Rahmah Hidayati; Pande Made Udiyani

2009-01-01

All nuclear facilities in Indonesia are owned and operated by the National Nuclear Energy Agency (BATAN). The programs and activities of emergency planning and preparedness in Indonesia are based on the existing nuclear facilities, i.e. research reactors, research reactor fuel fabrication plant, radioactive waste treatment installation and radioisotopes production installation. The assessment is conducted to learn of status of emergency preparedness and response plan for nuclear facilities in Indonesia and to support the preparation of future Nuclear Power Plant. The assessment is conducted by comparing the emergency preparedness and response system in Indonesia to the system in other countries such as Japan and Republic of Korea, since the countries have many Nuclear Power Plants and other nuclear facilities. As a result, emergency preparedness response plan for existing nuclear facility in Indonesia has been implemented in many activities such as environmental monitoring program, facility monitoring equipment, and the continuous exercise of emergency preparedness and response. However, the implementation need law enforcement for imposing the responsibility of the coordinators in National Emergency Preparedness Plan. It also needs some additional technical support systems which refer to the system in Japan or Republic of Korea. The systems must be completed with some real time monitors which will support the emergency preparedness and response organization. The system should be built in NPP site before the first NPP will be operated. The system should be connected to an Off Site Emergency Center under coordination of BAPETEN as the regulatory body which has responsibility to control of nuclear energy in Indonesia. (Author)

Information for nuclear emergency response: a case study based on ANGRA nuclear power plant emergency simulation exercises

International Nuclear Information System (INIS)

Carvalho, Paulo V.R. de

2008-01-01

Full text: Current nuclear emergency management procedures do not always satisfactorily address issues related to the information availability and to how people in emergency control centres use this information to respond to an nuclear accident. The lack of an adequate and prompt information may lead to a response that can be very different from what authorities recommend and thus create confusion, mistrust, and widespread uncertainty. This is a potentially serious problem for emergency planners. An adequate and prompt access to relevant information is a critical requirement that emergency teams face while they work towards reducing the undesired consequences of the emergency. There are three basic types of knowledge according to a conceptual framework developed to deal with emergency response: Previous Personal, Previous and, Current Contextual knowledge. Most decisions in emergency control centres require a dynamic combination of all types of knowledge, particularly the current contextual that comes from the emergency settings, including all information about the activities of other emergency teams. The aim of this paper is to describe the concepts and the structure of a system that aims at storing and disseminating the previous formal and contextual knowledge to help teams make the correct decisions during the evolution of an emergency. The elicitation of critical requirements are provided by a case study based on Cognitive Work Analysis and Naturalistic Decision Making methods, applied to a nuclear emergency response simulation. The framework and a prototype system were tested in a controlled experiment. The paper reports the results of this experiment. (author)

Situation-assessment and decision-aid production-rule analysis system for nuclear plant monitoring and emergency preparedness

International Nuclear Information System (INIS)

Gvillo, D.; Ragheb, M.; Parker, M.; Swartz, S.

1987-01-01

A Production-Rule Analysis System is developed for Nuclear Plant Monitoring. The signals generated by the Zion-1 Plant are considered. A Situation-Assessment and Decision-Aid capability is provided for monitoring the integrity of the Plant Radiation, the Reactor Coolant, the Fuel Clad, and the Containment Systems. A total of 41 signals are currently fed as facts to an Inference Engine functioning in the backward-chaining mode and built along the same structure as the E-Mycin system. The Goal-Tree constituting the Knowledge Base was generated using a representation in the form of Fault Trees deduced from plant procedures information. The system is constructed in support of the Data Analysis and Emergency Preparedness tasks at the Illinois Radiological Emergency Assessment Center (REAC)

Situation-Assessment And Decision-Aid Production-Rule Analysis System For Nuclear Plant Monitoring And Emergency Preparedness

Science.gov (United States)

Gvillo, D.; Ragheb, M.; Parker, M.; Swartz, S.

1987-05-01

A Production-Rule Analysis System is developed for Nuclear Plant Monitoring. The signals generated by the Zion-1 Plant are considered. A Situation-Assessment and Decision-Aid capability is provided for monitoring the integrity of the Plant Radiation, the Reactor Coolant, the Fuel Clad, and the Containment Systems. A total of 41 signals are currently fed as facts to an Inference Engine functioning in the backward-chaining mode and built along the same structure as the E-Mycin system. The Goal-Tree constituting the Knowledge Base was generated using a representation in the form of Fault Trees deduced from plant procedures information. The system is constructed in support of the Data Analysis and Emergency Preparedness tasks at the Illinois Radiological Emergency Assessment Center (REAC).

Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants. Interim report

International Nuclear Information System (INIS)

1980-01-01

The purpose of this document is to provide a common reference and interim guidance source for: state and local governments and nuclear facility operators in the development of radiological emergency response plans and preparedness in support of nuclear power plants; and Nuclear Regulatory Commission (NRC), Federal Emergency Management Agency (FEMA) and other Federal agency personnel engaged in the review of state, local government, and licensee plans and preparedness

Comparison of nuclear plant emergency plans of PBNCC members

International Nuclear Information System (INIS)

Kato, W.Y.; Hopwood, J.M.

1987-01-01

The Nuclear Safety Working Group (NSWG) of the Pacific Basin Nuclear Cooperation Committee initiated cooperation among Pacific Basin areas based primarily around emergency planning. The NSWG conducted a review of the emergency response plans of members. This paper briefly reviews and makes a comparison of the emergency response plans, with particular attention on the response organization, the planning zone, and the protective action guidelines for emergencies. Although all areas have adopted the same basic elements of emergency planning and are similar, there are also variances due to different governmental structures, population densities, and available resources. It is found that the most significant difference is in the size of the emergency planning zone. The paper concludes with a discussion on possible future cooperative activities of the working group. (author)

Study of arcview GIS application in the nuclear power plant emergency response decision support system

International Nuclear Information System (INIS)

Li Peng; Chen Lin; Dong Binjiang

2003-01-01

It is very significant to apply the technique of GIS to the development of the Nuclear Power Plant Emergency Response Decision Support System. On the basis of the software system ArcView. This paper investigate the framework, the function and the development methods of the system. (authors)

Resources available for nuclear power plant emergencies under the Price-Anderson Act and the Robert T. Stafford Disaster Relief and Emergency Assistance Act

International Nuclear Information System (INIS)

1992-07-01

Through a series of TABLETOP exercises and other events that involved participation by State and Federal organizations, the need was identified for further explanation of financial and other related resources available to individuals and State and local governments in a major emergency at a nuclear power plant. A group with representatives from the Nuclear Regulatory commission, the Federal Emergency Management Agency, and the American Nuclear Insurers/Mutual Atomic Energy Liability Underwriters was established to work toward this end. This report is the result of that effort. This document is not meant to modify, undermine, or replace any other planning document (e.g., the Federal Radiological Emergency Response Plan or the Federal Response Plan). Its purpose is to clarify issues that have surfaced regarding resources available under the Price-Anderson and Stafford Acts

Nuclear power plant emergency preparedness: results from an evaluation of Michigan's potassium iodide distribution program.

Science.gov (United States)

Zwolinski, Laura R; Stanbury, Martha; Manente, Susan

2012-10-01

In 2009, the Michigan Department of Community Health (MDCH) made potassium iodide (KI), a nonprescription radio-protective drug, available by mailing vouchers redeemable at local pharmacies for KI tablets, at no cost to residents living within 10 miles of Michigan's 3 nuclear power plants (NPPs). MDCH conducted an evaluation of this program to determine Michigan's KI coverage and to assess general emergency preparedness among residents living near the NPPs. KI coverage was estimated based on redeemed voucher counts and the 2010 Census. Telephone surveys were administered to a random sample (N = 153) of residents living near Michigan's NPPs to evaluate general emergency preparedness, reasons for voucher use or nonuse, and KI knowledge. Only 5.3% of eligible residences redeemed KI vouchers. Most surveyed residents (76.5%) were aware of living near an NPP, yet 42.5% reported doing "nothing" to plan for an emergency. Almost half of surveyed voucher users did not know when to take KI or which body part KI protects. Among voucher nonusers, 48.0% were either unaware of the program or did not remember receiving a voucher. Additional efforts are needed to ensure that all residents are aware of the availability of KI and that recipients of the drug understand when and why it should be taken. Minimal emergency planning among residents living near Michigan's NPPs emphasizes the need for increased emergency preparedness and awareness. Findings are particularly salient given the March 2011 Fukushima Daiichi Nuclear Power Plant emergency in Japan.

Effects of soft control in the nuclear power plants emergency operation condition

International Nuclear Information System (INIS)

Al Harbi, Mohamed Ali Salem; Kim, Ar Ryum; Jang, Inseok; Seong, Poong Hyun; Shirouzu, Shigenori; Katayama, Sotetsu; Kang, Hyun Gook

2013-01-01

Highlights: ► We investigated the effect of touch screen, known as ESCM, which is a soft control, on emergency operation of nuclear plants. ► Experiments clearly show the occurrence of more human errors in ESCM task groups. ► Physiological measures (ECG, EEG, nose temperature) were analyzed. ► Higher stress levels were consistently observed in ESCM task groups. - Abstract: In addition to the evolution from buttons and switches to the computer-based consoles, the operator may interact with the plant via soft controls. Soft controls are input interfaces connected with control and display systems that are mediated by software, rather than by direct physical connections. However use of soft control may cause unknown difficulties of operation and provide new opportunities of human errors. This study is to investigate the effect of the new interface to human errors in the emergency operation. Based on the emergency operation procedure, the human error modes were identified by using systematic human error reduction and prediction approach. Experiments with 21 graduate students in main control room mockup in the nuclear engineering departments of universities in UAE and Korea were conducted to observe the operators’ behavior resulted from the use of new input interface (Emergency safety feature-component control system Soft Control Module, ESCM). Physiological parameters such as electroencephalogram, electrocardiogram and skin temperature were measured to assess the stress level of the subjects. The experimental results showed more human errors during ESCM tasks than non-ESCM tasks. The analysis of the physiological measurements also demonstrated that subjects were in high stress level during the ESCM tasks in comparison with non-ESCM tasks. It is notable that this study was performed with graduate students without consideration of their expertise levels. Different behaviors of the novice and the expert groups were also discussed

Online Decision Support System (IRODOS) - an emergency preparedness tool for handling offsite nuclear emergency

International Nuclear Information System (INIS)

Vinod Kumar, A.; Oza, R.B.; Chaudhury, P.; Suri, M.; Saindane, S.; Singh, K.D.; Bhargava, P.; Sharma, V.K.

2009-01-01

A real time online decision support system as a nuclear emergency response system for handling offsite nuclear emergency at the Nuclear Power Plants (NPPs) has been developed by Health, Safety and Environment Group, Bhabha Atomic Research Centre (BARC), Department of Atomic Energy (DAE) under the frame work of 'Indian Real time Online Decision Support System 'IRODOS'. (author)

Atmospheric release advisory capability pilot project at two nuclear power plants and associated state offices of emergency preparedness. Final report

International Nuclear Information System (INIS)

Rosen, L.C.

1983-01-01

A project to demonstrate the feasibility of utilizing Atmospheric Release Advisory Capability (ARAC) limited service with commercial nuclear power plants and their associated state offices of emergency preparedness is discussed. Preliminary planning, installation and testing of the ARAC site facilities at Indian Point Nucler Power Station, New York State; at New York State Office of Emergency Preparedness, Albany, New York; at Rancho Seco Nuclear Generating Station, California; and at the State of California Office of Emergency Services, Sacramento, California, are summarized. ARAC participation in the Robert E. Ginna nuclear generating plant accident in New York on January 25, 1982, is discussed. The ARAC system is evaluated with emphasis on communications, the suite of models contained within the ARAC system, and the staff. The implications of this project in designing the next-generation ARAC system to service federal and state needs are assessed

Draft emergency action level guidelines for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-09-15

This document is provided for interim use during the initial phases of the NRC effort to promptly improve emergency preparedness at operating nuclear power plants. Changes to the document can be expected as experience is gained in its use and public comments are received. Further, the Commission has initiated a rulemaking procedure, now scheduled for completion in January 1930 in the area of Emergency Planning and Preparedness. Additional requirements are to be expected when rulemaking is completed and some modifications to this document may be necessary. Four classes of Emergency Action Levels are established which replace the classes in Regulatory Guide 1.101, each with associated examples of initiating conditions. The classes are: - Notification of Unusual Event; - Alert; - Site Emergency; - General Emergency. The rationale for the notification and alert classes is to provide early and prompt notification of minor events which could lead to more serious consequences given operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. A gradation is provided to assure fuller response preparations for more serious indicators. The site emergency class reflects conditions where some significant releases are likely or are occurring but where a core melt situation is not indicated based on current information. In this situation full mobilization of emergency personnel in tie :near site environs is indicated as well as dispatch of monitoring teams and associated communications. The general emergency class involves actual or imminent substantial core degradation or malting with the potential for loss of containment. The immediate action for this class is sheltering (staying inside) rather thai evacuation until an assessment can be made that (1) an evacuation is indicated and (2) an evacuation, if indicated, can be completed prior to significant release and transport of radioactive material to the affected

Draft emergency action level guidelines for nuclear power plants

International Nuclear Information System (INIS)

1979-09-01

This document is provided for interim use during the initial phases of the NRC effort to promptly improve emergency preparedness at operating nuclear power plants. Changes to the document can be expected as experience is gained in its use and public comments are received. Further, the Commission has initiated a rulemaking procedure, now scheduled for completion in January 1930 in the area of Emergency Planning and Preparedness. Additional requirements are to be expected when rulemaking is completed and some modifications to this document may be necessary. Four classes of Emergency Action Levels are established which replace the classes in Regulatory Guide 1.101, each with associated examples of initiating conditions. The classes are: - Notification of Unusual Event; - Alert; - Site Emergency; - General Emergency. The rationale for the notification and alert classes is to provide early and prompt notification of minor events which could lead to more serious consequences given operator error or equipment failure or which might be indicative of more serious conditions which are not yet fully realized. A gradation is provided to assure fuller response preparations for more serious indicators. The site emergency class reflects conditions where some significant releases are likely or are occurring but where a core melt situation is not indicated based on current information. In this situation full mobilization of emergency personnel in tie :near site environs is indicated as well as dispatch of monitoring teams and associated communications. The general emergency class involves actual or imminent substantial core degradation or malting with the potential for loss of containment. The immediate action for this class is sheltering (staying inside) rather thai evacuation until an assessment can be made that (1) an evacuation is indicated and (2) an evacuation, if indicated, can be completed prior to significant release and transport of radioactive material to the affected

From reliability to maintenance of emergency generator sets in nuclear plants

International Nuclear Information System (INIS)

Reyraud, Y.

1986-01-01

The particular conditions of operation of emergency generator sets in a nuclear energy plant induce to take up a strategy of supervision and of maintenance very different of the one recommended for production generator sets. Mechanical and thermal pulls are affected by the size of the set and the choice of rotation running in respect of the wanted power and the response time requirements for the security of nuclear reactor. Reliability studies are helpful to define the strategy of supervision tests. The importance of the number of starts with respect to the running time requires the introduction of the idea of equivalent hours for the definition of maintenance periods. The security of the equipment and the upholding of the reliability at a value close to the optimum impose rigorous choices and strict conditions of supervision and maintenance [fr

Nuclear security - New challenge to the safety of nuclear power plants

International Nuclear Information System (INIS)

Li Ganjie

2008-01-01

The safety of nuclear power plants involves two aspects: one is to prevent nuclear accidents resulted from systems and equipments failure or human errors; the other is to refrain nuclear accidents from external intended attack. From this point of view, nuclear security is an organic part of the nuclear safety of power plants since they have basically the same goals and concrete measures with each other. In order to prevent malicious attacks; the concept of physical protection of nuclear facilities has been put forward. In many years, a series of codes and regulations as well as technical standard systems on physical protection had been developed at international level. The United Nations passed No. 1540 resolution as well as 'Convention on the Suppression of Acts of Nuclear terrorism', and revised 'Convention on Physical Protection of Nuclear Materials', which has enhanced a higher level capacity of preparedness by international community to deal with security issues of nuclear facilities. In China, in order to improve the capability of nuclear power plants on preventing and suppressing the external attacks, the Chinese government consecutively developed the related codes and standards as well as technical documents based on the existing laws and regulations, including 'Guide for the Nuclear Security of Nuclear Power Plants' and 'Guide for the Physical Protection of Nuclear Materials', so as to upgrade the legislative requirements for nuclear security in power plants. The government also made greater efforts to support the scientific research and staff training on physical protection, and satisfying the physical protection standards for newly-built nuclear facilities such as large scale nuclear power plants to meet requirement at international level. At the same time old facilities were renovated and the Chinese government established a nuclear emergency preparedness coordination mechanism, developed corresponding emergency preparedness plans, intensified the

The development of nuclear power and emergency response

International Nuclear Information System (INIS)

Pan Ziqiang

2007-01-01

Nuclear power is a safe, clean energy, which has been evidenced by the history of nuclear power development. Nuclear power is associated with very low risk but not equal to zero. Accident emergency response and preparedness is a final barrier necessary to reduce potential risks that may arise from nuclear power plants, which must be enhanced. In the course of accident emergency response and preparedness, it is highly necessary to draw domestic and foreign experiences and lessons. Lastly, the paper presents the discussions of some issues which merit attention with respect to emergency response and preparedness in China. (authors)

Mental workload measurement for emergency operating procedures in digital nuclear power plants.

Science.gov (United States)

Gao, Qin; Wang, Yang; Song, Fei; Li, Zhizhong; Dong, Xiaolu

2013-01-01

Mental workload is a major consideration for the design of emergency operation procedures (EOPs) in nuclear power plants. Continuous and objective measures are desired. This paper compares seven mental workload measurement methods (pupil size, blink rate, blink duration, heart rate variability, parasympathetic/sympathetic ratio, total power and (Goals, Operations, Methods, and Section Rules)-(Keystroke Level Model) GOMS-KLM-based workload index) with regard to sensitivity, validity and intrusiveness. Eighteen participants performed two computerised EOPs of different complexity levels, and mental workload measures were collected during the experiment. The results show that the blink rate is sensitive to both the difference in the overall task complexity and changes in peak complexity within EOPs, that the error rate is sensitive to the level of arousal and correlate to the step error rate and that blink duration increases over the task period in both low and high complexity EOPs. Cardiac measures were able to distinguish tasks with different overall complexity. The intrusiveness of the physiological instruments is acceptable. Finally, the six physiological measures were integrated using group method of data handling to predict perceived overall mental workload. The study compared seven measures for evaluating the mental workload with emergency operation procedure in nuclear power plants. An experiment with simulated procedures was carried out, and the results show that eye response measures are useful for assessing temporal changes of workload whereas cardiac measures are useful for evaluating the overall workload.

Development of reliability program for emergency diesel generators in domestic nuclear power plants

International Nuclear Information System (INIS)

Kim, Young Ho; Jung, Hyun Jong; Choi, Kwang Hee; Hong, Seoung Yeul

2001-01-01

Surveillance tests of Emergency Diesel Generators (EDGs) in Nuclear Power Plants (NPPs) have been conducted periodically to verify the reliability and integrity of the EDGs, however, it was found that these surveillance methods were so conservative and severe as to accelerate the degradation of the EDGs. Hence, new regulatory guideline, Reg. Guide 1.9 Rev. 3, was established by the U.S. NRC to resolve these problems. But it requires the additional implementation of reliability program of the EDGs to improve the actual reliability of them. In Korea, the EDGs of Yonggwang nuclear units 3 and 4 were the first plant applying new Reg. guide 1.9 rev.3 and implementing EDG reliability program. Furthermore it is expected that new guideline for the EDGs will be applied to other EDGs of Korean NPPs. In this paper, this reliability program is described, and it can be used as a reference for other EDGs in Korean NPPs

Emergency Response Resources guide for nuclear power plant emergencies

International Nuclear Information System (INIS)

1992-07-01

On August 28 and September 18, 1990, the States of Louisiana and Mississippi, Gulf States Utilities, five local parishes, six Federal agencies, and the American Nuclear Insurers participated in a post-emergency TABLETOP exercise in Baton Rouge, Louisiana. One of the products developed from that experience was this guide for understanding the responsibilities and obtaining resources for specific needs from the various participants, particularly from those organizations within the Federal Government. This first revision of that guide broadens the focus of the original document. Also, new information defines the major Federal response facilities. This guide should assist State and local government organizations with identifying and obtaining those resources for the post-emergency response when their resources have been exhausted

Development of nuclear emergency exercise programme (NEEP) in Korea

International Nuclear Information System (INIS)

Shin, H. K.; Kim, J. Y.; Kim, M. K.; Kim, S. H.

2011-01-01

The nuclear emergency exercise programme (NEEP) is a PC-based application intended for design and planning emergency preparedness and response (EP and R) exercises for a potential nuclear emergency in Korea. The application programme allows EP and R staff to create and edit exercise scenarios based on information customised for a specific nuclear power plant's emergency plans. NEEP includes the following features: (1) step-by-step guide to developing new exercise scenario according to emergency alarm level and potential accident type, (2) database of specific plant's field exercise scenarios that can be easily modified by users, (3) generating master scenario events list and messages of exercise participants and (4) allowing the quantitative evaluation of exercise participants from the view of exercise objectives and evaluator guides. NEEP also features tools for queries, reports and visualisation that can be used to create documentation during the scenario planning and exercise evaluation processes. (authors)

Safety in Swiss nuclear power plants

International Nuclear Information System (INIS)

Cederqvist, H.

1992-01-01

Safety-related facilities and equipment are continuously backfitted in Swiss nuclear power plants. In the Beznau-1 and -2 nuclear generating units, the measures taken under the heading of 'Backfitting of Emergency Systems' included provisions to enhance the protection against earthquakes, airplane crash, and fire; in addition, the emergency power system was upgraded. In Muehleberg, the stack exhaust air monitoring system was optimized. The containment pressure suppression system of the plant has been designed to withstand a hypothetical accident exceeding the design basis. The BKM-Crud computer simulation model simulates steps taken to reduce radiation exposure. The power of Swiss nuclear power stations will be raised by 4% to 15% within the 'Energy 2000' action program. (orig.) [de

Reevaluation of the emergency planning zone for nuclear power plants in Taiwan using MACCS2 code

International Nuclear Information System (INIS)

Wu, J.; Yang, Y.-M.; Chen, I.-J.; Chen, H.-T.; Chuang, K.-S.

2006-01-01

According to government regulations, the emergency planning zone (EPZ) of a nuclear power plant (NPP) must be designated before operation and reevaluated every 5 years. Corresponding emergency response planning (ERP) has to be made in advance to guarantee that all necessary resources are available under accidental releases of radioisotope. In this study, the EPZ for each of the three operating NPPs, Chinshan, Kuosheng, and Maanshan, in Taiwan was reevaluated using the MELCOR Accident Consequence Code System 2 (MACCS2) developed by Sandia National Laboratory. Meteorological data around the nuclear power plant were collected during 2003. The source term data including inventory, sensible heat content, and timing duration, were based on previous PRA information of each plant. The effective dose equivalent and thyroid dose together with the related individual risk and societal risk were calculated. By comparing the results to the protective action guide and related safety criteria, 1.5, 1.5, and 4.5 km were estimated for Chinshan, Kuosheng, and Maanshan NPPs, respectively. We suggest that a radius of 5.0 km is a reasonably conservative value of EPZ for each of the three operating NPPs in Taiwan

Analysis of emergency response to fukushima nuclear accident in Japan and suggestions for China's nuclear emergency management

International Nuclear Information System (INIS)

Li Wei; Ding Qihua; Wu Haosong

2014-01-01

On March 11, 2011, the Fukushima Dai-ichi Nuclear Power Station of the Tokyo Electric Power Company ('TEPCO') was hit and damaged by a magnitude 9 earthquake and accompanying tsunami. The accident is determined to be of the highest rating on the International Nuclear Event Scale. The Government of Japan and TEPCO have taken emergency response actions on-site and off-site at the accident. It became clear through the investigation that the accident had been initiated on the occasion of a natural disaster of an earthquake and tsunami, but there have been various complex problems behind this very serious and large scale accident. For an example, the then-available accident preventive measures and disaster preparedness of TEPCO were insufficient against tsunami and severe accidents; inadequate TEPCO emergency responses to the accident at the site were also identified. The accident rang the alarm for the nuclear safety of nuclear power plants. It also taught us a great of lessons in nuclear emergency management. (authors)

Emergency management in the countries without nuclear power plants: the Italian case study

International Nuclear Information System (INIS)

Franzero, S.; Giaimo, G.; Pizzi, R.

2003-01-01

Full text: Italy stopped the activity of its nuclear power plants (NPPs), built up starting from the '60s, alter the accident occurred at the Chernobyl NPP in 1986 and the suspension of the use of nuclear energy for pacific motives, sanctioned by a popular referendum in 1987. They are going to be decommissioned in the near future. In spite of this, Italian people are still exposed to a risk of nuclear or radiological accidents, due to the presence of 1) research centres making use of nuclear reactors (although without critical masses); 2) industrial plants and storage centres that manage radioactive and nuclear materials; 3) the chance of foreign ships with nuclear engines mooring in some Italian harbours. Actually, the worst scenario deals with the possibility of an accident occuring at a foreign NPP, especially if the NPP is located less than 200 Km from the national boundaries. Inside this distance, there are 13 NPPs (see picture 1, next page), 6 located in France, 4 in Switzerland, 2 in Germany and 1 in Slovenia. An accident occurring at one of those NPPs is the basic scenario of the 'National plan of the countermeasures against radiological emergencies', which was prepared in 1996 and is now under review. The plan reports in detail the actions that national and local authorities must take in order to contain the effects of a possible radioactive plume diffusion coming from foreign countries: 1) the procedures to activate the relevant authorities; 2) the command and control sequence for the emergency management (which put at the top the Department of Civil Protection - DCP - established in the Presidency of the Council of Ministers); 3) the procedures for the information exchange between authorities and the people likely to be involved in the accident. In addition to the planned procedures, the Italian authorities have many technical and scientific tools at their disposal to survey disasters. Since the 80s, Italy has been provided with a national automatic

Development of the efficient emergency preparedness system for the nuclear critical infrastructure

International Nuclear Information System (INIS)

Kostadinov, V.; Marn, J.; Petelin, S.

2007-01-01

The evaluation of the critical nuclear infrastructure vulnerability to threats like human occurrences, terrorist attacks and natural disasters and the preparation of emergency response plans with the estimation of optimized costs are of the vital importance for the assurance of a safe nuclear facilities operation and the national security. In the past national emergency systems did not include vulnerability assessments of the critical nuclear infrastructure as the important part of the comprehensive preparedness framework. The fundamental aims of the efficient emergency preparedness and response system are to provide a sustained emergency readiness and to prevent an emergency situation and accidents. But when an event happens the mission is to mitigate consequences and to protect the people and environment against the nuclear and radiological damage. The efficient emergency response system, which would be activated in the case of the nuclear and/or radiological emergency and release of the radioactivity to the environment, is an important element of a comprehensive system of the nuclear and radiation safety. In the article the new methodology for the critical nuclear infrastructure vulnerability assessment as a missing part of an efficient emergency preparedness system is presented. It can help the overall national energy sectors to identify and better understand the terrorist threats and vulnerabilities of their critical infrastructure. The presented methodology could also facilitate national agencies to develop and implement a vulnerability awareness and education programs for their critical assets to enhance the security, reliability and safe operation of the whole energy infrastructure. The vulnerability assessment methodology will also assist nuclear power plants to develop, validate, and disseminate the assessment and survey of new efficient countermeasures. The significant benefits of the new vulnerability assessment research are to increase nuclear power

Improving operator quality at Genkai Nuclear Power Plant

International Nuclear Information System (INIS)

Kuwano, Takeshi.

1989-01-01

Improvement in operator quality, or improvement in an operator's skill and professional knowledge, is of prime importance because of its great influence on safe and steady plant operation. This paper describes the education and training of reactor operators at the Genkai pressurized water reactor nuclear power plant with respect to the following topics: organization of Genkai power plant; education and training program management; training at the Nuclear Training Center; training and education on-site including emergency procedures training, normal operating procedures training, informational study of emergency conditions in existing plants, and all-around training of operators; qualifying tests for supervisors; and operator motivation

Effort on Nuclear Power Plants safety

International Nuclear Information System (INIS)

Prayoto.

1979-01-01

Prospects of nuclear power plant on designing, building and operation covering natural safety, technical safety, and emergency safety are discussed. Several problems and their solutions and nuclear energy operation in developing countries especially control and permission are also discussed. (author tr.)

A knowledge based operator support system for emergency conditions in nuclear power plants

International Nuclear Information System (INIS)

Venkatesh Babu, C.; Subramanium, K.

1992-01-01

The control centres of the operating Indian nuclear power plants contain a large number of indicators and controls spread over many panels. In the event of onset of an emergency condition, there results a profusion of information, both numeric and symbolic. The operator may succumb to an information and cognitive overload that may be compounded by a lack of knowledge. The failure to apply knowledge and reasoning to solve an operational problem can lead to human error, which has been a major contributing factor in nuclear accidents. From the viewpoint of Artificial Intelligence, human error occurs if the operational problem requires computing resources that exceed human capabilities. The application of Artificial Intelligence, particularly expert systems, to nuclear power plant control room activities has considerable potential to reduce operator error and improve safety and reliability. The purpose of this paper is to discuss an investigative study of the feasibility of developing an operator support system incorporating Artificial Intelligence techniques. An information processing model of such a system, herein designated as Knowledge Based Operator Support System - KBOSS, employing expert systems technology, has been developed. The features of this system are described, and issues involved in its development are discussed. (author). 2 refs., 5 figs., 1 tab

Research of the improvement of the process, organization, etc. related to the emergency correspondence of JNES based on the cause analysis about emergency correspondence of JNES in case of the Fukushima Dai-ichi nuclear power plant accident

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

At the time of the occurrence of the Fukushima Dai-ichi nuclear power plant accident, JNES implemented various emergency correspondences. On the other hand, various organizations published the report about the Fukushima Dai-ichi nuclear power plant accident. In them, the problems about the regulatory body's regulatory process, regulatory organization, etc. are also pointed out. JNES is a designated public institution. JNES is required to improve process, organization, etc. related to emergency correspondence continuously based on the lessons learned obtained from the emergency corresponding experience about the Fukushima Dai-ichi nuclear power plant accident. Specifically, the following activities will be implemented in the 2014 and 2015 fiscal year. 1. Collect systematically and comprehensively the information about emergency correspondence of JNES in case of the Fukushima Dai-ichi nuclear power plant accident, and create the timeline of the event. 2. Specify problems and analyze human factors and organizational factors. 3. Specify the requirements for establishing a designated public institution's emergency correspondence based on the viewpoint of a human and an organization. 4. Publish the report which indicates collected information, the contents of analysis, proposals of improvement, etc. (author)

Network of siren, public address and display system to preparedness and response for nuclear emergencies

International Nuclear Information System (INIS)

Joshi, G.H.; Padmanabhan, N.; Raman, N.; Pradeepkumar, K.S.; Sharma, D.N.; Abani, M.C.

2003-01-01

For an effective emergency response and implementation of counter measures, communication during a nuclear emergency is a very important aspect. The declaration of a nuclear emergency must be immediately conveyed to all those working in the plant and around the nuclear site. Besides this, the nature of emergency also needs to be conveyed unambiguously along with corresponding counter measures, such as stay in, evacuation or all clear signal for the relevant plants. This requirement has necessitated the need for a networked signaling system. Based on this requirement, a microcontroller based signaling and a telephone/wireless based communication and display system has been designed at Bhabha Atomic Research Centre. It is proposed to be used as a part of emergency preparedness and response programme at the nuclear facility sites. As per the design made for Bhabha Atomic Research Centre, Trombay site, each plant or area in the site is identified by a unique identification code. The main Site Emergency Control Centre/Emergency Response Centre at Mod. Labs. selectively calls the various plants and declares the nature of emergency to be followed In that plant/area through different siren signals along with display and announcement of instructions. This paper describes the details of the system that is designed for Bhabha Atomic Research Centre, Trombay site and proposed for other nuclear power plant sites. (author)

Explanation of procedure on site medical emergency response for nuclear accident

International Nuclear Information System (INIS)

Liu Yulong; Jiang Zhong

2012-01-01

National occupational health standard-Procedure on Site Medical Emergency Response for Nuclear Accident has been approved and issued by the Ministry of Health. This standard is formulated according to the Emergency Response Law of the People's Republic of China, Law of the People 's Republic of China on Prevention and Control of Occupational Diseases, Regulations on Emergency Measures for Nuclear Accidents at Nuclear Power Plants, and Health Emergency Plans for Nuclear and Radiological Accidents of Ministry of Health, supporting the use of On-site Medical Emergency Planning and Preparedness for Nuclear Accidents and Off-site Medical Emergency Planning and Preparedness for Nuclear Accidents. Nuclear accident on-site medical response procedure is a part of the on-site emergency plan. The standard specifies the basic content and requirements of the nuclear accident on-site medical emergency response procedures of nuclear facilities operating units to guide and regulate the work of nuclear accident on-site medical emergency response of nuclear facilities operating units. The criteria-related contents were interpreted in this article. (authors)

Pre-fire planning for nuclear power plants

International Nuclear Information System (INIS)

Talbert, J.H.

1980-01-01

Regardless of the fire prevention measures which are taken, plant experience indicates that fires will occur in a nuclear power plant. When a fire occurs, the plant staff must handle the fire emergency. Pre-fire planning is a method of developing detailed fire attack plans and salvage operations to protect equipment from damage due to fire and fire fighting operations. This paper describes the purpose and use of a pre-fire plan to achieve these goals in nuclear power plants

Trial application of reliability technology to emergency diesel generators at the Trojan Nuclear Power Plant

International Nuclear Information System (INIS)

Wong, S.M.; Boccio, J.L.; Karimian, S.; Azarm, M.A.; Carbonaro, J.; DeMoss, G.

1986-01-01

In this paper, a trial application of reliability technology to the emergency diesel generator system at the Trojan Nuclear Power Plant is presented. An approach for formulating a reliability program plan for this system is being developed. The trial application has shown that a reliability program process, using risk- and reliability-based techniques, can be interwoven into current plant operational activities to help in controlling, analyzing, and predicting faults that can challenge safety systems. With the cooperation of the utility, Portland General Electric Co., this reliability program can eventually be implemented at Trojan to track its effectiveness

RODOS-based simulation of potential accident scenarios for emergency response management in the vicinity of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Walter, H.; Gering, F.; Arnold, K.; Gerich, B.; Heinrich, G.; Welte, U.

2016-09-15

In the wake of the Fukushima disaster in March 2011, the German Federal Office for Radiation Protection (BfS) started to investigate the potential radiological consequences of a ''Fukushima-like'' accident in a German nuclear power plant and conducted appropriate simulations in 2012. Between the end of 2012 and the end of 2013, the first study was followed by a much more detailed and comprehensive investigation comprising more than 5000 case studies for three nuclear power plant (NPP) sites in Germany. Based on these results the German Commission on Radiological Protection (SSK) released a new recommendation in March 2014 including an expansion of the current emergency planning zones for nuclear power plants in Germany. The key results of this study with respect to the maximum dimensions of the affected areas where dose criteria may be exceeded are described below. The following results are based on the largest nuclear release scenario ''FKA'' (INES scale 7): - Threshold levels for deterministic effects and high doses (effective doses higher than 1000 mSv) can be reached or exceeded within a distance of about 3 km on average. - The emergency reference level for the intervention ''Evacuation'' can be reached or exceeded within a distance of up to 9 to 18 km (adults) and/or up to 14 to 24 km (infants) on average (the indicated interval describes the minimum and maximum levels of the median value at all three NPP sites). - The emergency reference level for the intervention ''Sheltering'' can be reached or exceeded within a distance of up to 62 to 80 km (adults) and/or up to 91 to 114 km (infants) on average. - The emergency reference level for the intervention ''Stable iodine prophylaxis'' can be exceeded within a distance of up to 24 to 34 km (adults) and/or up to 148 to 161 km (infants and pregnant women) on average.

Emergency measures following hypothetical actions against nuclear facilities in Italy

International Nuclear Information System (INIS)

Rogani, A.; Tabet, E.

2003-01-01

Full text: After the Chernobyl accident a national emergency plan of protective measures for radiological emergencies has been set up in Italy to cope with nuclear risks which require actions at national level. Since most of the Italian nuclear installations are, at present, not operational, the most relevant nuclear risk sources identified in the national emergency plan stem from accidents in nuclear power plants near the Italian borders or aboard nuclearpropelled ships, or events related to the fall of nuclear-powered satellites and transportation of radioactive materials. The plan identifies a reference scenario for nation-wide emergency interventions and the proper structures to be involved in the radiological emergency. However, risks related to nuclear terrorism are not taken into account in the plan, whereas nuclear plants as well as nuclear materials and sources (in use in medical, scientific and industrial applications) are known to represent potential targets for hostile acts, potentially giving rise to harmful radioactive releases into the atmosphere. Along with four nuclear power plants, now undergoing a decommissioning procedure, several other nuclear facilities, such as provisional radioactive waste deposits or research centers, are present in Italy. Unfortunately not all of the radioactive waste inventory is conditioned in such a way to make a spread of radioactive contamination, as a consequence of a hostile action, unlikely; moreover, spent fuel elements are still kept, in some cases, inside the plant spent fuel storage pool. In this paper the hypothetical radiological impact of deliberate actions against some reference nuclear installations will be evaluated, together with its amplications for an appropriate profiling of the emergency countermeasures which could be required. Especially the case of a terrorism act against a spent fuel storage pool is worked out in some detail, as this event appears to be one of those with the most severe

Method and apparatus for emergency cooling of a nuclear power plant

International Nuclear Information System (INIS)

Naito, Masanori; Chino, Koichi; Sato, Chikara; Inoue, Hisamichi.

1978-01-01

Purpose: To improve the cooling effect of spray water by eliminating the flow control effect for spray water due to increase in the steam pressure and flowing the entire spray water into the reactor core. Constitution: Upon emergency cooling of a reactor core by spraying coolants from above at the loss of coolant accident in a nuclear power plant, coolant is sprayed in a state where the temperature upon flowing into the reactor core is below the saturated temperature after heat exchange with vapors rising from the core. This enables to apply spray water always at a temperature and a flow rate in the range of whole volume falling irrespective of the water temperature in a pressure suppression pool. (Furukawa, Y.)

Emergency planning and preparedness for a nuclear accident

International Nuclear Information System (INIS)

Rahe, E.P.

1985-01-01

Based on current regulations, FEMA approves each site-specific plan of state and local governments for each power reactor site after 1) formal review offsite preparedness, 2) holding a public meeting at which the preparedness status has been reviewed, and 3) a satisfactory joint exercise has been conducted with both utility and local participation. Annually, each state, within any position of the 10-mile emergency planning zone, must conduct a joint exercise with the utility to demonstrate its preparedness for a nuclear accident. While it is unlikely that these extreme measures will be needed as a result of an accident at a nuclear power station, the fact that these plans have been well thought out and implemented have already proven their benefit to society. The preparedness for a nuclear accident can be of great advantage in other types of emergencies. For example, on December 11, 1982, a non-nuclear chemical storage tank exploded at a Union Carbide plant in Louisiana shortly after midnight. More than 20,000 people were evacuated from their homes. They were evacuated under the emergency response plan formulated for use in the event of a nuclear accident at the nearby Waterford Nuclear plants. Clearly, this illustrates how a plan conceived for one purpose is appropriate to handle other types of accidents that occur in a modern industrial society

Criteria for preparation and evaluation of radiological emergency response plans and preparedness in support of nuclear power plants: Criteria for utility offsite planning and preparedness: Final report

International Nuclear Information System (INIS)

Podolak, E.M. Jr.; Sanders, M.E.; Wingert, V.L.; Donovan, R.W.

1988-09-01

The Nuclear Regulatory Commission (NRC) and the Federal Emergency Management Agency (FEMA) have added a supplement to NUREG-0654/FEMA-REP-1, Rev. 1 that provides guidance for the development, review, and evaluation of utility offsite radiological emergency response planning and preparedness for those situations in which state and/or local governments decline to participate in emergency planning. While this guidance primarily applies to plants that do not have full-power operating licenses, it does have relevance to operating nuclear power plants

A prototype nuclear emergency response decision making expert system

International Nuclear Information System (INIS)

Chang, C.; Shih, C.; Hong, M.; Yu, W.; Su, M.; Wang, S.

1990-01-01

A prototype of emergency response expert system developed for nuclear power plants, has been fulfilled by Institute of Nuclear Energy Research. Key elements that have been implemented for emergency response include radioactive material dispersion assessment, dynamic transportation evacuation assessment, and meteorological parametric forecasting. A network system consists of five 80386 Personal Computers (PCs) has been installed to perform the system functions above. A further project is still continuing to achieve a more complicated and fanciful computer aid integral emergency response expert system

Evaluating nuclear power plant crew performance during emergency response drills

International Nuclear Information System (INIS)

Rabin, D.

1999-01-01

The Atomic Energy Control Board (AECB) is responsible for the regulation of the health, safety and environmental consequences of nuclear activities in Canada. Recently, the Human Factors Specialists of the AECB have become involved in the assessment of emergency preparedness and emergency response at nuclear facilities. One key contribution to existing AECB methodology is the introduction of Behaviourally Anchored Rating Scales (BARS) to measure crew interaction skills during emergency response drills. This report presents results of an on-going pilot study to determine if the BARS provide a reliable and valid means of rating the key dimensions of communications, openness, task coordination and adaptability under simulated emergency circumstances. To date, the objectivity of the BARS is supported by good inter-rater reliability while the validity of the BARS is supported by the agreement between ratings of crew interaction and qualitative and quantitative observations of crew performance. (author)

A database for human performance under simulated emergencies of nuclear power plants

International Nuclear Information System (INIS)

Park, Jin Kyun; Jung, Won Dea

2005-01-01

Reliable human performance is a prerequisite in securing the safety of complicated process systems such as nuclear power plants. However, the amount of available knowledge that can explain why operators deviate from an expected performance level is so small because of the infrequency of real accidents. Therefore, in this study, a database that contains a set of useful information extracted from simulated emergencies was developed in order to provide important clues for understanding the change of operators' performance under stressful conditions (i.e., real accidents). The database was developed under Microsoft Windows TM environment using Microsoft Access 97 TM and Microsoft Visual Basic 6.0 TM . In the database, operators' performance data obtained from the analysis of over 100 audio-visual records for simulated emergencies were stored using twenty kinds of distinctive data fields. A total of ten kinds of operators' performance data are available from the developed database. Although it is still difficult to predict operators' performance under stressful conditions based on the results of simulated emergencies, simulation studies remain the most feasible way to scrutinize performance. Accordingly, it is expected that the performance data of this study will provide a concrete foundation for understanding the change of operators' performance in emergency situations

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

International Nuclear Information System (INIS)

2001-01-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

Ventilation-air conditioner system in nuclear power plant

International Nuclear Information System (INIS)

Kubota, Ryuji; Sugisaki, Toshihiko.

1989-01-01

This invention concerns a ventilation-air conditioner system which enables, upon occurrence of accidents in a nuclear power plant, continuous operation for other adjacent nuclear power plants with no effect of accidents. Air supply system and exhaust system are operated during usual operaiton. If loss of coolants accidents should occur in an adjacent nuclear power plants, operation is switched from ventilation operaiton to the operation of re-cycling system based on an AND logic of three signals, that is, a pressure HIGH signal for the reactor container, a water level LOW signal for the reactor and a radioactivity signal of the ventilation-air conditioner sytem on the side of air supply in the nuclear power plant. Thus, nuclear reactor buildings of the nuclear power plant are from the external atmosphere. Therefore, the radioactivity HIGH signal for switching to the emergency air conditioner system of the nuclear power plant is not actuated due to the loss of coolant accidents in the adjacent nuclear power plant. In addition, since the atmospheric temperature in the nuclear reactor building can be maintained by a cooling device disposed to the recycling system, reactor shutdown can be prevented. (I.S.)

Role of security during safety-related emergencies at nuclear power plants

International Nuclear Information System (INIS)

Cardwell, R.G.; Moul, D.A.; McBride, J.A.; Wilson, C.W.

1984-03-01

This report provides an analysis of the literature and on-site data gathering relating to the actions of security forces at licensed nuclear power plants during safety-related emergencies. Literature search findings and results of on-site data gathering are furnished and subjected to analysis. Taking into account the analysis provided, appropriate recommendations are presented. Recommendations are keyed as to how improvements can be made in the regulatory approach and licensee planning and procedures as they relate to the subject matter under examination. In addition, certain technological problems and issues are examined within the context of the study. Appendices provide the results of the literature search, an annotated bibliography, the Data Collection Guide used, and additional details regarding certain aspects of the study that are relevant for further explication of the body of the report

Pumps in nuclear power plants

International Nuclear Information System (INIS)

Kim, J.H.

1991-01-01

This paper reports that pumps play an important role in nuclear plant operation. For instance, reactor coolant pumps (RCPs) should provide adequate cooling for reactor core in both normal operation and transient or accident conditions. Pumps such as Low Pressure Safety Injection (LPSI) pump in the Emergency Core Cooling System (ECCS) play a crucial role during an accident, and their reliability is of paramount importance. Some key issues involved with pumps in nuclear plant system include the performance of RCP under two-phase flow conditions, piping vibration due to pump operating in two-phase flows, and reliability of LPSI pumps

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1994-06-01

Quarterly reports on the operation of the Finnish NPPs describe nuclear and radiation safety related events and observations which the Finnish Centre for Radiation and Nuclear Safety considers significant. Safety improvements at the plants and general matters relating to the use of nuclear energy are also reported. A summary of the radiation safety of plant personnel and the environment, and tabulated data on the plants' production and load factors are also given. One event during the last quarter of 1993 was rated on the International Nuclear Event Scale (INES) as level 1. During this event at Loviisa 2, the secondary circuit emergency feedwater system was erroneously isolated from automatic start-up readiness. The error went unnoticed for 4.5 hours. During 1993 one level 2 incident and three level 1 incidents occurred at the Finnish NPPs. (8 figs., 4 tabs.)

Nuclear threats and emergency preparedness in Finland

International Nuclear Information System (INIS)

Mustonen, R.; Aaltonen, H.; Laaksonen, J.; Lahtinen, J.; Rantavaara, A.; Reponen, H.; Rytoemaa, T.; Suomela, M.; Toivonen, H.; Varjoranta, T.

1995-10-01

The political and economic upheavals which have taken place in Eastern Europe have had an impact on radiation and nuclear safety throughout Europe. Emergency preparedness systems for unexpected nuclear events have been developed further in all European countries, and prosperous western nations have invested in improving the safety of East European nuclear power plants. The economic crisis facing countries of the former Soviet Union has also promoted illicit trade in nuclear materials; this has made it necessary for various border guards and police authorities to intensify their collaboration and to tighten border controls. On 3-4 October 1995, Finnish Centre for Radiation and Nuclear Safety (STUK) arranged a seminar on nuclear threats and emergency preparedness in Finland. In addition to STUK experts, a wide range of rescue and civil defence authorities, environmental health specialists and other persons engaged in emergency preparedness attended the seminar. The publication contains a compilation of reports presented at the seminar. The reports cover a broad spectrum of nuclear threats analyzed at STUK, the impacts of radioactive fallout on human beings and on the environment, and preparedness systems by which the harmful effects of radiation or nuclear accidents can, if necessary, be minimized. (33 figs., 5 tabs.)

Design of test and emergency procedures to improve operator behaviour in French nuclear power plants

International Nuclear Information System (INIS)

Griffon-Fouco, M.; Gomolinski, M.

1982-09-01

The incident analyses performed in French nuclear power plants high-lighted that deficiencies in the design of procedures are frequent causes of human errors. The process for developing new guidelines for the writing of test and emergency procedures is presented: this process is based on operators interviews and observations at the plants or at simulators. The main principles for the writing of procedures are developed. For example: - the elaboration of a procedure for action and of a separate educational procedure, - the coordination of crew responses, - the choice of vocabulary, graphs, flow charts and so on as regards the format. Other complementary actions, such as the training of operators in the use of procedures, are described

Design of test and emergency procedures to improve operator behavior in French nuclear power plants

International Nuclear Information System (INIS)

Griffon-Fouco, M.; Gomolinski, M.

1983-01-01

The incident analyses performed in French nuclear power plants high-lighted that deficiencies in the design of procedures are frequent causes of human errors. The process for developing new guidelines for the writing of test and emergency procedures is presented: this process is based on operators interviews and observations at the plants or at simulators. The main principles for the writing of procedures are developed. For example: the elaboration of a procedure for action and of separate educational procedure; the coordination of crew responses; and the choice of vocabulary, graphs, flow charts and so on as regards the format. Other complementary actions, such as the training of operators in the use of procedures, are described

Nuclear power plants

International Nuclear Information System (INIS)

1985-01-01

Data concerning the existing nuclear power plants in the world are presented. The data was retrieved from the SIEN (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: nuclear plants, its status and type; installed nuclear power plants by country; nuclear power plants under construction by country; planned nuclear power plants by country; cancelled nuclear power plants by country; shut-down nuclear power plants by country. (E.G.) [pt

Nigeria status on capabilities for response to nuclear or radiological emergency

International Nuclear Information System (INIS)

Sambo, I.; Elegba, S.B.; Ogharandukun, M.

2007-01-01

The use of nuclear technology has been widely employed and will continue to expand in use in Nigeria particularly in the health, industrial, mining, water resources, agriculture, manufacturing, education and research sectors. Incidents and emergencies cannot therefore be ruled out. Effective national response capabilities are essential to minimize the impacts from nuclear and radiological emergencies, and to build public trust in the safety and security of nuclear technology. The often discussed Nigeria's Nuclear Power Plant (NPP) project cannot occur without enhanced national capabilities to respond to an incidence or emergency. Moreover, increased concern over the use of nuclear or radioactive materials malevolent acts increases the need to broaden response capabilities. This paper examines Nigeria's status on capabilities for response to a nuclear and radiological emergency vis-a-vis international requirements for effective response capabilities

Preliminary regulatory assessment of nuclear power plants vulnerabilities

International Nuclear Information System (INIS)

Kostadinov, V.; Petelin, S.

2004-01-01

Preliminary attempts to develop models for nuclear regulatory vulnerability assessment of nuclear power plants are presented. Development of the philosophy and computer tools could be new and important insight for management of nuclear operators and nuclear regulatory bodies who face difficult questions about how to assess the vulnerability of nuclear power plants and other nuclear facilities to external and internal threats. In the situation where different and hidden threat sources are dispersed throughout the world, the assessment of security and safe operation of nuclear power plants is very important. Capability to evaluate plant vulnerability to different kinds of threats, like human and natural occurrences and terrorist attacks and preparation of emergency response plans and estimation of costs are of vital importance for assurance of national security. On the basis of such vital insights, nuclear operators and nuclear regulatory bodies could plan and optimise changes in oversight procedures, organisations, equipment, hardware and software to reduce risks taking into account security and safety of nuclear power plants operation, budget, manpower, and other limitations. Initial qualitative estimations of adapted assessments for nuclear applications are shortly presented. (author)

A reliability program for emergency diesel generators at nuclear power plants: Maintenance, surveillance, and condition monitoring

International Nuclear Information System (INIS)

Lofgren, E.V.; Henderson, W.; Burghardt, D.; Kripps, L.; Rothleder, B.

1988-12-01

This report is a companion report on NUREG/CR-5078, Volume 1, ''A Reliability Program for Emergency Diesel Generators at Nuclear Power Plants: Program Structure.'' The purpose of this report is to provide technical findings and insights related to: failure evaluation, troubleshooting, maintenance, surveillance, and condition monitoring. Examples and recommendations are provided for each of these areas based on actual emergency diesel generator (EDG) operating experience and the opinions of diesel generator experts. This report expands the more general guidance provided in Volume 1. In addition, a discussion of EDG interactions with other plant systems (e.g., instrument, air, service water, dc power) is provided since experience has shown that these support systems and their operation can adversely affect EDG reliability. Portions of this report have been designed for use by onsite personnel for evaluating operational characteristics of EDGs. 5 refs., 8 figs., 7 tabs

Emergency preparedness for the accidental release of radionuclides from the Uljin Nuclear Power Plant in Korea.

Science.gov (United States)

Park, Soon-Ung; Lee, In-Hye; Joo, Seung Jin; Ju, Jae-Won

2017-12-01

Site specific radionuclide dispersion databases were archived for the emergency response to the hypothetical releases of 137 Cs from the Uljin nuclear power plant in Korea. These databases were obtained with the horizontal resolution of 1.5 km in the local domain centered the power plant site by simulations of the Lagrangian Particle Dispersion Model (LPDM) with the Unified Model (UM)-Local Data Assimilation Prediction System (LDAPS). The Eulerian Dispersion Model-East Asia (EDM-EA) with the UM-Global Data Assimilation Prediction System (UM-GDAPS) meteorological models was used to get dispersion databases in the regional domain. The LPDM model was performed for a year with a 5-day interval yielding 72 synoptic time-scale cases in a year. For each case hourly mean near surface concentrations, hourly mean column integrated concentrations, hourly total depositions for 5 consecutive days were archived by the LPDM model in the local domain and by the EDM-EA model in the regional domain of Asia. Among 72 synoptic cases in a year the worst synoptic case that showed the highest mean surface concentration averaged for 5 days in the LPDM model domain was chosen to illustrate the emergency preparedness to the hypothetical accident at the site. The simulated results by the LPDM model with the 137 Cs emission rate of the Fukushima nuclear power plant accident for the first 5-day period were found to be able to provide prerequisite information for the emergency response to the early phase of the accident whereas those of the EDM-EA model could provide information required for the environmental impact assessment of the accident in the regional domain. The archived site-specific database of 72 synoptic cases in a year could have a great potential to be used as a prognostic information on the emergency preparedness for the early phase of accident. Copyright © 2017 Elsevier Ltd. All rights reserved.

Research on evacuation planning as nuclear emergency preparedness

International Nuclear Information System (INIS)

Yamamoto, Kazuya

2007-10-01

The International Atomic Energy Agency (IAEA) has introduced new concepts of precautionary action zone (PAZ) and urgent protective action planning zone (UPZ) in 'Preparedness and Response for a Nuclear or Radiological Emergency' (GS-R-2 (2002)), in order to reduce substantially the risk of severe deterministic health effects. Open literature based research was made to reveal problems on evacuation planning and the preparedness for nuclear emergency arising from introduction of PAZ into Japan that has applied the emergency planning zone (EPZ) concept currently. In regard to application of PAZ, it should be noted that the requirements for preparedness and response for a nuclear or radiological emergency are not only dimensional but also timely. The principal issue is implementation of evacuation of precautionary decided area within several hours. The logic of evacuation planning for a nuclear emergency and the methods of advance public education and information in the U.S. is effective for even prompt evacuation to the outside of the EPZ. As concerns evacuation planning for a nuclear emergency in Japan, several important issues to be considered were found, that is, selection of public reception centers which are outside area of the EPZ, an unique reception center assigned to each emergency response planning area, public education and information of practical details about the evacuation plan in advance, and necessity of the evacuation time estimates. To establish a practical evacuation planning guide for nuclear emergencies, further researches on application of traffic simulation technology to evacuation time estimates and on knowledge of actual evacuation experience in natural disasters and chemical plant accidents are required. (author)

National emergency medical assistance program for commercial nuclear power plants

International Nuclear Information System (INIS)

Linnemann, R.E.; Berger, M.E.

1987-01-01

Radiation Management Consultant's Emergency Medical Assistance Program (EMAP) for nuclear facilities provides a twenty-four hour emergency medical and health physics response capability, training of site and off-site personnel, and three levels of care for radiation accident victims: first air and rescue at an accident site, hospital emergency assessment and treatment, and definitive evaluation and treatment at a specialized medical center. These aspects of emergency preparedness and fifteen years of experience in dealing with medical personnel and patients with real or suspected radiation injury will be reviewed

Development of CSA N1600-14: general requirements for nuclear emergency management programs

Energy Technology Data Exchange (ETDEWEB)

Sellar, C. [Canadian Standards Association Group, Mississauga, ON (Canada); Coles, J. [Ontario Power Generation, Darlington, ON (Canada)

2014-07-01

CSA Group has published a new standard on General requirements for nuclear emergency management programs (CSA N1600-14). The standard establishes criteria for the emergency management programs of on- and off-site organizations to address nuclear emergencies at Canadian nuclear power plants (NPPs). It provides the requirements to develop, implement, evaluate, maintain, and continuously improve a nuclear emergency management program for prevention and mitigation, preparedness, response, and recovery from a nuclear emergency at a NPP. This paper discusses the development of the standard, and provides the key drivers, structure, scope, and outline of the standard, while highlighting key features, impacts, and benefits. (author)

Developing new methodology for nuclear power plants vulnerability assessment

International Nuclear Information System (INIS)

Kostadinov, Venceslav

2011-01-01

Research highlights: → Paper presents new methodology for vulnerability assessment of nuclear power plants. → First universal quantitative risks assessment model for terrorist attack on a NPPs. → New model enhance security, reliability and safe operation of all energy infrastructure. → Significant research benefits: increased NPPs security, reliability and availability. → Useful new tool for PRA application to evaluation of terrorist threats on NPPs. - Abstract: The fundamental aim of an efficient regulatory emergency preparedness and response system is to provide sustained emergency readiness and to prevent emergency situations and accidents. But when an event occurs, the regulatory mission is to mitigate consequences and to protect people and the environment against nuclear and radiological damage. The regulatory emergency response system, which would be activated in the case of a nuclear and/or radiological emergency and release of radioactivity to the environment, is an important element of a comprehensive national regulatory system of nuclear and radiation safety. In the past, national emergency systems explicitly did not include vulnerability assessments of the critical nuclear infrastructure as an important part of a comprehensive preparedness framework. But after the huge terrorist attack on 11/09/2001, decision-makers became aware that critical nuclear infrastructure could also be an attractive target to terrorism, with the purpose of using the physical and radioactive properties of the nuclear material to cause mass casualties, property damage, and detrimental economic and/or environmental impacts. The necessity to evaluate critical nuclear infrastructure vulnerability to threats like human errors, terrorist attacks and natural disasters, as well as preparation of emergency response plans with estimation of optimized costs, are of vital importance for assurance of safe nuclear facilities operation and national security. In this paper presented

Fire prevention in nuclear plants

International Nuclear Information System (INIS)

Cayla, J.P.; Jacquet-Francillon, J.; Matarozzo, F.

2014-01-01

About 80 fire starts are reported in EDF nuclear power plants every year but only 3 or 4 turn into a real fire and none has, so far, has led to a major safety failure of a nuclear plant. A new regulation has been implemented in july 2014 that strengthens the concept of defense in depth, proposes an approach that is proportionate to the stakes and risks, this proportionality means that the requirements for a power reactor are not the same as for a nuclear laboratory, and imposes an obligation or result rather than of means. The second article deals with the fire that broke out in the waste silo number 130 at La Hague plant in january 1981. The investigation showed that the flammability of the silo content had been underestimated. The third article presents the consequences of the fire that broke out in a power transformer at the Cattenom plant in june 2013. The fire was rapidly brought under control thanks to the immediate triggering of the emergency plan. The article details also the feedback experience of this event. (A.C.)

Guidelines for attendance and registration for radiological emergencies of nuclear accidents

International Nuclear Information System (INIS)

1994-01-01

Today in Brazil the use of nuclear energy is becoming an usual practice in various activities. Thus, must be a matter of great weight, directions for attendance and registration for radiological emergencies or nuclear accidents. This work shows the planning elaborated by the Comissao Nacional de Energia Nuclear (Brazilian CNEN) for nuclear plants, aiming avoid the injurious effects from the ionizing radiation exposure, radionuclides release or the direct or indirect exposure of ionizing radiation, that proceeding from a radiological emergencies or a nuclear accidents. (J.A.M.M.)

Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

In co-operation with the OECD Nuclear Energy Agency (NEA), the Halden Reactor Project organised a Summer School on ''Safe Operation of Nuclear Power Plants: Impacts of Human and Organisational Factors and Emerging Technologies'' in the period August 27-August 31, 2001. The Summer School was intended for scientists, engineers and technicians working for nuclear installations, engineering companies, industry and members of universities and research institutes, who wanted to broaden their nuclear background by getting acquainted with Man-Technology-Organisation-related subjects and issues. The Summer School should also serve to transfer knowledge to the ''young generation'' in the nuclear field. The following presentations were given: (1) Overview of the Nuclear Community and Current issues, (2) The Elements of Safety Culture; Evaluation of Events, (3) Quality Management (QM), (4) Probabilistic Risk Assessment (PSA), (5) Human Behaviour from the Viewpoint of Industrial Psychology, (6) Technical tour of the Halden Project Experimental Facilities, (7) Human Factors in Control Room Design, (8) Computerised Operator Support Systems (COSSs) and (9) Artificial Intelligence; a new Approach. Most of the contributions are overhead figures from spoken lectures.

Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

International Nuclear Information System (INIS)

Bhatnagar, P.K.

2009-01-01

Management of Nuclear and Radiological Emergencies arising from Radiological Dispersive Device (RDD), Improvised Nuclear Devices (IND), Nuclear Reactors/Power plants and Nuclear War require measurement of ionizing radiations and radioactivity on an enhanced scale relative to the levels encountered in peaceful uses of ionizing radiations and radioactivity. It is heartening that since Hiroshima, Nagasaki nuclear disaster, the world has been quiet but since early 2000 there has been a fear of certain devices to be used by terrorists, which could lead to panic, and disaster due to dispersal of radioactivity by RDD, IND. Nuclear attack would lead to blast, thermal, initial nuclear radiation, nuclear fall out leading to gamma and neutron dose, dose rates in range from few R, R/h to kR, kR/h, and determinations of k Bq or higher order. Such situations have been visualized at national levels and National Disaster Management Authority NDMA has been established and Disaster Management Act 2005 has come into existence. NDMA has prepared guidelines for Nuclear and radiological emergency management highlighting preparedness, mitigation, response, capacity building, etc. Critical point in all these issues is detection of emergency, quick intimation to the concerned for action in shortest possible time. Upper most requirement by those involved in pursuing action, is radiation sensor based radiation monitors for personnel, area, and to assess contamination due to radioactivity.This presentation briefly describes the Indian scenario in the development of the radiation sensors and the sensor-based radiation monitors. (author)

Nuclear radiation sensors and monitoring following a nuclear or radiological emergencies

Energy Technology Data Exchange (ETDEWEB)

Bhatnagar, P K [Defence Laboratory, Jodhpur (India)

2009-01-15

Management of Nuclear and Radiological Emergencies arising from Radiological Dispersive Device (RDD), Improvised Nuclear Devices (IND), Nuclear Reactors/Power plants and Nuclear War require measurement of ionizing radiations and radioactivity on an enhanced scale relative to the levels encountered in peaceful uses of ionizing radiations and radioactivity. It is heartening that since Hiroshima, Nagasaki nuclear disaster, the world has been quiet but since early 2000 there has been a fear of certain devices to be used by terrorists, which could lead to panic, and disaster due to dispersal of radioactivity by RDD, IND. Nuclear attack would lead to blast, thermal, initial nuclear radiation, nuclear fall out leading to gamma and neutron dose, dose rates in range from few R, R/h to kR, kR/h, and determinations of k Bq or higher order. Such situations have been visualized at national levels and National Disaster Management Authority NDMA has been established and Disaster Management Act 2005 has come into existence. NDMA has prepared guidelines for Nuclear and radiological emergency management highlighting preparedness, mitigation, response, capacity building, etc. Critical point in all these issues is detection of emergency, quick intimation to the concerned for action in shortest possible time. Upper most requirement by those involved in pursuing action, is radiation sensor based radiation monitors for personnel, area, and to assess contamination due to radioactivity.This presentation briefly describes the Indian scenario in the development of the radiation sensors and the sensor-based radiation monitors. (author)

Diethylene-triamine-penta-acetate administration protocol for radiological emergency medicine in nuclear fuel reprocessing plants.

Science.gov (United States)

Jin, Yutaka

2008-01-01

Inhalation therapy of diethylene-triamine-penta-acetate (DTPA) should be initiated immediately to workers who have significant incorporation of plutonium, americium or curium in the nuclear fuel reprocessing plant. A newly designed electric mesh nebulizer is a small battery-operated passive vibrating mesh device, in which vibrations in an ultrasonic horn are used to force drug solution through a mesh of micron-sized holes. This nebulizer enables DTPA administration at an early stage in the event of a radiation emergency from contamination from the above radioactive metals.

Radiation protection during operation of nuclear power plants

International Nuclear Information System (INIS)

1983-01-01

This Guide describes a Radiation Protection Programme for nuclear power plants. It includes: (1) An outline of the basic principles as well as practical aspects of the programme; (2) A description of the responsibilities of the operating organization to establish an effective programme based upon these principles; (3) A description of the administrative and technical measures to establish and implement the programme. This Guide also deals with the operational aspects to be considered by the operating organization in reviewing design in order to facilitate implementation of the Radiation Protection Programme. This Guide covers the requirements for a Radiation Protection Programme for all operational states of the nuclear power plant. It also includes guidelines for handling planned special exposures and for coping with unplanned exposures and contamination of personnel, areas, and equipment. Additional information concerning emergency situations involving releases of radioactive materials is given in Safety Guides 50-SG-O6, ''Preparedness of the Operating Organization (Licensee) for Emergencies at Nuclear Power Plants'', and 50-SG-G6, ''Preparedness of Public Authorities for Emergencies at Nuclear Power Plants''. This Guide covers the principles of dose limitation to site personnel and to the public, but it does not include detailed instructions on the techniques used for the actual measurement and evaluation of the exposures. This Guide does not include detailed instructions on environmental surveys, but it does mention principal steps in environmental monitoring which may be required for confirmation of the acceptability of radioactive discharges

Nuclear power plant's safety and risk (requirements of safety and reliability)

International Nuclear Information System (INIS)

Franzen, L.F.

1977-01-01

Starting out from the given safety objectives as they have evolved during the past few years and from the present legal and regulatory provisions for the construction and operation of nuclear power plants, the hazards involved in regular operation, accidents and emergency situations are discussed. In compliance with the positive safety balance of nuclear power plants in the FRG, special attention is focused on the preventive safety analysis within the frame of the nuclear licensing procedure. Reference is made to the beginnings of a comprehensive hazard concept for an unbiased plant assessment. Emergency situations are discussed from the point of view of general hazard comparisons. (orig.) [de

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1992-03-01

The Finnish nuclear power plant units Loviisa 1 and 2 as well as TVO I and II were in operation for almost the whole third quarter of 1991. Longer interruptions in electricity generation were caused by the annual maintenances of the Loviisa plant units. The load factor average was 81.7 %. In a test conducted during the annual maintenance outage of Loviisa 1 it was detected that the check valve of the discharge line of one pressurized emergency make-up tank did not open sufficiently at the tank's hydrostatic pressure. In connection with a 1988 modification, a too tightly dimensioned bearing had been mounted on the valve's axle rod and the valve had not been duly tested after the operation. The event is classified as Level 1 on the International Nuclear Event Scale. Other events in this quarter which are classified according to the International Nuclear Event Scale are Level Zero (Below Scale). Occupational radiation doses and releases of radioactive material off-site were below authorised limits in this quarter. Only small amounts of radioactive materials originating in nuclear power plants were detected in samples taken in the vicinity of nuclear power plants

Nuclear emergency planning and response in the Netherlands after Chernobyl

International Nuclear Information System (INIS)

Bergman, L.J.W.M.; Kerkhoven, I.P.

1989-01-01

After Chernobyl an extensive project on nuclear emergency planning and response was started in the Netherlands. The objective of this project was to develop a (governmental) structure to cope with accidents with radioactive materials, that can threaten the Dutch community and neighbouring countries. The project has resulted in a new organizational structure for nuclear emergency response, that differs on major points from the existing plans and procedures. In this paper an outline of the new structure is given. Emphasis is placed on accidents with nuclear power plants

Distributed Control Systems in New Nuclear Power Plants

International Nuclear Information System (INIS)

Doerfler, Joseph

2008-01-01

With the growing demand for energy many countries have expressed interest in constructing new plants over the next 15 to 20 years. These expectations have presented a challenge to the nuclear industry to provide a high volume of construction. A key strategy to meet this challenge is developing an advanced nuclear power plant design that allows for a modular construction, a high level of standardization, passive safety features, reduced number of components, and a short bid-to-build time. In addition, the implementation of the plant control system has evolved as new technologies emerge to support these goals. The purpose of this paper is to discuss the ways that the distributed control and information systems in the new generation of nuclear power plants will differ from those currently in service. The new designs provide opportunities to improve overall performance through the use of bus technology, a video display driven Human System Interface, enhanced diagnostics and improved maintenance features. However, the new technologies must fully address requirements for cyber security and high reliability. This paper will give an overview of new technology, improvements, as well as emerging issues in new plant design. (authors)

Distributed Control Systems in New Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Doerfler, Joseph [Westinghouse Electric Company, 4350 Northern Pike, Monroeville, PA 15146 (United States)

2008-07-01

With the growing demand for energy many countries have expressed interest in constructing new plants over the next 15 to 20 years. These expectations have presented a challenge to the nuclear industry to provide a high volume of construction. A key strategy to meet this challenge is developing an advanced nuclear power plant design that allows for a modular construction, a high level of standardization, passive safety features, reduced number of components, and a short bid-to-build time. In addition, the implementation of the plant control system has evolved as new technologies emerge to support these goals. The purpose of this paper is to discuss the ways that the distributed control and information systems in the new generation of nuclear power plants will differ from those currently in service. The new designs provide opportunities to improve overall performance through the use of bus technology, a video display driven Human System Interface, enhanced diagnostics and improved maintenance features. However, the new technologies must fully address requirements for cyber security and high reliability. This paper will give an overview of new technology, improvements, as well as emerging issues in new plant design. (authors)

Emerging nuclear suppliers

International Nuclear Information System (INIS)

Sands, A.

1990-01-01

Efforts to prevent the spread of nuclear weapons have usually taken two tracks: The traditional approach has concentrated on a potential proliferant's perceived need for nuclear technology and possibly weapons; a second approach has targeted the supply side of the proliferation equation. The issue being examined in this book---emerging nuclear suppliers---falls between these two approaches. The potential proliferants have emerged as possible unrestrained suppliers of nuclear materials and technology. They threaten the entire nonproliferation regime by their exporting, not their weapons development. Analyzing and understanding the issue of emerging suppliers requires a refined definition of suppliers in general. The simple dichotomy of traditional versus emerging suppliers is no longer an adequate framework for analysis. Suppliers differ significantly in their technical capabilities, experience, and regime involvement, and these distinctions result in different nuclear export policies

Counter Action Procedure Generation in an Emergency Situation of Nuclear Power Plants

Science.gov (United States)

Gofuku, A.

2018-02-01

Lessons learned from the Fukushima Daiichi accident revealed various weak points in the design and operation of nuclear power plants at the time although there were many resilient activities made by the plant staff under difficult work environment. In order to reinforce the measures to make nuclear power plants more resilient, improvement of hardware and improvement of education and training of nuclear personnel are considered. In addition, considering the advancement of computer technology and artificial intelligence, it is a promising way to develop software tools to support the activities of plant staff.This paper focuses on the software tools to support the operations by human operators and introduces a concept of an intelligent operator support system that is called as co-operator. This paper also describes a counter operation generation technique the authors are studying as a core component of the co-operator.

[Risk communication in construction of new nuclear power plant].

Science.gov (United States)

He, Gui-Zhen; Lü, Yong-Long

2013-03-01

Accompanied by construction of new nuclear power plants in the coming decades in China, risk management has become increasingly politicized and contentious. Nuclear risk communication is a critical component in helping individuals prepare for, respond to, and recover from nuclear power emergencies. It was discussed that awareness of trust and public attitudes are important determinants in nuclear power risk communication and management. However, there is limited knowledge about how to best communicate with at-risk populations around nuclear power plant in China. To bridge this gap, this study presented the attitudinal data from a field survey in under-building Haiyang nuclear power plant, Shandong Province to measure public support for and opposition to the local construction of nuclear power plant. The paper discussed the structure of the communication process from a descriptive point of view, recognizing the importance of trust and understanding the information openness. The results showed that decision-making on nuclear power was dominated by a closed "iron nuclear triangle" of national governmental agencies, state-owned nuclear enterprises and scientific experts. Public participation and public access to information on nuclear constructions and assessments have been marginal and media was a key information source. As information on nuclear power and related risks is very restricted in China, Chinese citizens (51%) tend to choose the government as the most trustworthy source. More respondents took the negative attitudes toward nuclear power plant construction around home. It drew on studies about risk communication to develop some guidelines for successful risk communication. The conclusions have vast implications for how we approach risk management in the future. The findings should be of interest to state and local emergency managers, community-based organizations, public health researchers, and policy makers.

Nuclear emergency planning in Spain. The PLABEN review project

International Nuclear Information System (INIS)

Lentijo Lentijo, J. C.; Vila Pena, M.

2002-01-01

The international rules and recommendations for nuclear emergency planning and the Spanish experience gained in the management of event with radiological risk have noticed that is necessary to review the planning radiological bases for emergencies in nuclear power plants and to define the planning radiological bases for radiological emergencies that could happen in radioactive facilities or in activities out of the regulatory framework. The paper focuses on CSN actions concerning the Plaben review project related to define the new radiological principles taking into account the current international recommendations for interventions, make a proposal about the organisation and operation of the provincial radiological action group and the national support level for radiological emergency response. (Author) 7 refs

Recognition of Instrumentation Gauge in the Nuclear Power Plant

Energy Technology Data Exchange (ETDEWEB)

Cho, Jai Wan; Jeong, Kyung Min [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Nuclear emergency robots were developed in 2001 as the countermeasure following the criticality accident at the JCO (uranium refinery facility) in Tokaimura, Japan in 1999. We assumed that these nuclear emergency robots were deployed (or put into) for a mitigation (or management) of severe accident, for example, occurred at Fukushima Daiichi nuclear power plant. In the case, the image understanding using a color CCD camera, loaded on the nuclear emergency robot, is important. We proposed an image processing technique to read indication value of the IC water level gauges using the structural characteristics of the instrumentation panels (water level gauges) located inside the reactor building. At first, we recognized the scales on the instrumentation panel using the geometric shape of the panel. And then, we could read the values of the instrumentation gauge by calculating the slope of the needle on the gauge. Using the proposed algorithm, we deciphered instrumentation panels for the four water level gauges and indicators shown on the IC video released by TEPCO and Japanese Nuclear Regulatory Commission of Japan. In this paper, recognition of the instrumentation gauges inside reactor building of the nuclear power plant by an image processing technology is described.

Monitoring support system for nuclear power plant

International Nuclear Information System (INIS)

Higashikawa, Yuichi; Kubota, Rhuji; Tanaka, Keiji; Takano, Yoshiyuki

1996-01-01

The nuclear power plants in Japan reach to 49 plants and supply 41.19 million kW in their installed capacities, which is equal to about 31% of total electric power generation and has occupied an important situation as a stable energy supplying source. As an aim to keeping safe operation and working rate of the power plants, various monitoring support systems using computer technology, optical information technology and robot technology each advanced rapidly in recent year have been developed to apply to the actual plants for a plant state monitoring system of operators in normal operation. Furthermore, introduction of the emergent support system supposed on accidental formation of abnormal state of the power plants is also investigated. In this paper, as a monitoring system in the recent nuclear power plants, design of control panel of recent central control room, introduction to its actual plant and monitoring support system in development were described in viewpoints of improvement of human interface, upgrade of sensor and signal processing techniques, and promotion of information service technique. And, trend of research and development of portable miniature detector and emergent monitoring support system are also introduced in a viewpoint of labor saving and upgrade of the operating field. (G.K.)

NARAC Modeling During the Response to the Fukushima Dai-ichi Nuclear Power Plant Emergency

Energy Technology Data Exchange (ETDEWEB)

Sugiyama, G; Nasstrom, J S; Probanz, B; Foster, K T; Simpson, M; Vogt, P; Aluzzi, F; Dillon, M; Homann, S

2012-02-14

This paper summarizes the activities of the National Atmospheric Release Advisory Center (NARAC) during the Fukushima Dai-ichi nuclear power plant crisis. NARAC provided a wide range of products and analyses as part of its support including: (1) Daily Japanese weather forecasts and hypothetical release (generic source term) dispersion predictions to provide situational awareness and inform planning for U.S. measurement data collection and field operations; (2) Estimates of potential dose in Japan for hypothetical scenarios developed by the Nuclear Regulatory Commission (NRC) to inform federal government considerations of possible actions that might be needed to protect U.S. citizens in Japan; (3) Estimates of possible plume arrival times and dose for U.S. locations; and (4) Plume model refinement and source estimation based on meteorological analyses and available field data. The Department of Energy/National Nuclear Security Administration (DOE/NNSA) deployed personnel to Japan and stood up 'home team' assets across the DOE complex to aid in assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. The DOE Nuclear Incident Team (NIT) coordinated response activities, while DOE personnel provided predictive modeling, air and ground monitoring, sample collection, laboratory analysis, and data assessment and interpretation. DOE deployed the Aerial Measuring System (AMS), Radiological Assistance Program (RAP) personnel, and the Consequence Management Response Team (CMRT) to Japan. DOE/NNSA home team assets included the Consequence Management Home Team (CMHT); National Atmospheric Release Advisory Center (NARAC); Radiation Emergency Assistance Center/Training Site (REAC/TS); and Radiological Triage. NARAC was activated by the DOE/NNSA on March 11, shortly after the Tohoku earthquake and tsunami occurred. The center remained on active operations through late May when DOE ended its deployment to Japan. Over 32 NARAC staff

NARAC Modeling During the Response to the Fukushima Dai-ichi Nuclear Power Plant Emergency

International Nuclear Information System (INIS)

Sugiyama, G.; Nasstrom, J.S.; Probanz, B.; Foster, K.T.; Simpson, M.; Vogt, P.; Aluzzi, F.; Dillon, M.; Homann, S.

2012-01-01

This paper summarizes the activities of the National Atmospheric Release Advisory Center (NARAC) during the Fukushima Dai-ichi nuclear power plant crisis. NARAC provided a wide range of products and analyses as part of its support including: (1) Daily Japanese weather forecasts and hypothetical release (generic source term) dispersion predictions to provide situational awareness and inform planning for U.S. measurement data collection and field operations; (2) Estimates of potential dose in Japan for hypothetical scenarios developed by the Nuclear Regulatory Commission (NRC) to inform federal government considerations of possible actions that might be needed to protect U.S. citizens in Japan; (3) Estimates of possible plume arrival times and dose for U.S. locations; and (4) Plume model refinement and source estimation based on meteorological analyses and available field data. The Department of Energy/National Nuclear Security Administration (DOE/NNSA) deployed personnel to Japan and stood up 'home team' assets across the DOE complex to aid in assessing the consequences of the releases from the Fukushima Dai-ichi Nuclear Power Plant. The DOE Nuclear Incident Team (NIT) coordinated response activities, while DOE personnel provided predictive modeling, air and ground monitoring, sample collection, laboratory analysis, and data assessment and interpretation. DOE deployed the Aerial Measuring System (AMS), Radiological Assistance Program (RAP) personnel, and the Consequence Management Response Team (CMRT) to Japan. DOE/NNSA home team assets included the Consequence Management Home Team (CMHT); National Atmospheric Release Advisory Center (NARAC); Radiation Emergency Assistance Center/Training Site (REAC/TS); and Radiological Triage. NARAC was activated by the DOE/NNSA on March 11, shortly after the Tohoku earthquake and tsunami occurred. The center remained on active operations through late May when DOE ended its deployment to Japan. Over 32 NARAC staff members

Soil sampling and analytical strategies for mapping fallout in nuclear emergencies based on the Fukushima Dai-ichi Nuclear Power Plant accident

International Nuclear Information System (INIS)

Onda, Yuichi; Kato, Hiroaki; Hoshi, Masaharu; Takahashi, Yoshio; Nguyen, Minh-Long

2015-01-01

The Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident resulted in extensive radioactive contamination of the environment via deposited radionuclides such as radiocesium and 131 I. Evaluating the extent and level of environmental contamination is critical to protecting citizens in affected areas and to planning decontamination efforts. However, a standardized soil sampling protocol is needed in such emergencies to facilitate the collection of large, tractable samples for measuring gamma-emitting radionuclides. In this study, we developed an emergency soil sampling protocol based on preliminary sampling from the FDNPP accident-affected area. We also present the results of a preliminary experiment aimed to evaluate the influence of various procedures (e.g., mixing, number of samples) on measured radioactivity. Results show that sample mixing strongly affects measured radioactivity in soil samples. Furthermore, for homogenization, shaking the plastic sample container at least 150 times or disaggregating soil by hand-rolling in a disposable plastic bag is required. Finally, we determined that five soil samples within a 3 m × 3-m area are the minimum number required for reducing measurement uncertainty in the emergency soil sampling protocol proposed here. - Highlights: • Emergency soil sampling protocol was proposed for nuclear hazards. • Various sampling procedures were tested and evaluated in Fukushima area. • Soil sample mixing procedure was of key importance for measured radioactivity. • Minimum number of sampling was determined for reducing measurement uncertainty

A study on expert system applications for nuclear power plant

International Nuclear Information System (INIS)

Huh, Young Hwan; Kim, Yeong Jin; Park, Nam Seog; Dong, In Sook; Choi, In Seon

1987-12-01

The application of artificial intelligence techniques to nuclear power plants such as expert systems is rapidly emerging. expert systems can contribute significantly to the availability and the improved operation and safety of nuclear power plants. The objective of the project is to develop an expert system in a selected application area in the nuclear power plants. This project will last for 3 years. The first year's tasks are: - Information collection and literature survey on expert systems. - Analysis of several applicable areas for applying AI technologies to the nuclear power plants. - Conceptual design of a few selected domains. - Selection of hardware and software tools for the development of the expert system

Guidance for emergency planning in nuclear power plants; Vaegledning foer insatsplanering i kaerntekniska anlaeggningar

Energy Technology Data Exchange (ETDEWEB)

Magnusson, Tommy; Ekdahl, Maria (Ringhals AB, Vaeroebacka (Sweden))

2008-06-15

Ringhals has been a model for this study, but the purpose has been to make the report applicable at all nuclear power plants in Sweden. The work has been done in close co-operation with the Swedish nuclear power plants and Rescue Services in the nuclear power municipalities Oesthammar, Oskarshamn, and Varberg. The internal fire brigade at the nuclear power plants has also been involved. A document will also be published as a further guidance at efforts of the type fires, which are mentioned in the enclosed document. After a fire in a switchgear room in 2005 the need of making the existing effort planning more effective at nuclear power plants was observed. The idea with the planning is to plan the effort in order to give the operational and emergency staff a good and actual support to come to a decision and to start the mission without delay. The risk information is showed by planning layouts, symbols and drawings as basis, give risk information and effort information. The effort information shows outer arrangements, manual action points, fire installations, passive fire safety etc. The risk information is shown by risk symbols. Their purpose is to give a fast overview of the existing risks. Reactor safety effects is the ruling influence if an effort has to be done in order to secure safety for a third person. In order to make an effort in an area personal risks for rescue staff, such as electricity risks, radiological risks, chemicals and gas bottles with compressed gases, has to be eliminated. For complicated missions detailed instructions are needed in order to handle specific risks. In a group discussion different people with pertinent knowledge has to value which problematic efforts need detailed instruction. Missions that have to be analyzed in a work group as above are: fire may affect the reactor safety, fire that may threaten the structural integrity, chemical discharge with big consequence on environment/third person and handling of gas system (compressed

Reconstruction of the Radiation Emergency Medical System From the Acute to the Sub-acute Phases After the Fukushima Nuclear Power Plant Crisis.

Science.gov (United States)

Ojino, Mayo; Ishii, Masami

2014-02-01

The radiation emergency medical system in Japan ceased to function as a result of the accident at the Fukushima Daiichi Nuclear Power Plant, which has commonly become known as the "Fukushima Accident." In this paper, we review the reconstruction processes of the radiation emergency medical system in order of events and examine the ongoing challenges to overcoming deficiencies and reinforcing the system by reviewing relevant literature, including the official documents of the investigation committees of the National Diet of Japan, the Japanese government, and the Tokyo Electric Power Company, as well as technical papers written by the doctors involved in radiation emergency medical activities in Fukushima. Our review has revealed that the reconstruction was achieved in 6 stages from March 11 to July 1, 2011: (1) Re-establishment of an off-site center (March 13), (2) Re-establishment of a secondary radiation emergency hospital (March 14), (3) Reconstruction of the initial response system for radiation emergency care (April 2), (4) Reinforcement of the off-site center and stationing of disaster medical advisors at the off-site center (April 4), (5) Reinforcement of the medical care system and an increase in the number of hospitals for non-contaminated patients (From April 2 to June 23), and (6) Enhancement of the medical care system in the Fukushima Nuclear Power Plant and the construction of a new medical care system, involving both industrial medicine and emergency medicine (July 1). Medical resources such as voluntary efforts, academic societies, a local community medical system and university hospitals involved in medical care activities on 6 stages originally had not planned. In the future, radiation emergency medical systems should be evaluated with these 6 stages as a basis, in order to reinforce and enrich both the existing and backup systems so that minimal harm will come to nuclear power plant workers or evacuees and that they will receive proper care. This

WSPEEDI-II system user's manual for a nuclear or radiological emergency

International Nuclear Information System (INIS)

Nakanishi, Chika; Sato, Sohei; Muto, Shigeo; Furuno, Akiko; Terada, Hiroaki; Nagai, Haruyasu

2011-03-01

Nuclear Emergency Assistance and Training Center (NEAT) has developed the response system to evaluate the radiological consequences of an accident on a nuclear power plant or nuclear weapons testing around Japan and to support prediction of radioactive material distributions by using an atmospheric dispersion model on the framework of the Response Assistance Network (RANET) which is established by the International Atomic Energy Agency (IAEA). For the enhancement of assistance capability to external organizations at a nuclear or radiological emergency, NEAT will introduce a computer-based emergency response system, 'Worldwide version of System for Prediction of Environmental Emergency Dose Information: WSPEEDI 2nd version (WSPEEDI-II)' developed by Division of Environmental and Radiation Sciences. This manual covers the overview of the system and configuration parameters as the basic knowledge needed for operating the systems. (author)

The development of emergency core cooling systems in the PWR, BWR, and HWR Candu type of nuclear power plants

International Nuclear Information System (INIS)

Mursid Djokolelono.

1976-01-01

Emergency core cooling systems in the PWR, BWR, and HWR-Candu type of nuclear power plant are reviewed. In PWR and BWR the emergency cooling can be catagorized as active high pressure, active low pressure, and a passive one. The PWR uses components of the shutdown cooling system: whereas the BWR uses components of pressure suppression contaiment. HWR Candu also uses the shutdown cooling system similar to the PWR except some details coming out from moderator coolant separation and expensive cost of heavy water. (author)

'Present nuclear emergency responses in India: tracing requirements and guidelines suggested after Fukushima accident in regards to public and plant safety

International Nuclear Information System (INIS)

Jawale, Priyanka M.

2014-01-01

In this poster the primary initiative is to educate the public at large and instill confidence about the present Emergency Response Systems of DAE and the imminent agencies in India. Poster attempts to analyse present regulatory and safety systems, mechanisms like plant and site emergency response plans are in place to handle radiation emergencies and how public will not be affected in any manner. In India also we needed some supplementary provisions to cope up with major disasters in Nuclear Power Plants (NPP) apart from the existing one. Some of the NPPs are not under the UN safeguards, which can not import Uranium also need extra care and protection. Regulatory and safety functions of Atomic Energy in India are carried out by the Atomic Energy Regulatory Board (Atomic Energy Regulatory Board), the poster attempts to explain the present regulatory and safety mechanism under Atomic Energy Regulatory Board. We have the plant and site emergency response plans in place. The well planned functioning of these is demonstrated here. India is equipped with detail plans of emergency response system, to handle the radiation emergencies in public domain even at the locations where DAE facility is not available

Safety design of Qinshan Nuclear Power Plant

International Nuclear Information System (INIS)

Ouyang Yu; Zhang Lian; Du Shenghua; Zhao Jiayu

1984-01-01

Safety issues have been greatly emphasized through the design of the Qinshan Nuclear Power Plant. Reasonable safety margine has been taken into account in the plant design parameters, the design incorporated various safeguard systems, such as engineering safety feature systems, safety protection systems and the features to resist natural catastrophes, e. g. earthquake, hurricanes, tide and so on. Preliminary safety analysis and environmental effect assessment have been done and anti-accident provisions and emergency policy were carefully considered. Qinshan Nuclear Power Plant safety related systems are designed in accordance with the common international standards established in the late 70's, as well as the existing engineering standard of China

Operation of Finnish nuclear power plants

International Nuclear Information System (INIS)

Tossavainen, K.

1990-08-01

During the first quarter of 1990 the Finnish nuclear power plant units Loviisa 1 and 2 and TVO I and II were in commercial operation for most of the time. Nuclear electricity accounted for 32.5% of the total Finnish electricity production during this quarter. The load factor average of the nuclear power plant units was 99.0%. An international nuclear event scale has been introduced for the classification of nuclear power plant events according to their nuclear and radiation safety significance. The scale first undergoes about a year long trial period in several countries. on the scale, events are divided into levels from 1 to 7 of which events at Level 7 are the most serious. Furthermore, Level 0 (Below Scale) is used for events with no safety significance. All events which occurred at the Finnish nuclear power plants this quarter are classified as Level 0. Occupational radiation doses and external releases of radioactivity were considerably below authorised limits. At the Loviisa plant, a back-up emergency feedwater system independent of the plant's other systems has been introduced which offers a new, alternative means of removing residual heat from the reactor. Owing to this system, the risk of a severe accident has been further reduced. At the TVO plants, systems have been introduced by which accident sequences which lead to containment failure could be eliminated and the consequences of a potential severe accident could be mitigated. In this report, also the release of short-lived radioactive materials along the transfer route of an irradiated sample is described which occured at the FiR 1 research reactor. The amounts of radioactive materials individuals received in their bodies in connection with this event were very low

NRC nuclear-plant-analyzer concept and status at INEL

International Nuclear Information System (INIS)

Aguilar, F.; Wagner, R.J.

1982-01-01

The Office of Research of the US NRC has proposed development of a software-hardware system called the Nuclear Plant Analyzer (NPA). This paper describes how we of the INEL envision the nuclear-plant analyzer. The paper also describes a pilot RELAP5 plant-analyzer project completed during the past year and current work. A great deal of analysis is underway to determine nuclear-steam-system response. System transient analysis being so complex, there is the need to present analytical results in a way that interconnections among phenomena and all the nuances of the transient are apparent. There is the need for the analyst to dynamically control system calculations to simulate plant operation in order to perform what if studies as well as the need to perform system analysis within hours of a plant emergency to diagnose the state of the stricken plant and formulate recovery actions. The NRC-proposed nuclear-plant analyzer can meet these needs

Study on Korean Radiological Emergency System-Care System- and National Nuclear Emergency Preparedness System Development

International Nuclear Information System (INIS)

Akhmad Khusyairi; Yudi Pramono

2008-01-01

Care system; Radiological Emergency Supporting System. Environmental radiology level is the main aspect that should be concerned deal with the utilization of nuclear energy. The usage of informational technology in nuclear area gives significant contribution to anticipate and to protect human and environment. Since 1960, South Korea has developed environment monitoring system as the effort to protect the human and environment in the radiological emergency condition. Indonesia has possessed several nuclear installations and planned to build and operate nuclear power plants (PLTN) in the future. Therefore, Indonesia has to prepare the integrated system, technically enables to overcome the radiological emergency. Learning from the practice in South Korea, the system on the radiological emergency should be prepared and applied in Indonesia. However, the government regulation draft on National Radiological Emergency System, under construction, only touches the management aspect, not the technical matters. Consequently, when the regulation is implemented, it will need an additional regulation on technical aspect including the consideration on the system (TSS), the organization of operator and the preparation of human resources development of involved institution. For that purpose, BAPETEN should have a typical independence system in regulatory frame work. (author)

Emergency preparedness for nuclear electric generating facilities in foreign countries: A brief survey of practices

Energy Technology Data Exchange (ETDEWEB)

Schuller, C R [Battelle Human Affairs Research Centers, Seattle, WA (United States); Marcus, A A; Hanhardt, Jr, A M; Selvin, M; Huelshoff, M [Pacific Northwest Laboratory, Richland, WA (United States)

1980-12-01

This report summarizes the emergency plans for accidents at nuclear power plants in Germany, Sweden, Switzerland, the United Kingdom, Canada, and France. Soviet Union documents were examined, but no published information was found on the subject. The study of foreign plans was to determine what U.S. planners might learn that could be useful to them. Plans of the foreign countries were published before the nuclear accident at Three Mile Island and reflected a generally accepted premise that a serious nuclear emergency would never occur. Therefore, there are few ideas of immediate use to U.S. planners. Most countries have since begun to re-examine their emergency planning. The study also discusses the emergency action levels, warning systems, evacuation management and procedures, and public information and education for people living near nuclear power plants and defines roles of nuclear facility operators and roles of the government. (author)

A new design concept for offshore nuclear power plants with enhanced safety features

International Nuclear Information System (INIS)

Lee, Kihwan; Lee, Kang-Heon; Lee, Jeong Ik; Jeong, Yong Hoon; Lee, Phill-Seung

2013-01-01

Highlights: ► A new design concept for offshore nuclear power plants is proposed. ► The total general arrangement for the concept is suggested. ► A new emergency passive containment cooling system (EPCCS) is proposed. ► A new emergency passive reactor-vessel cooling system (EPRVCS) is proposed. ► Safety features against earthquakes, tsunamis, and storms are discussed. - Abstract: In this paper, we present a new concept for offshore nuclear power plants (ONPP) with enhanced safety features. The design concept of a nuclear power plant (NPP) mounted on gravity-based structures (GBSs), which are widely used offshore structures, is proposed first. To demonstrate the feasibility of the concept, a large-scale land-based nuclear power plant model APR1400, which is the most recent NPP model in the Republic of Korea, is mounted on a GBS while minimizing modification to the original features of APR1400. A new total general arrangement (GA) and basic design principles are proposed and can be directly applied to any existing land based large scale NPPs. The proposed concept will enhance the safety of a NPP due to several aspects. A new emergency passive containment cooling system (EPCCS) and emergency passive reactor-vessel cooling system (EPRVCS) are proposed; their features of using seawater as coolant and safety features against earthquakes, Tsunamis, storms, and marine collisions are also described. We believe that the proposed offshore nuclear power plant is more robust than conventional land-based nuclear power plants and it has strong potential to provide great opportunities in nuclear power industries by decoupling the site of construction and that of installation.

Implementation of a radiological emergency monitoring system for Bruce Power nuclear power plant (Canada); Implementierung eines radiologischen Umgebungsueberwachungsmesssystems fuer das Kernkraftwerk Bruce Power (Kanada)

Energy Technology Data Exchange (ETDEWEB)

Madaric, M. [Saphymo GmbH, Frankfurt (Germany)

2016-07-01

The Bruce Power nuclear power plant (BP NPP) in Ontario, Canada, is the largest nuclear generating station in the world, operating 8 nuclear reactors producing 6300 MW. In correlation with Bruce Power's safety culture, ''Safety first'' and continuous improvements are essential and substantial parts of the Bruce Power philosophy and management system. After the Fukushima nuclear accident the existing radiological emergency monitoring was analyzed and improved.

Preparedness of Operation Teams' Non-technical Skills in a Main Control Room of Nuclear Power Plants to Manage Emergency Situations

International Nuclear Information System (INIS)

Yim, Ho Bin; Kim, Ar Ryum; Seong, Poong Hyun

2012-01-01

Human reliability is one of the important determinants for the system safety. Nuclear Energy Agency reported that approximately half of events reported by foreign nuclear industry were related with inappropriate human actions. The human error problems can be viewed in two ways: the person approach and the system approach. Other terms to represent each approach are active failures and latent conditions. Active failures are unsafe acts committed by people who are in direct contact with systems whereas latent conditions are the inevitable 'resident pathogens' within the system. To identify what kinds of non-technical skills were needed to cope with emergency conditions, a method to evaluate preparedness of task management in emergency conditions based on monitoring patterns was presented. Five characteristics were suggested to evaluate emergency task management and communication: latent mistake resistibility, latent violation resistibility, thoroughness, communication, and assertiveness. Case study was done by analyzing emergency training of 9 different real operation teams in the reference plant. The result showed that the 9 teams had their own emergency task management skills which resulted in good and bad performances

Nuclear plants gain integrated information systems

International Nuclear Information System (INIS)

Villavicencio-Ramirez, A.; Rodriquez-Alvarez, J.M.

1994-01-01

With the objective of simplifying the complex mesh of computing devices employed within nuclear power plants, modern technology and integration techniques are being used to form centralized (but backed up) databases and distributed processing and display networks. Benefits are immediate as a result of the integration and the use of standards. The use of a unique data acquisition and database subsystem optimizes the high costs of engineering, as this task is done only once for the life span of the system. This also contributes towards a uniform user interface and allows for graceful expansion and maintenance. This article features an integrated information system, Sistema Integral de Informacion de Proceso (SIIP). The development of this system enabled the Laguna Verde Nuclear Power plant to fully use the already existing universe of signals and its related engineering during all plant conditions, namely, start up, normal operation, transient analysis, and emergency operation. Integrated systems offer many advantages over segregated systems, and this experience should benefit similar development efforts in other electric power utilities, not only for nuclear but also for other types of generating plants

Picket engineer concept in Swiss nuclear power plants

International Nuclear Information System (INIS)

Steffen, W.

1982-01-01

Switzerland has four plants already in operation, three of the 300 MW Class and one of 1000 MW, with a further 1000 MW plant under construction. Nuclear energy is of vital importance to the country, in 1980 it accounted for almost 30% of the year's total electricity production. Great economic and political importance is attached to the safety and availability of the nuclear power plants. For safety reasons neither the plant owners nor the Authority were willing to dispense with having a qualified engineer in permanent attendance at the plant, particularly during incidents, accidents or emergencies. For this reason the concept of picket engineer was introduced in 1972, through the initiative of the plant owners and with the approval of the Authority

Involvement of the Public Health Authority in emergency planning and preparedness for nuclear facilities in Hungary

International Nuclear Information System (INIS)

Sztanyik, L.B.

1986-01-01

It is required by the Hungarian Atomic Energy Act and its enacting clause of 1980 that facilities established for the application of atomic energy be designed, constructed and operated in such a manner that abnormal operational occurrences can be avoided and unplanned exposures to radiation and radioactive substances can be prevented. The primary responsibility for planning and implementing emergency actions rests with the management of the operating organization. Thus one of the prerequisites of licensing the first nuclear power plant in Hungary was the preparation and submission for approval of an emergency plan by the operating organization. In addition to this, the council of the county where the power plant is located has also been obliged to prepare a complementary emergency plan, in co-operation with other regional and national authorities, for the prevention of consequences from an emergency that may extend beyond the site boundary of the plant. In preparing the complementary plan, the emergency plan of the facility had to be taken into account. Unlike most national authorities involved in nuclear matters, the Public Health Authority is involved in the preparation of plans for every kind of emergency in a nuclear facility, including even those whose consequences can probably be confined to the plant site. The paper discusses in detail the role and responsibility of the Public Health Authority in emergency planning and preparedness for nuclear facilities. (author)

Development of Northeast Asia Nuclear Power Plant Accident Simulator.

Science.gov (United States)

Kim, Juyub; Kim, Juyoul; Po, Li-Chi Cliff

2017-06-15

A conclusion from the lessons learned after the March 2011 Fukushima Daiichi accident was that Korea needs a tool to estimate consequences from a major accident that could occur at a nuclear power plant located in a neighboring country. This paper describes a suite of computer-based codes to be used by Korea's nuclear emergency response staff for training and potentially operational support in Korea's national emergency preparedness and response program. The systems of codes, Northeast Asia Nuclear Accident Simulator (NANAS), consist of three modules: source-term estimation, atmospheric dispersion prediction and dose assessment. To quickly assess potential doses to the public in Korea, NANAS includes specific reactor data from the nuclear power plants in China, Japan and Taiwan. The completed simulator is demonstrated using data for a hypothetical release. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Building Up an On-Line Plant Information System for the Emergency Response Center of the Hungarian Nuclear Safety Directorate

International Nuclear Information System (INIS)

Vegh, Janos; Major, Csaba; Horvath, Csaba; Hozer, Zoltan; Adorjan, Ferenc; Lux, Ivan; Horvath, Kristof

2002-01-01

The main design features, services, and human-machine interface characteristics are described of the CERTA VITA on-line plant information system developed and installed by KFKI AEKI at the Nuclear Safety Directorate (NSD) of the Hungarian Atomic Energy Authority (HAEA) in cooperation with experts from the NSD. The Center for Emergency Response, Training, and Analysis (CERTA) located at the headquarters of NSD, Budapest, Hungary, was established in 1997. The center supports the NSD installation, radiological monitoring, and advisory team in case of nuclear emergencies, with appropriate hardware and software for communication, diagnosis, prognosis, and prediction. The vital information transfer and analysis (VITA) system represents an important part of the CERTA, as it provides for the continuous remote inspection of the four VVER-440/V213 units of the Hungarian Paks nuclear power plant (NPP). The on-line information system maintains a continuous data link with the NPP through a managed leased line that connects CERTA to a gateway computer located at the Paks NPP. The present scope of the system is a result of a 4-yr development project: In addition to the basic safety parameter display functions, the VITA system now includes an on-line break parameter estimation module, an extensive training package based on simulated transients, and on-line data transfer capabilities to feed accident diagnosis/analysis codes

Nuclear plant analyzer development and analysis applications

International Nuclear Information System (INIS)

Laats, E.T.

1984-10-01

The Nuclear Plant Analyzer (NPA) is being developed as the US Nuclear Regulatory Commission's (NRC's) state of the art safety analysis and engineering tool to address key nuclear plant safety issues. This paper describes four applications of the NPA in assisting reactor safety analyses. Two analyses evaluated reactor operating procedures, during off-normal operation, for a pressurized water reactor (PWR) and a boiling water reactor (BWR), respectively. The third analysis was performed in support of a reactor safety experiment conducted in the Semiscale facility. The final application demonstrated the usefulness of atmospheric dispersion computer codes for site emergency planning purposes. An overview of the NPA and how it supported these analyses are the topics of this paper

Systematic safety evaluation of old nuclear power plants

International Nuclear Information System (INIS)

Dredemis, G.; Fourest, B.

1984-01-01

The French safety authorities have undertaken a systematic evaluation of the safety of old nuclear power plants. Apart from a complete revision of safety documents (safety analysis report, general operating rules, incident and accident procedures, internal emergency plan, quality organisation manual), this examination consisted of analysing the operating experience of systems frequently challenged and a systematic examination of the safety-related systems. This paper is based on an exercise at the Ardennes Nuclear Power Plant which has been in operation for 15 years. This paper also summarizes the main surveys and modifications relating to this power plant. (orig.)

Knowledge-based framework for procedure synthesis and its application to the emergency response in a nuclear power plant

International Nuclear Information System (INIS)

Sharma, D.D.

1986-01-01

In this dissertation a nuclear power plant operator is viewed as a knowledge based problem solver. It is shown that, in responding to an abnormal situation, an operator typically solves several problems, for example, plant status monitoring, diagnosis, sensor data validation, consequence prediction, and procedure synthesis. It is proposed that, in order to respond to unexpected situations and handle procedure failures the capability to synthesize and modify procedures dynamically or in runtime is required. A knowledge based framework for dynamically synthesizing procedures (DPS), a knowledge representation language to apply DPS framework for real problems (DPSRL), and a framework for emergency procedure synthesis (FEPS) for nuclear power plants based on DPS are developed. The DPS framework views the task of synthesis as a process of selecting predefined procedures to match the needs of the dynamically changing plant conditions. The DPSRL language provides knowledge organization and representation primitives required to support the DPS framework. Specifically, it provides mechanisms to build various plant libraries and procedures to access information from them. The capabilities and the use of DPS, DPSRL, and FEPS are demonstrated by developing an experimental expert system for a typical boiling water reactor and analyzing its performance for various selected abnormal incidents

Quality assurance during operation of nuclear power plants

International Nuclear Information System (INIS)

1981-01-01

This Safety Guide provides requirements and recommendations for the establishment and implementation of quality assurance for activities important to safety during commissioning, operation and decommissioning of a nuclear power plant, hereinafter referred to in this Guide as the operation phase or operation. It applies to activities such as: operating, inspecting, testing, commissioning, refuelling, maintaining, repairing, modifying and eventual shut-down and decommissioning of nuclear power plants. It applies also to associated activities related to safety, such as environmental monitoring and responses to emergencies

Goal-oriented functional tree structure for nuclear power plant emergency preparedness

International Nuclear Information System (INIS)

Calabrese, R.V.; Roush, M.L.

1987-01-01

Guidelines for development and implementation of emergency response plans do not provide the planner/implementer with an adequate overview of the functions to be achieved or a measure of their relative importance. To provide a framework in which this importance can be recognized, understood and quantified, a logical goal oriented tree structure has been developed which integrates and gives a clear visual representation of the functions required to meet the emergency preparedness objective. The tree considers a spectrum of both high and low probability events which may require mitigation both onsite and offsite. The ultimate objective: to Minimize the Ill Effects of a Nuclear Power Plant Incident is satisfied by functions concerned with prevention and mitigation of human injury and property damage. A complete and detailed structure which specifies the subfunctions and success paths which satisfy these functions has been developed. Institutional activities such as planning, training, procedure development, monitoring and decision making do not enter the tree directly. Instead, the logic structure defines the extent to which these activities must be considered and the information systems and decision models required for successful implementation of the plan. The top structure of the tree is presented and a few branches are considered in detail. The impact of institutional activities, information systems, etc. is discussed. Tree quantification is considered

High-risk facilities. Emergency management in nuclear, chemical and hazardous waste facilities

International Nuclear Information System (INIS)

Kloepfer, Michael

2012-01-01

The book on emergency management in high-risk facilities covers the following topics: Change in the nuclear policy, risk management of high-risk facilities as a constitutional problem - emergency management in nuclear facilities, operational mechanisms of risk control in nuclear facilities, regulatory surveillance responsibilities for nuclear facilities, operational mechanism of the risk control in chemical plants, regulatory surveillance responsibilities for chemical facilities, operational mechanisms of the risk control in hazardous waste facilities, regulatory surveillance responsibilities for hazardous waste facilities, civil law consequences in case of accidents in high-risk facilities, criminal prosecution in case of accidents in high-risk facilities, safety margins as site risk for emission protection facilities, national emergency management - strategic emergency management structures, warning and self-protection of the public in case of CBRN hazards including aspects of the psych-social emergency management.

Human-machine interaction in nuclear power plants

International Nuclear Information System (INIS)

Yoshikawa, Hidekazu

2005-01-01

Advanced nuclear power plants are generally large complex systems automated by computers. Whenever a rate plant emergency occurs the plant operators must cope with the emergency under severe mental stress without committing any fatal errors. Furthermore, the operators must train to improve and maintain their ability to cope with every conceivable situation, though it is almost impossible to be fully prepared for an infinite variety of situations. In view of the limited capability of operators in emergency situations, there has been a new approach to preventing the human error caused by improper human-machine interaction. The new approach has been triggered by the introduction of advanced information systems that help operators recognize and counteract plant emergencies. In this paper, the adverse effect of automation in human-machine systems is explained. The discussion then focuses on how to configure a joint human-machine system for ideal human-machine interaction. Finally, there is a new proposal on how to organize technologies that recognize the different states of such a joint human-machine system

Particular features of fire protection in nuclear power plants

International Nuclear Information System (INIS)

Krueger, W.

1985-01-01

The particular features of fire protection in nuclear power plants that are connected with the need to ensure nuclear and radiation safety even during an emergency are outlined followed by the recommendation to lay them down in special fire protection standards. These, in conjunction with comprehensive fire hazard analyses, could serve to work out complex concepts for the fire protection of individual nuclear power plants. Such concepts would be very useful for review and assessment of the fire protection design during the licensing process and for later inspections. (author)

Planning and architectural safety considerations in designing nuclear power plants

International Nuclear Information System (INIS)

Konsowa, Ahmed A.

2009-01-01

To achieve optimum safety and to avoid possible hazards in nuclear power plants, considering architectural design fundamentals and all operating precautions is mandatory. There are some planning and architectural precautions should be considered to achieve a high quality design and construction of nuclear power plant with optimum safety. This paper highlights predicted hazards like fire, terrorism, aircraft crash attacks, adversaries, intruders, and earthquakes, proposing protective actions against these hazards that vary from preventing danger to evacuating and sheltering people in-place. For instance; using safeguards program to protect against sabotage, theft, and diversion. Also, site and building well design focusing on escape pathways, emergency exits, and evacuation zones, and the safety procedures such as; evacuation exercises and sheltering processes according to different emergency classifications. In addition, this paper mentions some important codes and regulations that control nuclear power plants design, and assessment methods that evaluate probable risks. (author)

Facilities and medical care for on-site nuclear power plant radiological emergencies

International Nuclear Information System (INIS)

Anon.

1979-01-01

The operation of a nuclear power plant introduces risks of injury or accidents that could also result in the exposure of personnel to radiation or radioactive materials. It is important in such an event to have adequate first aid and medical facilities, supplies, equipment, transportation capabilities and trained personnel available to provide necessary care. This standard provides guidance for first aid during an emergency and for initial medical care of those overexposed to penetrating radiation or contaminated with radioactive material or radionuclides. Recommendations cover facilities, supplies, equipment and the extent of care on-site, where first aid and initial care may be provided, and off-site at a local hospital, where further medical and surgical care may be provided. Additional recommendations are also provided for the transportation of patients and the training of personnel. A brief discussion of specialized care is provided in an appendix

Scenario guidance handbook for emergency-preparedness exercises at nuclear facilities

International Nuclear Information System (INIS)

Laughlin, G.J.; Martin, G.F.; Desrosiers, A.E.

1983-01-01

As part of the Emergency Preparedness Implementation Appraisal Program conducted by the Nuclear Regulatory Commission (NRC) with the technical assistance of the Pacific Northwest Laboratory (PNL), emergency preparedness exercises are observed on an annual basis at all licensed reactor facilities. One of the significant findings to arise from these observations was that a large number of the commonly observed problems originated in the design of the scenarios used as a basis for each exercise. In an effort to help eliminate some of these problems a scenario guidance handbook has been generated by PNL for the NRC to assist nuclear power plant licensees in developing scenarios for emergency preparedness exercises

Reinforcement of planning and response to emergencies inside nuclear power plants; Refuerzo de la planificación y respuesta ante emergencias en el interior de las centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Cortés, M.A.; Garcés, J.M.; Bolaños, J.; Fernández, J.; Gutiérrez, C.; Pontejo, A.; Rosell, B.

2015-07-01

Fukushima Daichi nuclear accident (11th march of 2011) required a rapid and effective response of nuclear industry, in order to guarantee that current safety margins were enough to cope with events like this or even worse. In Europe, stress tests were carried out to comply with that objective, evaluating if every nuclear plant was able to succeed managing design basis accidents or even beyond. Stress-test results were satisfactory, although several areas for improvement where identified. Improvements in emergency response and management have been developed in several phases. First, increasing emergency response capacity by implementing modifications in existing equipment. Later, installing new equipment (generally portable) which would be used in even more degraded conditions. This must be held by the revision of emergency response personnel and their training. Finally, external support has been reinforced to help in longstanding emergencies, with the establishment of CAE (Regional Center), and collaboration protocols with the Army. These actions, supervised and approved by the Regulator Body (CSN) will lead to increase plants safety margins and their emergency response capacities in order to reduce probability and consequences of a nuclear accident to the minimum. [Spanish] El accidente nuclear ocurrido el 11 de marzo de 2011 en Fukushima Daichi requirió de una pronta y efectiva respuesta de la industria nuclear, que garantizase que los márgenes de seguridad eran los adecuados para hacer frente a sucesos de estas características o incluso peores. Con ese objetivo se planteó, a nivel europeo, la realización de unas pruebas de resistencia que valorasen si las centrales podían hacer frente con garantías a una serie de accidentes dentro y más allá de las bases de diseño. Los resultados fueron satisfactorios, si bien se identificaron varios aspectos de mejora. La mejora en la respuesta y gestión de emergencias de las centrales nucleares se ha planteado en

Safety/security interface assessments at commercial nuclear power plants

International Nuclear Information System (INIS)

Byers, K.R.; Brown, P.J.; Norderhaug, L.R.

1985-01-01

The findings of the Haynes Task Force Committee (NUREG-0992) are used as the basis for defining safety/security assessment team activities at commercial nuclear power plants in NRC Region V. A safety/security interface assessment outline and the approach used for making the assessments are presented along with the composition of team members. As a result of observing simulated plant emergency conditions during scheduled emergency preparedness exercises, examining security and operational response procedures, and interviewing plant personnel, the team has identified instances where safety/security conflicts can occur

Safety/security interface assessments at commercial nuclear power plants

International Nuclear Information System (INIS)

Byers, K.R.; Brown, P.J.; Norderhaug, L.R.

1985-07-01

The findings of the Haynes Task Force Committee (NUREG-0992) are used as the basis for defining safety/security assessment team activities at commercial nuclear power plants in NRC Region V. A safety/security interface assessment outline and the approach used for making the assessments are presented along with the composition of team members. As a result of observing simulated plant emergency conditions during scheduled emergency preparedness exercises, examining security and operational response procedures, and interviewing plant personnel, the team has identified instances where safety/security conflicts can occur. 2 refs

Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil

International Nuclear Information System (INIS)

Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar

1996-01-01

In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

Emergency Mitigating Equipments - Post Fukushima Actions at Canadian Nuclear Power Plants - Portable AC Power Sources

International Nuclear Information System (INIS)

Vucetic, Jasmina; Kameswaran, R.

2015-01-01

In response to the Fukushima Daiichi NPP accident in 2011, the Canadian Nuclear Safety Commission set up a Task Force to evaluate operational, technical and regulatory implications on Canadian NPPs. While accepting that the risk from beyond-design-basis accidents (BDBA) at Canadian NPPs is very low, the Task Force identified a number of areas where additional improvements or confirmatory assessments would further enhance safety. As a result, a set of 36 Fukushima Action Items (FAIs) were assigned to the licensees. This paper focuses on the FAI related to electrical power system enhancements to address a total loss of all AC Power leading to a possibility of loss of heat sinks (i.e. Station Blackout). This required the licensees to implement the following: - Additional back up power supplied by portable diesel generator(s) to allow key instrumentation and control equipment and key electrical loads to remain operable; - Provisions for a storage and timely transportation and connection of the portable generator(s) to the applicable units; - Provisions for testing of the portable generator; - Provisions for fuelling of portable generators; - Provisions such as panels, receptacles, and connectors to quickly deploy the portable generators to plant system, and separate feeder cables route to avoid a common mode failure; - Load shedding strategy to extend the existing station's battery life to ensure that the connection of portable generators can be completed before the batteries are depleted; - Provisions to supply water to steam generators and Irradiated Fuel Bay using portable pumps; The paper will also provide a brief description of Electrical power systems of the Canadian NPPs designed to satisfy the high safety and reliability requirements for nuclear systems, which are based on the following: - 2 group design philosophy (Group 1 and Group 2 Electrical Power Systems) - 2 separate groups of onsite emergency generators (Class III Standby generators and Emergency

Fire safety study of Dodewaard and Borssele nuclear power plants

International Nuclear Information System (INIS)

1988-03-01

From the nuclear and conventional fire safety audits of both Dutch nuclear power plants performed under supervision of the Nuclear Safety Inspectorate and the Inspectorate for the Fire Services it turns out that the fire safety is sufficient however amenable for improvement. Besides a detailed description of the method of examination, the study 'Fire Safety' contains the results of the audit and 14 respectively 15 recommendations for improvement of the fire safety in Dodewaard and Borssele. The suggested recommendations which are applicable to both power plants are the following: fire fighting training for operators and guards, a complete emergency ventilation system of the control room, increase in the number of detectors and alarms, an increase in the quantity of water available for high-pressure fire fighting, improvement of fire barriers between several redundancies of nuclear safety systems, an investigation and possible improvement of the heat and radiation protection offered by presently used fire fighting suits. For Dodewaard a closed emergency staircase in the reactor building (secondary containment) is deemed necessary for personnel emergency escape routes and continued fire fighting if required

Preparedness of Operation Teams' Non-technical Skills in a Main Control Room of Nuclear Power Plants to Manage Emergency Situations

Energy Technology Data Exchange (ETDEWEB)

Yim, Ho Bin; Kim, Ar Ryum; Seong, Poong Hyun [Korea Advanced Institute of Science and Technology, Daejeon (Korea, Republic of)

2012-05-15

Human reliability is one of the important determinants for the system safety. Nuclear Energy Agency reported that approximately half of events reported by foreign nuclear industry were related with inappropriate human actions. The human error problems can be viewed in two ways: the person approach and the system approach. Other terms to represent each approach are active failures and latent conditions. Active failures are unsafe acts committed by people who are in direct contact with systems whereas latent conditions are the inevitable 'resident pathogens' within the system. To identify what kinds of non-technical skills were needed to cope with emergency conditions, a method to evaluate preparedness of task management in emergency conditions based on monitoring patterns was presented. Five characteristics were suggested to evaluate emergency task management and communication: latent mistake resistibility, latent violation resistibility, thoroughness, communication, and assertiveness. Case study was done by analyzing emergency training of 9 different real operation teams in the reference plant. The result showed that the 9 teams had their own emergency task management skills which resulted in good and bad performances

Fire protection in nuclear power plants

International Nuclear Information System (INIS)

Wright, H.A.

1981-01-01

This lecture describes briefly the chronological order of events which may arise for a very serious emergency situation in a nuclear power plant for which preparations should be made even though the situation has an extremely low probability of happening. The planning and preparedness required are expected to cope with a whole spectrum of emergency situations, from minor accidents to serious plant failures which also lead to releases of significant quantities of radioactive material beyond the site boundary. Fire protection aspects will be briefly covered, and some guidance will be provided on exercises to ensure the plans are feasible and the appropriate personnel and facilities are in a satisfactory state of preparedness. (orig./RW)

Chemical and nuclear emergencies: Interchanging lessons learned from planning and accident experience

International Nuclear Information System (INIS)

Adler, V.; Sorensen, J.H.; Rogers, G.O.

1989-01-01

Because the goal of emergency preparedness for both chemical and nuclear hazards is to reduce human exposure to hazardous materials, this paper examines the interchange of lessons learned from emergency planning and accident experience in both industries. While the concerns are slightly different, sufficient similarity is found for each to draw implications from the others experience. Principally the chemical industry can learn from the dominant planning experience associated with nuclear power plants, while the nuclear industry can chiefly learn from the chemical industry's accident experience. 23 refs

An expert system for improving nuclear emergency response

International Nuclear Information System (INIS)

Salame-Alfie, A.; Goldbogen, G.C.; Ryan, R.M.; Wallace, W.A.; Yeater, M.L.

1987-01-01

The accidents at TMI-2 and Chernobyl have produced initiatives aimed at improving nuclear plant emergency response capabilities. Among them are the development of emergency response facilities with capabilities for the acquisition, processing, and diagnosis of data which are needed to help coordinate plant operations, engineering support and management under emergency conditions. An effort in this direction prompted the development of an expert system. EP (EMERGENCY PLANNER) is a prototype expert system that is intended to help coordinate the overall management during emergency conditions. The EP system was built using the GEN-X expert system shell. GEN-X has a variety of knowledge representation mechanisms including AND/OR trees, Decision trees, and IF/THEN tables, and runs on an IBM PC-XT or AT computer or compatible. Among the main features, EP is portable, modular, user friendly, can interact with external programs and interrogate data bases. The knowledge base is made of New York State (NYS) Procedures for Emergency Classification, NYS Radiological Emergency Preparedness Plan (REPP) and knowledge from experts of the NYS Radiological Emergency Preparedness Group and the Office of Radiological Health and Chemistry of the New York Power Authority (NYPA)

Uncertainties under emergency conditions and possible application of fuzzy theory for nuclear safety

International Nuclear Information System (INIS)

Nishiwaki, Y.

1996-01-01

Various uncertainties involved in emergency conditions are discussed, and it is pointed out that uncertainties, in many factors, are fuzzy. As a result, it is proposed to use fuzzy theory as an attempt for analysing cause and effects under emergency conditions such as Hiroshima, Nagasaki and other nuclear accidents and, for fuzzy failure analysis and diagnostics of nuclear power plant

Emerging sensor and I and C technologies for nuclear power plants

International Nuclear Information System (INIS)

Korsah, K.; Wood, R. T.; Freer, E.; Antonescu, C.

2006-01-01

This paper presents the findings from a survey of emerging technologies in the field of instrumentation and controls (I and C). The survey findings give an overview of the state-of-the-art in selected technology focus areas for industrial, research, or scientific applications that are relevant to nuclear power plant I and C systems, and discuss potential regulatory impact for safety-related applications. Four technology focus areas are selected for review: Sensors and Measurement Systems; Radiation Hardness of Microprocessors and other Integrated Circuits; Diagnostics and Prognostics Systems; and High-Integrity Software. It is concluded that, while there have been considerable advances in digital I and C hardware, advances in software engineering have not kept pace with hardware. The authors anticipate advances in hardware (e.g., more accurate sensors, sophisticated on-line diagnostics, advances in rad-hard electronics) to influence some regulatory revisions (e.g., surveillance requirements, margins, calibration intervals). However, the state-of-the-art in software engineering has not advanced enough to warrant significant changes in the current position in software review requirements. (authors)

Estimation of environmental external costs between coal fired power plant and nuclear power plant

International Nuclear Information System (INIS)

Moon, G. H.; Kim, S. S.

2000-01-01

First of all, this study evaluated the impacts on the health and the environment of air pollutants emitted from coal power plant and nuclear power pant, two major electric power generating options in Korea. Then, the environmental external costs of those two options were estimated by transforming the health and environment impact into monetary values. To do this, AIRPACTS and Impacts of Atmospheric Release model developed by IAEA were used. The environmental external cost of Samcheonpo coal power plant was estimated about 25 times as much as that of Younggwang nuclear power plant. This result implies that nuclear power plant is a clean technology compared with coal power plant. This study suggests that the external cost should be reflected in the electric system expansion plan in order to allocate energy resources efficiently and to reduce economic impact stemming from the environmental regulation emerged recently on a global level

Safety in nuclear power plant siting. A code of practice

International Nuclear Information System (INIS)

1978-01-01

This publication is brought out within the framework of establishing Codes of Practice and Safety Guides for nuclear power plants: NUSS programme. The scope of the document encompasses site and site-plant interaction factors related to operational states and accident conditions. The purpose of the Code is to give criteria and procedures to be applied as appropriate to operational states and accident conditions, including those which could lead to emergency situations. This Code is mainly concerned with severe events of low probability which relate to the siting of nuclear power plants and have to be considered in designing a particular nuclear power plant. Annex: Examples of natural and man-made events relevant for design basis evaluation

An artificial intelligence approach towards disturbance analysis in nuclear power plants

International Nuclear Information System (INIS)

Lindner, A.; Klebau, J.; Fielder, U.; Baldeweg, F.

1987-01-01

The scale and degree of sophistication of technological plants, e.g. nuclear power plants, have been essentially increased during the last decades. Conventional disturbance analysis systems have proved to work successfully in wellknown situations. But in cases of emergencies, the operator staff needs a more advanced assistance in realizing diagnosis and therapy control. The significance of introducing artificial intelligence methods in nuclear power technology is emphasized. Main features of the on-line disturbance analysis system SAAP-2 are reported about. It is being developed for application in nuclear power plants. 9 refs. (author)

Nuclear emergency preparedness in Canada

International Nuclear Information System (INIS)

1993-03-01

The preparedness of utilities and government agencies at various levels for dealing with nuclear emergencies occurring at nuclear reactors in Canada is reviewed and assessed. The review is centered on power reactors, but selected research reactors are included also. Emergency planning in the U.S.A., Germany and France, and international recommendations on emergency planning are reviewed to provide background and a basis for comparison. The findings are that Canadians are generally well protected by existing nuclear emergency plans at the electric utility and provincial levels but there are improvements that can be made, mainly at the federal level and in federal-provincial coordination. Ten issues of importance are identified: commitment to nuclear emergency planning by the federal government; division of federal and provincial roles and responsibilities; auditing of nuclear emergency preparedness of all levels of government and of electric utilities; the availability of technical guidance appropriate to Canada; protective action levels for public health and safety; communication with the public; planning and response for the later phases of a nuclear emergency; off-site exercises and training; coordination of international assistance; and emergency planning for research reactors. (L.L.) 79 refs., 2 tabs

Application of the methodology of safety probabilistic analysis to the modelling the emergency feedwater system of Juragua nuclear power plant

International Nuclear Information System (INIS)

Troncoso, M.; Oliva, G.

1993-01-01

The application of the methodology developed in the framework of the national plan of safety probabilistic analysis (APS) to the emergency feed water system for the failures of small LOCAS and external electrical supply loss in the nuclear power plant is illustrated in this work. The facilities created by the ARCON code to model the systems and its documentation are also expounded

Analysis of the emergency plan of Angra dos Reis Nuclear Power Plants: a critical view related to accessibility and mobility of people with special needs

International Nuclear Information System (INIS)

Correa, Luanda C.A.; Correa, Samanda C.A.; Santos, Geissa; Souza, Edmilson M.

2014-01-01

This work intends to make a critical analysis of the emergency plan of the Angra dos Reis Nuclear Power Plants related to appropriate transportation, accommodation and infrastructure for people with special needs

Planning for nuclear emergencies

International Nuclear Information System (INIS)

Lakey, J.R.A.

1989-01-01

This paper aims to stimulate discussions between nuclear engineers and the radiological protection professions in order to facilitate planning for nuclear emergencies. A brief review is given of the response to nuclear accidents. Studying accidents can lead to prevention, but some effort must be put into emergency response. Such issues as decontamination and decommissioning, socio-economic consequences, education and training for nuclear personnel and exercises and drills, are raised. (UK)

Change in perception of people towards a nuclear emergency plan for a nuclear power station after being presented

International Nuclear Information System (INIS)

Kouzen, Hideharu

2017-01-01

We conducted a group interview survey for 24 persons living in urban areas of the Kansai region to understand the change in their perception of information about nuclear emergency plans for nuclear power stations. The participants were given descriptions about a nuclear emergency plan based on plans that had been prepared by the national government and local government. Before hearing the explanation about the nuclear emergency plan, we found that only a few participants were concerned about it, but no one knew the detailed contents. For the question 'Do you think the nuclear emergency plan is being improved after the Fukushima Daiichi Nuclear Power Plant accident?', we found 6 persons among the 24 held opinions saying that the plan was 'improved' or 'somewhat improved'. However, after hearing the explanation and a brief Q and A session about it, 18 persons held opinions saying the plan was 'improved' or 'somewhat improved'. As the reason for such answers, the most common opinion shared by 13 persons was that 'a nuclear emergency plan is being made'. There is a possibility that urban residents had not known the facts about specific disaster prevention plans for each nuclear power station that have been formulated. (author)

Plant incident progress scenario analysis for nuclear emergency exercise of Fukui Pref. 2009

International Nuclear Information System (INIS)

Tatebe, Yasumasa; Yoshida, Yoshitaka; Minami, Noritoshi

2010-01-01

Severe accident scenario was analyzed to assist the nuclear emergency exercise of Fukui prefecture in 2009. The evaluation of the postulated disaster was evaluated based on analysis result, including the time of occurrence of specified events, response of the plant to the AM measures, etc. The evaluation results are as follows: (1) loss of core cooling took place about 7 hours after, abnormal leakage of fission products from containment vessel to the containment annulus started about 17 hours after and the disaster terminated about 46 hours after the initiation of the accident, (2) although multiple failures of the engineered safety system and failure of AM measures were postulated in the accident scenario, the integrity of the containment vessel could be maintained successfully for a long term, if the AM measures are taken to protect the containment vessel. (3) according to the evaluation of radiation dose rate during the emergency response assuming the operation of recirculation mode using containment spray A, the dose rate could be too high for the operators to work not only in the containment spray A area but also in the another containment spray heat exchanger and the residual heat removal system heat exchanger areas. (author)

Sea water pumping-up power plant system combined with nuclear power plant

International Nuclear Information System (INIS)

Ichiki, Tadaharu; Tanaka, Masayuki.

1991-01-01

It is difficult to find a site suitable to construction for a sea water pumping-up power plant at a place relatively near the electric power consumption area. Then, a nuclear power plant is set at the sea bottom or the land portion of a sea shore near the power consumption area. A cavity is excavated underground or at the bottom of the sea in the vicinity of the power plant to form a lower pond, and the bottom of the sea, as an upper pond and the lower pond are connected by a water pressure pipe and a water discharge pipe. A pump water turbine is disposed therebetween, to which electric power generator is connected. In addition, an ordinary or emergency cooling facility in the nuclear power plant is constituted such that sea water in the cavity is supplied by a sea water pump. Accordingly, the sea water pumping-up plant system in combination with the nuclear power plant is constituted with no injuring from salts to animals and plants on land in the suburbs of a large city. The cost for facilities for supplying power from a remote power plant to large city areas and power loss are decreased and stable electric power can be supplied. (N.H.)

A Method for Analyzing the Communications among Nuclear Power Plant Operators in Emergency Situations

International Nuclear Information System (INIS)

Kim, Man Cheol; Park, Jin Kyun; Jung, Won Dea

2006-01-01

Communications among MCR operators is an important factor for understanding how and how well MCR operators manage abnormal situations in NPPs. As mentioned by Ujita et al., the performance of MCR operators in emergency situations in NPPs is strongly affected by not only the cognitive process for each operator, but also by communications and collaboration among operators. Many researches have been conducted to find out the relation between the communication of human operators and the performance of them. But, it seems that few researches have been conducted on in what way the communication among MCR operators should be performed to enhance the performance of them. In this paper, we propose an analysis method for evaluating the quality of communications among MCR operators in nuclear power plants (NPPs)

Transient evaluation using EMTP at single open phase with the offsite power transformer for the emergency power supply systems of nuclear power plants

International Nuclear Information System (INIS)

Shimada, Yoshio

2017-01-01

The emergency power supply systems of nuclear power plants, as the objects of this research, are critical in supplying stable electric power to such systems as the emergency core cooling system (ECCS), and in maintaining safety of the nuclear power reactor; this was apparent in the accident at the Fukushima Daiichi Nuclear Power Station. The Nuclear Regulatory Commission (USNRC) issued regulatory documents (BL 2012-011, IN 2012-032), and has commenced evaluations on newly discovered vulnerability in the design of power supply systems which cannot be detected with under-voltage protection relays, with certain kinds of configuration of coils and iron core structures, such as when the offsite power supply side is a Y-connection and the load side is a ⊿-connection etc., when the detection of single open phase fault with the circuit of a transformer which is without a ground fault connected to the offsite power supply system. This report uses simulation by the electro magnetic transients program (EMTP) and clearly describe the response at the time of the power supply single open phase without ground fault for various configuration of coils and various iron core structures of the three-phase transformer, and identify the important issues in the response of emergency power supply systems and the safety related components of representative domestic PWR plants when the single open phase fault occurred without ground fault. This report describes the results of the simulations of operations of the protection relays of the emergency power supply systems and the safety related components of representative a domestic PWR plant with EMTP. This report explains the method to detect open-phase when the transformer is no-load which United States Electric Power Research Institute (EPRI) developed. As the detailed analyses data from EPRI related to the detection method concerned have not been disclosed officially yet, in this paper, the quantitative and detailed verification results

Emergency preparedness and response: compensating victims of a nuclear accident

International Nuclear Information System (INIS)

Schwartz, Julia

2004-01-01

The 1986 tragedy at the Chernobyl Nuclear Power Plant in Ukraine motivated the entire international nuclear community to ensure that countries would, in the future, be well prepared to manage the physical, psychological and financial consequences of a serious nuclear accident. Since that event, numerous nuclear emergency preparedness and post-emergency management programmes have been established at national and international levels to ensure that appropriate mechanisms will respond to the threat, and the aftermath, of a nuclear accident. The INEX 2000 Workshop on the Indemnification of Nuclear Damage, jointly organised by the OECD/Nuclear Energy Agency and the French Government, was the first ever international programme to address the manner in which victims of a nuclear accident with trans-boundary consequences would be compensated for damage suffered before, during and after the accident. The Workshop results revealed striking differences in the compensation principles and practices implemented in the 30 participating countries, in the co-ordination measures between different public authorities within an affected state, and in the co-operative procedures between the accident state and its neighbours. All participants agreed on the need for improvement in these areas, particularly for maintaining public confidence in governments' ability to properly manage nuclear emergencies

Emergency management for a nuclear power plant using fuzzy cognitive maps

International Nuclear Information System (INIS)

Espinosa-Paredes, G.; Nunez-Carrera, A.; Laureano-Cruces, A.L.; Vazquez-Rodriguez, A.; Espinosa-Martinez, E.-G.

2008-01-01

This paper explores the application of fuzzy cognitive maps (FCM) to emergency operating procedures (EOPS), to represent the decision-making process during abnormal situations in a nuclear power plant (NPP). The decision-making process in a NPP is a complex process, due to the many elements involved in its operation, and the permanent attention demanded by its maintenance. At the present time, the decision making process in a NPP is analyzed and developed by reactor operators, based on a set of instructions as well as flow charts to mitigate the consequences of a broad range of transients, accidents and multiple equipment failures, whose main characteristic is to be linear representations of events within a scenario. One of the main objectives of this paper is to present a method based in FCM that could be applied in the development of EOPS, and show some simulations, specifically the loss of coolant accident (LOCA) scenario in a boiling water reactor (BWR) with the Mark II containment design was studied. The FCM-based method represents with high fidelity the expert reasoning (the human expert is very important) and the interpretation of the results aids instantly to the reactor operators in the surveillance of the reactor proper functionality due that they have the responsibility of the decision taking in emergency situations. The simulations results show that the FCM predict properly the phenomenon in the reactor vessel and primary containment

Nuclear power plants

International Nuclear Information System (INIS)

Margulova, T.Ch.

1976-01-01

The textbook focuses on the technology and the operating characteristics of nuclear power plants equiped with pressurized water or boiling water reactors, which are in operation all over the world at present. The following topics are dealt with in relation to the complete plant and to economics: distribution and consumption of electric and thermal energy, types and equipment of nuclear power plants, chemical processes and material balance, economical characteristics concerning heat and energy, regenerative preheating of feed water, degassing and condenser systems, water supply, evaporators, district heating systems, steam generating systems and turbines, coolant loops and pipes, plant siting, ventilation and decontamination systems, reactor operation and management, heat transfer including its calculation, design of reactor buildings, and nuclear power plants with gas or sodium cooled reactors. Numerous technical data of modern Soviet nuclear power plants are included. The book is of interest to graduate and post-graduate students in the field of nuclear engineering as well as to nuclear engineers

Anticipated and abnormal transients in nuclear power plants

International Nuclear Information System (INIS)

Karam, R.A.

1987-01-01

This book contains the proceedings of an international conference on Anticipated and Abnormal Transients in Nuclear Power Plants. Included are the following papers: Comparative evaluation of recent water hammer events in light water reactors, Rick reduction through enhanced human performance, Assessment of the performance of an emergency boration system for anticipated transients without trip faults, Emergency procedure planning to mitigate event progression

Development of a standard communication protocol for an emergency situation management in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kim, Man Cheol, E-mail: charleskim@kaeri.re.k [Integrated Risk Assessment Center, Korea Atomic Energy Research Institute, 150, Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Park, Jinkyun; Jung, Wondea [Integrated Risk Assessment Center, Korea Atomic Energy Research Institute, 150, Deokjin-dong, Yuseong-gu, Daejeon 305-353 (Korea, Republic of); Kim, Hanjeom; Kim, Yoon Joong [YGN Nuclear Power Division Training Center, Korea Hydro and Nuclear Power Company, 517 Kyemari, Hongnong-eup, Yeongkwang-gun, Chonnam 513-880 (Korea, Republic of)

2010-06-15

Correct communication between main control room (MCR) operators is an important factor in the management of emergency situations in nuclear power plants (NPPs). For this reason, a standard communication protocol for the management of emergency situations in NPPs has been developed, with the basic direction of enhancing the safety of NPPs and the standardization of communication protocols. To validate the newly developed standard communication protocol, validation experiments with 10 licensed NPP MCR operator teams was performed. From the validation experiments, it was found that the use of the standard communication protocol required more time, but it can contribute to the enhancement of the safety of NPPs by an operators' better grasp of the safety-related parameters and a more efficient and clearer communication between NPP operators, while imposing little additional workloads on the NPP MCR operators. The standard communication protocol is expected to be used to train existing NPP MCR operators without much aversion, as well as new operators.

Emergency ac power systems operating experience at U.S. nuclear power plants - 1976 through 1983

Energy Technology Data Exchange (ETDEWEB)

Battle, R. E. [Oak Ridge National Laboratory, Oak Ridge, Tennessee (United States)

1986-02-15

Success and failure data of test and emergency starts of emergency ac power sources (diesel generators) at U.S. nuclear power plants were collected and evaluated to estimate diesel generator reliability parameters. A regression analysis of the estimates of the probability of failure to start based on surveillance test data from 1976 through 1983 indicates that the probability of failure to start has been decreasing. However, the reliability of diesel generator performance during losses of off-site power for 1981 through 1983 was less than expected based on the test data estimates. The failures that occurred during losses of off-site power were reviewed to determine why the calculated failure to start was greater than expected, and possible explanations for this high value are presented. The subsystems involved In diesel generator subsystem failures were categorized to determine whether there were any dominant failure modes. The results indicate that further significant Improvement in diesel generator reliability will require improvement of many subsystems. (author)

Nuclear power plant safety, the merits of separation

International Nuclear Information System (INIS)

Helander, L.I.; Tiren, L.I.

1977-01-01

The United States AEC General Design Criteria for Nuclear Power Plants are used worldwide as a basis for the assessment of nuclear plant safety. Several of these criteria require redundancy of safety systems, separation of protection and control systems, consideration of natural phenomena, etc. All these criteria point in one particular direction: the necessity for physically separating the various safety-related systems of a nuclear power plant, particularly with regard to single occurrences that may yield a multiple failure. Requirements in this regard have been amplified by the United States NRC Regulatory Guides and by IEEE Standards. The single occurrence that yields a multiple failure may be, for example, fire, pipe whip, missiles, flooding, hurricanes, or lightning. The paper discusses protection, against the quoted events and others, obtained through applying criteria regarding redundancy and separation of safety-related structures, systems and components. Such criteria affect nuclear plant design in many areas, such as building lay-out, arrangements for fire protection and ventilation, separation of mechanical systems and components, in particular emergency cooling systems, and separation of electric equipment and cables. Implementation of the ensuing design criteria for a BWR power plant is described. This design involves the separation of Emergency Cooling Systems into four 50% Capacity Systems which are independent and separated, including the distribution network for electric power from on-site standby diesel generators and the circuitry for the reactor protection system. The plant is subdivided into a number of fire zones each with its own independent ventilation system. The fire zones are further subdivided into a multitude of fire cells such that redundant subsystems are housed in separate cells. These design precautions with regard to fire are complemented by extensive fire fighting systems

Nuclear threats and emergency preparedness in Finland; Ydinuhkat ja varautuminen

Energy Technology Data Exchange (ETDEWEB)

Mustonen, R; Aaltonen, H; Laaksonen, J; Lahtinen, J; Rantavaara, A; Reponen, H; Rytoemaa, T; Suomela, M; Toivonen, H; Varjoranta, T

1995-10-01

The political and economic upheavals which have taken place in Eastern Europe have had an impact on radiation and nuclear safety throughout Europe. Emergency preparedness systems for unexpected nuclear events have been developed further in all European countries, and prosperous western nations have invested in improving the safety of East European nuclear power plants. The economic crisis facing countries of the former Soviet Union has also promoted illicit trade in nuclear materials; this has made it necessary for various border guards and police authorities to intensify their collaboration and to tighten border controls. On 3-4 October 1995, Finnish Centre for Radiation and Nuclear Safety (STUK) arranged a seminar on nuclear threats and emergency preparedness in Finland. In addition to STUK experts, a wide range of rescue and civil defence authorities, environmental health specialists and other persons engaged in emergency preparedness attended the seminar. The publication contains a compilation of reports presented at the seminar. The reports cover a broad spectrum of nuclear threats analyzed at STUK, the impacts of radioactive fallout on human beings and on the environment, and preparedness systems by which the harmful effects of radiation or nuclear accidents can, if necessary, be minimized. (33 figs., 5 tabs.).

Center for emergency response at the ENUSA fuel fabrication plant in Juzbado; El centro de gestion de las emergencias de la fabrica de combustible nuclear de ENUSA en Juzbado

Energy Technology Data Exchange (ETDEWEB)

Alvaro Perez, C.; Romano, A.

2016-08-01

Effective emergency preparedness and management is critical for a safe exploitation of nuclear installations like the Enusa fuel fabrication plant. In 2012, an important project was carried out at the plant which enlarged and remodeled the Emergency Room used until then to give response to the Internal Emergency Plan postulated scenarios. This project was motivated after carefully analyzing the results of audits, inspections and operation experience as well as after studying the conclusions of the Fukushima accident emergency management weaknesses. The new Center for Emergency Response, which hosts the plant control room, devoted to monitoring the plant safety systems on a constant basis, greatly improves both technical means available and operative procedures as well as human interactions during an emergency. This paper describes the most relevant technical features of this Center, the safety systems which support its operation and the emergency management process that takes place in it. (Author)

Nuclear power plant safety. The merits of separation

International Nuclear Information System (INIS)

Helander, L.I.; Tiren, L.I.

1977-01-01

The paper illustrates how the physical separation of safety-related structures, systems and components can improve the protection of a nuclear power plant against multiple failures that may be caused by events such as fire, pipe-whip, missiles, flooding, hurricanes, lightning etc. Criteria for redundancy and separation requirements affect nuclear plant design in many areas such as building layout, arrangements for fire protection and ventilation, separation of mechanical systems and components, in particular emergency cooling systems, separation of electric equipment and cables. The implementation of the ensuing design criteria for a BWR power plant is described. This design involves the separation of emergency cooling systems into four 50% capacity systems, which are independent and separated, including the distribution network for electric power from on-site standby diesel generators and the circuitry for the reactor protection system. The plant is subdivided into a number of fire zones, each with its own independent ventilation system. The fire zones are further subdivided into a multitude of fire cells such that redundant subsystems are housed in separate cells. These design precautions with regard to fire are complemented by extensive fire fighting systems. (author)

American National Standard: for facilities and medical care for on-site nuclear-power-plant radiological emergencies

International Nuclear Information System (INIS)

Anon.

1979-01-01

This standard provides guidance for first aid during an emergency and for initial medical care of those persons on-site who are overexposed to penetrating radiation (irradiated). It also provides guidance for medical care of persons contaminated with radioactive material or radionuclides who may also be irradiated or injured as a result of an accident at a nuclear power plant. It provides recommendations for facilities, supplies, equipment, and the extent of care both on-site where first aid and initial care may be provided and off-site at a local hospital where further medical and surgical care may be provided. This initial care continues until either the patient is released or admitted, or referred to another, possibly distant, medical center for definitive care. Recommendations are also provided for the transportation of patients and the training of personnel. Recommendations for specialized care are considered to be beyond the scope of this standard on emergency medical care; however, since emergency and specialized care are related, a brief discussion of specialized care is provided in the Appendix

Recommended criteria for the evaluation of on-site nuclear power plant emergency plans, volume II: criteria

International Nuclear Information System (INIS)

1997-01-01

A critical review of existing Canadian and international nuclear power plant (NPP) emergency plans, evaluation criteria, and approaches has been conducted to provide AECB staff with information which can be used to assess the adequacy of NPP on-site emergency response plans. The results of this work are published in two volumes. Volume I, Basis Document, provides the reasons why certain requirements are in place. It also gives comprehensive references to various standards.Volume II, Criteria, contains the criteria which relate to on-site actions and their integration with control room activities and the roles of off-site responsible organizations. The recommended criteria provide information on what is required, and not on how to accomplish the requirements. The licensees are given the latitude to decide on the methods and processes needed to meet the requirements. The documents do not address NPP off-site plans and response capability, or the control room emergency operating procedures and response capability. This report contains only Volume II: Criteria. 55 refs., 2 tabs., 1 fig

NKS - The Nordic region's cooperative network for addressing challenges in nuclear safety and emergency preparedness

Energy Technology Data Exchange (ETDEWEB)

Andersson, K.G. [NKS/Technical University of Denmark (Denmark); Andgren, K. [NKS/Vattenfall R and D (Sweden); Leino, K. [NKS/Fortum Power and Heat Oy (Finland); Magnusson, S. [NKS/Icelandic Radiation Safety Authority (Iceland); Physant, F. [NKS/FRIT, Roskilde (Denmark)

2014-07-01

Based on the foundation of a common cultural and historical heritage and a long tradition of collaboration, NKS aims to facilitate a common Nordic view on nuclear and radiation safety. A common understanding of rules, practice and measures, and national differences in this context, is here an essential requirement. Problems can generally be tackled quicker, more efficiently, more consistently and at a lower cost through collaboration, bearing in mind that key competencies are not equally distributed in the different Nordic countries. For instance common Nordic challenges emerge in relation to nuclear installations, where nuclear power plants are in operation in Finland and Sweden, and research reactors have been operated in Denmark, Finland, Norway and Sweden. There is an obvious benefit in exchanging ideas and technologies in relation to plant operation, and since a number of reactors in different Nordic countries are under decommissioning, a collaborative benefit can also be realised in that context. Sweden also has a nuclear fuel production plant, and its collaboration with other Nordic nuclear installations can also be beneficial. Further, a number of large radiological installations are projected in Nordic areas (e.g., the MAX-LAB/MAX IV synchrotron radiation source and the European spallation source ESS), where Nordic organisations are collaborating in addressing, e.g., potential environmental implications. On the emergency preparedness side, the Fukushima accident in March 2011 was a reminder that large accidents at nuclear installations can lead to widespread radioactive contamination in the environment. In order to respond to nuclear or radiological emergencies, should they affect Nordic populations, it is necessary to maintain an operational emergency preparedness. By continuously improving detection, response and decision aiding tools while maintaining an informal collaborative network between relevant stakeholders in the Nordic countries (including

Safety philosophy for nuclear power plants in egypt

International Nuclear Information System (INIS)

Mervat, S.A.; Hammad, F.H.

1988-01-01

This work establishes the basic principles of a safety philosophy for nuclear power plants in egypt. A number of deterministic requirements stemming the multiple barriers and the defense-in-depth concept are emphasised. other requirements in the areas of siting, operational safety, safety analysis, special issues, and experience feedback are also identified. The role of international cooperation in nuclear safety technology-transfer and nuclear emergencies is highlighted. In addition probabilistic ally based guidelines are set for acceptable risk and dose limits

The Nuclear Emergency Assistance Team, an Institution for Nuclear Emergency Relief

Energy Technology Data Exchange (ETDEWEB)

Boldyreff, P.; Kiefer, H.; Krause, H.; Zuehlke, K. [Gesellschaft fuer Kernforschung mbH, Karlsruhe, Federal Republic of Germany (Germany)

1969-10-15

The design of nuclear facilities is to exclude serious damage to the environment, even in case of the MCA (maximum credible accident). Although the likelihood of accidents exceeding the expected consequences of the MCA is extremely small, it is deemed reasonable to take general precautions against such accidents. Precautions of this type are customary also in the conventional field, and in this case they are to be implemented in part through the Nuclear Emergency Assistance Team. If the internal safety provisions of a nuclear facility are unable to prevent an impermissible leakage of radioactivity as the result of a major accident there is, at present, no possibility of decisively curbing the spread of activity throughout the environment in the first few hours after the accident. Hence the measures taken by the authorities as a result of the emission and immediately following upon it will have to be restricted to the protection of the population: analysis of intensity and pattern of distribution of activity, instructions.to seek closed shelters, or prohibition of the consumption of certain foodstuffs, distribution of blocking agents, etc. It is the purpose of the Nuclear Emergency Assistance Team to bring relief in the phase following the end of the emission. This may comprise the following steps: exact investigation of the external scope of the damage, in particular assessment of the contamination of ground, persons, and material; rapid personnel decontamination; securing and shielding radiation sources; fixing contamination and removing it immediately where this is deemed urgent for reasons of traffic or to keep the drinking water free from contamination; external containment of the source of danger; support in limiting the damage within the facility. In addition to these tasks of emergency protection, the Nuclear Emergency Assistance Team can take action also in disturbances within the facility which have no influence on the environment and where the operator

The emerging nuclear suppliers

International Nuclear Information System (INIS)

Dunn, L.A.

1990-01-01

Since the early 1980s, a growing amount of attention has been paid to a small group of mostly developing countries that have come to be called the emerging nuclear suppliers. Argentina and Brazil, China and South Korea, India and Pakistan, Spain and Yugoslavia have frequently been mentioned in this category. Their actual and potential nuclear export dealings and policies have been the subject of academic writings and policy papers, of scholarly symposia and exchanges at meetings of the traditional nuclear suppliers. With foundation and other support, UCLA's Center for International and Strategic Affairs has begun a major project to develop a database on the transactions, policies, and export control institutions of the emerging suppliers. This chapter provides some guidelines for policy toward the emerging nuclear suppliers

Safety problems of nuclear power plants with channel-type graphite boiling water reactors

International Nuclear Information System (INIS)

Emel'yanov, I.Ya.; Vasilevskij, V.P.; Volkov, V.P.; Gavrilov, P.A.; Kramerov, A.Ya.; Kuznetsov, S.P.; Kunegin, E.P.; Rybakov, N.Z.

1977-01-01

Construction of nuclear power plants in a highly populated region near large industrial centres necessitates to pay a special attention to their nuclear and radiation safety. Safety problems of nuclear reactor operation are discussed, in particular, they are: reliable stoppage of fission chain reaction at any emergency cases; reliable core cooling with failure of various equipment; emergency core cooling with breached pipes of a circulating circuit; and prevention of radioactive coolant release outside the nuclear power plant in amount exceeding the values adopted. Channel-type water boiling reactors incorporate specific features requiring a new approach to safety operation of a reactor and a nuclear power plant. These include primarily a rather large steam volume in the coolant circuit, large amount of accumulated heat, void reactivity coefficient. Channel-type reactors characterized by fair neutron balance and flexible fuel cycle, have a series of advantages alleviating the problem of ensuring their safety. The possibility of reliable control over the state of each channel allows to replace failed fuel elements by the new ones, when operating on-load, to increase the number of circulating loops and reduce the diameter of main pipelines, simplifies significantly the problem of channel emergency cooling and localization of a radioactive coolant release from a breached circuit. The concept of channel-type reactors is based on the solution of three main problems. First, plant safety should be assured in emergency switch off of separate units and, if possible, energy conditions should be maintained, this is of particular importance considering the increase in unit power. Second, the system of safety and emergency cooling should eliminate a great many failures of fuel elements in case of potential breaches of any tube in the circulating circuit. Finally, rugged boxes and localizing devices should be provided to exclude damage of structural elements of the nuclear power

A human error analysis methodology, AGAPE-ET, for emergency tasks in nuclear power plants and its application

Energy Technology Data Exchange (ETDEWEB)

Kim, Jae Whan; Jung, Won Dea [Korea Atomic Energy Research Institute, Taejeon (Korea)

2002-03-01

This report presents a procedurised human reliability analysis (HRA) methodology, AGAPE-ET (A Guidance And Procedure for Human Error Analysis for Emergency Tasks), for both qualitative error analysis and quantification of human error probability (HEP) of emergency tasks in nuclear power plants. The AGAPE-ET is based on the simplified cognitive model. By each cognitive function, error causes or error-likely situations have been identified considering the characteristics of the performance of each cognitive function and influencing mechanism of PIFs on the cognitive function. Then, error analysis items have been determined from the identified error causes or error-likely situations to help the analysts cue or guide overall human error analysis. A human error analysis procedure based on the error analysis items is organised. The basic scheme for the quantification of HEP consists in the multiplication of the BHEP assigned by the error analysis item and the weight from the influencing factors decision tree (IFDT) constituted by cognitive function. The method can be characterised by the structured identification of the weak points of the task required to perform and the efficient analysis process that the analysts have only to carry out with the necessary cognitive functions. The report also presents the the application of AFAPE-ET to 31 nuclear emergency tasks and its results. 42 refs., 7 figs., 36 tabs. (Author)

Organisation of the INEX2-HUN nuclear emergency exercise

International Nuclear Information System (INIS)

Lux, I.; Borsi, L.; Feher, I.; Ronaky, J.

2000-01-01

The third exercise in the INEX2 series organised under the auspices of OECD NEA was held in November 1998 in Hungary, with the participation of 4000 members of the Hungarian Emergency Response Organisation (HERO), 32 countries and 4 international organisations. The main goal of the INEX2 series was to exercise emergency preparedness activity with limited knowledge on the accident situation, to test the international notification schemes and to gain experience in informing the media and the population. The INEX2-HUN exercise assumed a medium severe accident in the Hungarian nuclear power plant with relatively high release of radioactive material that could reach also the territory of the neighbouring countries. The scenario of the accident has been elaborated by power plant experts and was played by the full scope simulator of the plant during the exercise. The nuclear emergency organisations were alerted and set up, and a full range exercise was held. The Hungarian Atomic Energy Authority (HAEA) Centre of Emergency Response Training and Analysis (CERTA) obtained on-line data from the power plant, performed source term calculations, prepared progression forecast and even analysis. The radiological monitoring network of the Emergency Information Centre (EIC) of the Secretariat to the Governmental Commission for Nuclear Emergency Preparedness (GCNEP) collected and analysed (simulated) radiological data. EIC received also the meteorological data and - making use of the source term estimates obtained from CERTA - run the specific program that gave detailed description of the radiological situation over the affected area and generated proposals to the decision-makers on the interventions to be performed. The results of the analysis and simulation were used to compile the information to be communicated to the leading organs of HERO, to the neighbouring countries and to the international community by the International Contact Point situated in the HAEA. Technical questions

Configuration management of plant modifications for nuclear power plants

International Nuclear Information System (INIS)

Ritsch, W.J.

1987-01-01

Due to the increasing complexity of nuclear power plant operation, regulatory pressure, and the large numbers of people required to operate and support the stations, the control of plant modifications at these plants needs to be expanded and improved. The aerospace and defense industries, as well as the owners or operators of large energy projects have established configuration management programs (CMPs) to control plant design changes. These programs are composed of well-defined functions for identifying, evaluating, recording, tracking, issuing, and documenting the established baseline conditions, as well as required changes to these baseline conditions. The purpose of this paper is to describe a recommended CMP for plant modifications consisting of a computerized data base installed on the utility's computer to provide a central storage of plant design and operations data necessary to control the following activities as they are affected by plant design changes: training; record management; operations; maintenance; health physics; planning/scheduling; procurement/inventory control; outage management (including modifications); and emergency response

Fukushima Nuclear Accident, the Third International Severe Nuclear Power Plant Accident

International Nuclear Information System (INIS)

Rashad, S.M.

2013-01-01

Japan is the world's third largest power user. Japan's last remaining nuclear reactor shutdown on Saturday 4 Th of May 2012 leaving the country entirely nuclear free. All of 50 of the nation's operable reactors (not counting for the four crippled reactors at Fukushima) are now offline. Before last year's Fukushima nuclear disaster, the country obtained 30% of its energy from nuclear plants, and had planned to produce up to 50% of its power from nuclear sources by 2030. Japan declared states of emergency for five nuclear reactors at two power plants after the units lost cooling ability in the aftermath of Friday 11 March 2011 powerful earthquake. Thousands of (14000) residents were immediately evacuated as workers struggled to get the reactors under control to prevent meltdowns. On March 11 Th, 2011, Japan experienced a sever earthquake resulting in the shutdown of multiple reactors. At Fukushima Daiichi site, the earthquake caused the loss of normal Ac power. In addition it appeals that the ensuing tsunami caused the loss of emergency Ac power at the site. Subsequent events caused damage to fuel and radiological releases offsite. The spent fuel problem is a wild card in the potentially catastrophic failure of Fukushima power plant. Since the Friday's 9.0 earthquake, the plant has been wracked by repeated explosions in three different reactors. Nuclear experts emphasized there are significant differences between the unfolding nuclear crisis at Fukushima and the events leading up to the Chernobyl disaster in 1986. The Chernobyl reactor exploded during a power surge while it was in operation and released a major cloud of radiation because the reactor had no containment structure around to. At Fukushima, each reactor has shutdown and is inside a 20 cm-thick steel pressure vessel that is designed to contain a meltdown. The pressure vessels themselves are surrounded by steel-lined, reinforced concrete shells. Chernobyl disaster was classified 7 on the International

Incorporation of severe accidents in the licensing of nuclear power plants

International Nuclear Information System (INIS)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz

2011-01-01

Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

Incorporation of severe accidents in the licensing of nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Alvarenga, Marco Antonio Bayout; Rabello, Sidney Luiz, E-mail: bayout@cnen.gov.b, E-mail: sidney@cnen.gov.b [Comissao Nacional de Energia Nuclear (CNEN) Rio de Janeiro, RJ (Brazil)

2011-07-01

Severe accidents are the result of multiple faults that occur in nuclear power plants as a consequence from the combination of latent failures and active faults, such as equipment, procedures and operator failures, which leads to partial or total melting of the reactor core. Regardless of active and latent failures related to the plant management and maintenance, aspects of the latent failures related to the plant design still remain. The lessons learned from the TMI accident in the U.S.A., Chernobyl in the former Soviet Union and, more recently, in Fukushima, Japan, suggest that severe accidents must necessarily be part of design-basis of nuclear power plants. This paper reviews the normative basis of the licensing of nuclear power plants concerning to severe accidents in countries having nuclear power plants under construction or in operation. It was addressed not only the new designs of nuclear power plants in the world, but also the design changes in plants that are in operation for decades. Included in this list are the Brazilian nuclear power plants, Angra-1, Angra-2, and Angra-3. This paper also reviews the current status of licensing in Brazil and Brazilian standards related to severe accidents. It also discusses the impact of severe accidents in the emergency plans of nuclear power plants. (author)

Nuclear emergencies and protective actions

International Nuclear Information System (INIS)

Sjoeblom, Klaus

1995-01-01

Although technical improvements have increased the safety of new and old nuclear power plants, many simultaneous component failures and/or human errors are improbable but possible. Both the plant (on-site) and the nearby area (off-site) have emergency plans. Rescue service authorities are responsible of the off-site. The main protective actions are sheltering, evacuation and iodine ingestion. The Loviisa off-site emergency plan assumes that a major part of this population takes care of their own protective actions; Rescue service authorities can then concentrate on the coordination activities and to those people who need help. To be able to carry out the protective actions timely and effectively the people should have information on radiation risk and emergency planning. In case of a potential accident the local population should follow the rescue service information and know how to shelter and how to evacuate themselves. Though there are many stockpiles of iodine pellets in the area the rescue service authorities recommend that each household should purchase iodine pellets for their own need. The utility and the rescue service authorities have distributed information brochures to all homes within 30 km from Loviisa NPP since 1990. This brochure gives information on radiation and protective actions in case of an accident. Because the brochures might not stay available and so also the local telephone book contains this information

Technical evaluation of the proposed changes in the technical specifications for emergency power sources for the Big Rock Point nuclear power plant

International Nuclear Information System (INIS)

Latorre, V.R.

1979-12-01

The technical evaluation is presented for the proposed changes to the Technical Specifications for emergency power sources for the Big Rock Point nuclear power plant. The criteria used to evaluate the acceptability of the changes include those delineated in IEEE Std-308-1974, and IEEE Std-450-1975 as endorsed by US NRC Regulatory Guide 1.129

Sabotage at Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Purvis, James W.

1999-07-21

Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented.

Sabotage at Nuclear Power Plants

International Nuclear Information System (INIS)

Purvis, James W.

1999-01-01

Recently there has been a noted worldwide increase in violent actions including attempted sabotage at nuclear power plants. Several organizations, such as the International Atomic Energy Agency and the US Nuclear Regulatory Commission, have guidelines, recommendations, and formal threat- and risk-assessment processes for the protection of nuclear assets. Other examples are the former Defense Special Weapons Agency, which used a risk-assessment model to evaluate force-protection security requirements for terrorist incidents at DOD military bases. The US DOE uses a graded approach to protect its assets based on risk and vulnerability assessments. The Federal Aviation Administration and Federal Bureau of Investigation conduct joint threat and vulnerability assessments on high-risk US airports. Several private companies under contract to government agencies use formal risk-assessment models and methods to identify security requirements. The purpose of this paper is to survey these methods and present an overview of all potential types of sabotage at nuclear power plants. The paper discusses emerging threats and current methods of choice for sabotage--especially vehicle bombs and chemical attacks. Potential consequences of sabotage acts, including economic and political; not just those that may result in unacceptable radiological exposure to the public, are also discussed. Applicability of risk-assessment methods and mitigation techniques are also presented

Current trends in codal requirements for safety in operation of nuclear power plants

International Nuclear Information System (INIS)

Srivasista, K.; Shah, Y.K.; Gupta, S.K.

2006-01-01

The Code of practice on safety in nuclear power plant operation states the requirements to be met during operation of a nuclear power plant for assuring safety. Among various stages of authorization, regulatory body issues authorization for operation of a nuclear power plant, monitors and enforces regulatory requirements. The responsible organization shall have overall responsibility and the plant management shall have the primary responsibility for ensuring safe and efficient operation of its nuclear power plants. A set of codal requirements covering technical and administrative aspects are mandatory for the plant management to implement to ensure that the nuclear power plant is operated in accordance with the design intent. Requirements on operating procedures and instructions establish operation and maintenance, inspection and testing of the plant in a planned and systematic way. The requirements on emergency preparedness programme establish with a reasonable assurance that, in the event of an emergency situation, appropriate measures can be taken to mitigate the consequences. Commissioning requirements verify performance criteria during commissioning to ensure that the design intent and QA requirements are met. Several modifications in systems important to safety required during operation of a nuclear power plant are regulated. However new operational codal requirements arising out of periodic safety review, operational experience feedback, life management, probabilistic safety assessment, physical security, safety convention and obligations and decommissioning are not covered in the present code of practice for safety in nuclear power plant operation. Codal provisions on 'Review by operating organization on aspects of design having implications on operability' are also required to be addressed. The merits in developing such a methodology include acceptance of the design by operating organization, ensuring maintainability, proper layout etc. in the new designs

Dukovany nuclear power plant safety

International Nuclear Information System (INIS)

1999-01-01

Presentation covers recommended safety issues for the Dukovany NPP which have been solved with satisfactory conclusions. Safety issues concerned include: radiation safety; nuclear safety; security; emergency preparedness; health protection at work; fire protection; environmental protection; chemical safety; technical safety. Quality assurance programs at all stages on NPP life time is described. Report includes description of NPP staff training provision, training simulator, emergency operating procedures, emergency preparedness, Year 2000 problem, inspections and life time management. Description of Dukovany Plant Safety Analysis Projects including integrity of the equipment, modernisation, equipment innovation and safety upgrading program show that this approach corresponds to the actual practice applied in EU countries, and fulfilment of current IAEA requirements for safety enhancement of the WWER 440/213 units in the course of MORAWA Equipment Upgrading program

Lessons Learned in Protection of the Public for the Accident at the Fukushima Daiichi Nuclear Power Plant.

Science.gov (United States)

Callen, Jessica; Homma, Toshimitsu

2017-06-01

What insights can the accident at the Fukushima Daiichi nuclear power plant provide in the reality of decision making on actions to protect the public during a severe reactor and spent fuel pool emergency? In order to answer this question, and with the goal of limiting the consequences of any future emergencies at a nuclear power plant due to severe conditions, this paper presents the main actions taken in response to the emergency in the form of a timeline. The focus of this paper is those insights concerning the progression of an accident due to severe conditions at a light water reactor nuclear power plant that must be understood in order to protect the public.

New aspects in the radiological emergency plan outside the Nuclear power plant of Laguna Verde

International Nuclear Information System (INIS)

Alva L, S.

1991-01-01

The Mexican government through the National Commission of Nuclear Safety and Safeguards has imposed to the Federal Commission of Electricity to fulfill the requirement of having a functional Emergency Plan and under the limits that the regulator organisms in the world have proposed. The PERE (Plan of External Radiological Emergency) it has been created for the Nuclear Power station of Laguna Verde, Mexico

Plan for national nuclear emergency preparedness

International Nuclear Information System (INIS)

1992-06-01

The responsibility for Denmark's preparedness for nuclear emergencies lies with the Ministry of the Interior and the Civil Defense administration. The latter is particularly responsible for the presented plan which clarifies the organization and the measures to be taken in order to protect the public where, in the event of such an emergency, it could be in danger of radiation from radioactive materials. The main specifications of the plan, the activation of which covers the whole country, are that daily monitoring should be carried out so that warnings of nuclear accidents can be immediately conveyed to the relevant parties and that immediate action can be taken. These actions should result in the best possible protection against nuclear radiation so that acute and chronic damage to the health of members of the public can be restricted. The public, and relevant authorities should be informed of the situation and it should be attempted to regulate the reactions of individuals and of the society in general in such a way that damage to health, or social and economical conditions, can be restricted as much as possible. Denmark has not itself any atomic power plants, but some are located in neighbour countries and there are other sources such as nuclear research reactors, passing nuclear-driven ships etc. The detailed plan also covers possible sources of radiation, the nature of related damage to health, international cooperation, legal aspects, and a very detailed description of the overall administration and of the responsibilities of the organizations involved. (AB)

Reliability of diesel generators in the Finnish and Swedish nuclear power plants

International Nuclear Information System (INIS)

Pulkkinen, U.; Huovinen, T.; Norros, L.; Vanhala, J.

1989-10-01

Diesel generators are used as emergency AC-power sources in nuclear power plants and they produce electric power for other emergency systems during accidents in which offsite power is lost. The reliability of diesel generators is thus of major concern for overall safety of nuclear power plants. In this study we consider the reliability of diesel generators in the Swedish and Finnish nuclear power plants on the basis of collected operational experience. We classify the occurred failures according to their functional criticality, type and cause. The failures caused by human errors in maintenance and testing are analysed in detail. We analyse also the reliability of the diesel generator subsystems. Further, we study the effect of surveillance test and the type of test on the reliability. Finally we construct an unavailability model for single diesel generator unit and discuss the findings of the study giving some practical recommendations

Translocation of radiocesium from stems and leaves of plants and the effect on radiocesium concentrations in newly emerged plant tissues

International Nuclear Information System (INIS)

Tagami, Keiko; Uchida, Shigeo; Ishii, Nobuyoshi; Kagiya, Shigeo

2012-01-01

An accident occurred at the Fukushima Dai-ichi Nuclear Power Plant in March 2011 at which time large amounts of radionuclides were released into the atmosphere and the sea. In early May 2011, it was found that newly emerged tea (Camellia sinensis) leaves contained radiocesium, both 134 Cs and 137 Cs in some areas more than 300 km away from the Fukushima plant. To understand the mechanisms of radiocesium transfer to newly emerged tissues (shoots, leaves and fruits) of other plants in the future, radiocesium concentrations in newly emerged leaves of 14 plant species collected from the sampling areas in and near National Institute of Radiological Sciences in Chiba, Japan. The studied plant types were: (1) herbaceous plants, (2) woody plants with no old leaves at the time of the March accident, and (3) woody plants with old leaves out before the accident. About 40–50 d after the start of the accident, newly emerged leaves from woody plant with old leaves tended to show higher values than other woody or herbaceous plants. Concentrations of radiocesium in newly emerged tissues of trees decreased with time, but they did not decrease to the level of herbaceous plants. The type of the plant and presence of old leaves at the time of the heavy deposition period affected the radiocesium concentrations in newly emerged tissues.

Plant-specific evaluations of Transamerica Delaval diesel engines for nuclear service

International Nuclear Information System (INIS)

Dingee, D.A.; Laity, W.W.; Nesbitt, J.F.

1985-03-01

This paper discusses the approach taken to evlauate the readiness of Transamerica Delaval, Inc. (TDI) diesel generators for nuclear service at five power plants: Catawba, Comanche Peak, Grand Gulf, San Onofre, and Shoreham. TDI engines in these and other nuclear power plants have been the subject of a coordinated effort by 13 nuclear utilities to address reliability and quality issues. The utilities formed the TDI Diesel Generator Owners' Group and prepared a comprehensive plan for requalifying the engines as emergency power sources. Prior to full implementation of the plan by the Owners' Group and final review of the findings by the US Nuclear Regulatory Commission, several member plants became candidates for operating licenses. The TDI engines in those plants, including the five listed above, were evaluated on a case-by-case basis, taking into consideration the factors discussed in this paper. 2 refs

Ar-41 measurements and nuclear emergency preparedness

International Nuclear Information System (INIS)

Kunst, J.J.; Rodriguez, M.; Ugarte, R.; Vigile, R.S.; Boutet, L.I.; Jordan, O.D.; Hernandez, D.G.

2010-01-01

During the early phase of an emergency is necessary to confirm the release of radioactivity predictions made by the operator of the nuclear plant. In this context, it has begun measuring Ar-41 in the vicinity of a research reactor. Since the Ar-41 is produced in the reactor, it has been studied as a good way to validate the air dispersion model used in nuclear emergencies and to develop a method to improve the characterization of the release. For this latter purpose a pilot experiment was conducted to determine computational and experimental methods, the flux of 1.29 MeV of Ar-41 and compared to evaluate the accuracy of the assessments made. This paper describes meteorological forecasting systems used in the experiment, the estimate of the stability class and the concentration of nuclides using a calculation code developed by the ARN, as well as the methodology and equipment used for measurement in the field. (authors) [es

Management of Large Volumes of Waste Arising in a Nuclear or Radiological Emergency

International Nuclear Information System (INIS)

2017-10-01

This publication, prepared in light of the IAEA Action Plan on Nuclear Safety developed after the accident at the Fukushima Daiichi nuclear power plant, addresses the management of large volumes of radioactive waste arising in a nuclear or radiological emergency, as part of overall emergency preparedness. The management of large volumes of waste will be one of many efforts to be dealt with to allow recovery of affected areas, to support return of evacuated or relocated populations and preparations for normal social and economic activities, and/or to mitigate additional environmental impacts. The publication is intended to be of use to national planners and policy makers, facility and programme managers, and other professionals responsible for developing and implementing national plans and strategies to manage radioactive waste arising from nuclear or radiological emergencies.

Year 2000 problem impact on nuclear power plants

International Nuclear Information System (INIS)

Mauck, J.L.

1998-01-01

US Nuclear Regulatory commission began consideration of Year 2000 problem in nuclear power plants in 1996. It was found that no Year 2000 problem exists in safety related (reactor protection) instrumentation and control systems. Other important but not safety related systems needed for safe operation are impacted, namely security, emergency response data collection, radiation monitoring and control, surveillance tracking, control of feedwater, control rods, turbine as well as externals (communication, parts supply)

Nuclear Plant Integrated Outage Management

International Nuclear Information System (INIS)

Gerstberger, C. R.; Coulehan, R. J.; Tench, W. A.

1992-01-01

This paper is a discussion of an emerging concept for improving nuclear plant outage performance - integrated outage management. The paper begins with an explanation of what the concept encompasses, including a scope definition of the service and descriptions of the organization structure, various team functions, and vendor/customer relationships. The evolvement of traditional base scope services to the integrated outage concept is addressed and includes discussions on changing customer needs, shared risks, and a partnership approach to outages. Experiences with concept implementation from a single service in 1984 to the current volume of integrated outage management presented in this paper. We at Westinghouse believe that the operators of nuclear power plants will continue to be aggressively challenged in the next decade to improve the operating and financial performance of their units. More and more customers in the U. S. are looking towards integrated outage as the way to meet these challenges of the 1990s, an arrangement that is best implemented through a long-term partnering with a single-source supplier of high quality nuclear and turbine generator outage services. This availability, and other important parameters

Inadequacies of Belgium nuclear emergency plans: lessons from the Fukushima catastrophe have not been learned

International Nuclear Information System (INIS)

Boilley, David; Josset, Mylene

2015-01-01

After having outlined that some Belgium regional authorities made some statements showing that they did not learn lessons neither from the Chernobyl catastrophe, nor from the Fukushima accident, this report aims at examining whether Belgium is well prepared to face a severe nuclear accident occurring within its borders or in neighbouring countries, whether all hypotheses have actually been taken into account, and whether existing emergency plans are realistic. After a presentation of Belgium's situation regarding nuclear plants (Belgium plants and neighbouring French plants), the report presents the content and organisation of the nuclear emergency plan for the Belgium territory at the national, provincial and municipal levels. While outlining inadequacies and weaknesses of the Belgium plan regarding the addressed issues, it discusses the main lessons learned from the Fukushima accident in terms of emergency planning areas, of population sheltering, of iodine-based prophylaxis, of population evacuation, of food supply, of tools (measurement instruments) and human resources, and of public information. In the next parts, the report addresses and discusses trans-border issues, and the commitment of stakeholders

Demographic comparison of the Barsebaeck nuclear power plant with plants situated near large cities and national borders

International Nuclear Information System (INIS)

Walmod-Larsen, O.; Starcke, K.

1984-06-01

The Swedish-Danish Barsebaeck committee suggested in June 1983 that a demographic comparison of the Barsebaeck nuclear power plant be made with plants situated near other large cities and national borders. Sixteen other nuclear power plants: 13 in Western Europe, 2 in USA and 1 in Canada were chosen for the comparison. For five discrete distances out to 50 km, the population distributions have been found and compared. In addition the positions, related to the plants, of institutions, administrative centres, communication centres and other plants of public importance within the country or in neughbouring countries are described. Finally, the details of special agreements are given together with negotiations between neighbouring countries or internationally about nuclear power related matters. These include alarm and emergency procedures and agreements about liability in case of an accident in a neighbouring country. (author)

Nuclear power. Volume 1. Nuclear power plant design

International Nuclear Information System (INIS)

Pedersen, E.S.

1978-01-01

NUCLEAR POWER PLANT DESIGN is intended to be used as a working reference book for management, engineers and designers, and as a graduate-level text for engineering students. The book is designed to combine theory with practical nuclear power engineering and design experience, and to give the reader an up-to-date view of the status of nuclear power and a basic understanding of how nuclear power plants function. Volume 1 contains the following chapters; (1) nuclear reactor theory; (2) nuclear reactor design; (3) types of nuclear power plants; (4) licensing requirements; (5) shielding and personnel exposure; (6) containment and structural design; (7) main steam and turbine cycles; (8) plant electrical system; (9) plant instrumentation and control systems; (10) radioactive waste disposal (waste management) and (11) conclusion

Improved nuclear emergency management system reflecting lessons learned from the emergency response at Fukushima Daini Nuclear Power Station after the Great East Japan Earthquake

International Nuclear Information System (INIS)

Kawamura, Shinichi; Narabayashi, Tadashi

2016-01-01

Three nuclear reactors at Fukushima Daini Nuclear Power Station lost all their ultimate heat sinks owing to damage from the tsunami caused by the Great East Japan Earthquake on March 11, 2011. Water was injected into the reactors by alternate measures, damaged cooling systems were restored with promptly supplied substitute materials, and all the reactors were brought to a cold shutdown state within four days. Lessons learned from this experience were identified to improve emergency management, especially in the areas of strategic response planning, logistics, and functions supporting response activities continuing over a long period. It was found that continuous planning activities reflecting information from plant parameters and response action results were important, and that relevant functions in emergency response organizations should be integrated. Logistics were handled successfully but many difficulties were experienced. Therefore, their functions should be clearly established and improved by emergency response organizations. Supporting emergency responders in the aspects of their physical and mental conditions was important for sustaining continuous response. As a platform for improvement, the concept of the Incident Command System was applied for the first time to a nuclear emergency management system, with specific improvement ideas such as a phased approach in response planning and common operation pictures. (author)

Nuclear emergency preparedness in the Nordic and Baltic Sea countries

Energy Technology Data Exchange (ETDEWEB)

Jaworska, A. [Norwegian Radiation Protection Authority (Norway)

2002-07-01

Radiation emergency preparedness systems must be able to deal with the threats posed to each country and the region as a whole. The threats from nuclear accidents differ in the various countries of the region. The most serious nuclear threats are those with cross-border implications and are generally assumed to be due to the presence of nuclear reactors of various kinds. Some countries in the region, Finland, Germany, Lithuania, the Russian Federation and Sweden, have nuclear power plants, and several countries in the region possess smaller research reactors. Other nuclear threats arise from nuclear powered naval vessels or submarines, and from nuclear powered satellites. Production, transportation, use, and disposal of radioactive materials constitute potential local nuclear hazards. Finally, terrorist use of radioactive material poses a nuclear threat to all countries. (au)

Nuclear emergency preparedness in the Nordic and Baltic Sea countries

International Nuclear Information System (INIS)

Jaworska, A.

2002-01-01

Radiation emergency preparedness systems must be able to deal with the threats posed to each country and the region as a whole. The threats from nuclear accidents differ in the various countries of the region. The most serious nuclear threats are those with cross-border implications and are generally assumed to be due to the presence of nuclear reactors of various kinds. Some countries in the region, Finland, Germany, Lithuania, the Russian Federation and Sweden, have nuclear power plants, and several countries in the region possess smaller research reactors. Other nuclear threats arise from nuclear powered naval vessels or submarines, and from nuclear powered satellites. Production, transportation, use, and disposal of radioactive materials constitute potential local nuclear hazards. Finally, terrorist use of radioactive material poses a nuclear threat to all countries. (au)

More safety for emergency diesel engines for the Belgium nuclear power plants

International Nuclear Information System (INIS)

Laire, Ch.; Scauflaire, O.; D'ans, G.; Moland, G. de; Bresseleers, J.

2002-01-01

Each nuclear plant in Belgium is equipped with a series of ultimate power supply (UPS) units, also called emergency power units. These consist of generators driven by multi-cylinder (typically 18) diesel engines, which are marine derivatives. Unlike marine applications, the steady-state load does not produce pulsating torques. However, these diesel engines are designed to start upon short notice following a blackout and reach full power within a few seconds to guarantee the availability or all safety valves and ventilators. Such sharp and quasi-cold starts, periodically performed to guarantee the UPS availability, may spell utter failures of the crank shaft, as demonstrated by a fatigue failure observed on the fillets connecting the crank pin to the web faces. The fillet cracks initiate in bending mode and then progress in torsion mode to excessive transient torques arising in the power train during successive starts. Aware of the potential risk and conforming to the Belgian nuclear safety rules, the plant operator of Doel sponsored the development of a nondestructive technique enabling the inspection of each fillet for cracks without first removing each piston rod from its crank pin. As a result, Laborelec developed a specific eddy-current probe which avoids fully dismantling the engine, as is done during ten-yearly overhauls with dye-checks for cracks. Inspecting crank shaft fillet integrity with this least obtrusive technique requires 24 hours per engine. It can thus be performed more frequently to prevent total crank shaft failures in time and monitor the engine fatigue caused following the mandatory monthly start-up tests. This promising technique may also find marine applications. Measuring the transient torque arising between the engine and the generator showed that this reached very high values shortly after starting the engine and injecting fuel at full throttle to reach full power within seconds. The pulsating torque of the 18-cylinders engine occurring 9

Measures for reinforcing safety at the Ohma Nuclear Power Plant

International Nuclear Information System (INIS)

Ishikawa, Hiroyasu; Iwata, Kichisa; Koga, Kaoru

2013-01-01

Electric Power Development Co., Ltd. ('J-POWER') has been moving ahead with the Ohma Nuclear Power Project at Ohma-machi, Shimokita-gun in Aomori Prefecture and commenced the construction of an Advanced Boiling Water Reactor (ABWR) in May 2008. In light of the Fukushima Daiichi Nuclear Power Station Incident, J-POWER has undertaken an investigation of various measures for reinforcing safety at the Ohma nuclear power plant. These measures include a range of anti-tsunami measures, measures to ensure emergency power sources and ultimate heat removal functions, and responses for severe accidents. While consistently and properly reflecting the necessary measures, J-POWER will continue to ensure the creation of a safe power plant. J-POWER intends to appropriately reflect at all times new standards of technology established by the Nuclear Regulation Authority and makes concerted efforts to build a safe nuclear power plant in which the local community can have confidence. (author)

Participation of the ININ in the external radiological emergency plan of the Laguna Verde power plant

International Nuclear Information System (INIS)

Martinez S, R.; Cervini L, A.

1991-01-01

The planning of performances in radiological emergencies, with the object of reducing the consequences as much as possible on the population to accidental liberations of radioactive material coming from Nuclear power plant, it has been of main interest in the nuclear community in the world. In Mexico it has not been the exception, since with the setting in march of the Laguna Verde nuclear power plant exists an executive program of planning for emergencies that it outlines the activities to follow trending to mitigate the consequences that are derived of this emergency. As integral part of this program this the External Plan of Radiological Emergency (PERE) that covers the emergencies that could leave the frontiers of the Laguna Verde power plant. In the PERE it settles down the planning, address and control of the preparation activities, response and recovery in emergencies, as well as the organization and coordination of the institutions that participate. The National Institute of Nuclear Research (ININ), like integral part of these institutions in the PERE, has an infrastructure that it allows to participate in the plan in a direct way in the activities of 'Control of the radiological exhibition the response personnel and control of water and foods' and of support way and consultant ship in the activities of 'Monitoring, Classification and decontamination of having evaluated' and 'Specialized medical radiological attention'. At the moment the ININ has a radiological mobile unit and this conditioning a second mobile unit to carry out part of the activities before mentioned; also accounts with 48 properly qualified people that directly intervene in the plan. In order to guarantee an adequate response in the PERE an organization it has been structured like that of the annex as for the personnel, transport, team, procedures and communication system, with the objective always of guaranteeing the security and the population's health in emergency situations in the

Risk perception of the public living in vicinity of nuclear power plant

International Nuclear Information System (INIS)

Li Xiaojuan; Hou Changsong; Wang Chunyan; Liu Ying; Sun Quanfu; Yu Ningle; Li Ningning; Zhou Rihui; Zhuang Jiayi

2008-01-01

Objective: To investigate the attitude toward and perception of the risk of nuclear power plant among the public residing in vicinity of nuclear power plant, as well as the related factors. Methods: A face-to-face interview on perceived radiation risks was conducted among 1408 individuals in Liangyungang City, Jiangsu Province, where the Tianwan nuclear power plant was under construction. The four groups was defined according to the distance between the residence of the subjects and the Tianwan nuclear power plant: <4 km, 4- 8 km, 8-30 km and 30-50 km. A was used to collect information on education, working history, religion, perception of major industries hazards especially nuclear power plant, and major factors may influence their perceptions. Ordinal logistic regression model was used to analyze the data. Results: About 91.18% of the interviewee heard about the nuclear power plant, 35.36% of them had knowledge about Chernobyl nuclear power plant accident, 71.05% of them believed that the nuclear power plant had no negative effects on environments, 37.03% of them believed that the nuclear energy was safe, 74.27% of them believed that it was necessary for China to develop nuclear energy, 63.29% of them supported the construction of the nuclear power plant in local area. Ordinal logistic regression analysis revealed that the higher education, higher family annual income, male, economic benefits from the nuclear power plant construction, and trust in local government having competency to handling emergencies were positive factors; otherwise, impression on nuclear power plant of bad influences on environment and health were negative factors. An inverted U-shaped with a right tailing relationship between negative attitudes toward nuclear power plant and distance to the plant was found. Conclusions: Education, gender, family annual income and expectation of economic benefit returns were the major factors influencing the perception of and attitudes toward nuclear power

Importance of Promocat in nuclear emergency management in ANAV; Impacto del Promocat en la gestion de emergencias en ANAV

Energy Technology Data Exchange (ETDEWEB)

Gil Cortiella, R.; Torres Gurdel, C.

2016-08-01

The nuclear power plant emergency management tool PROMOCAT, has been developed for supporting and facilitating the nuclear emergency management in the Spanish NPPs of Asco and Vandellos II. PROMOCAT is a computerized tool that comprises all the activities made by the Technical Support Centre (TSC) and Offsite facilities. In order to ease the management and decision-making during a nuclear emergency. In addition, the drill mode helps to improve and strengthen emergency personnel training. (Author)

Different aspects of safety in Nuclear Fuel Plant at Pitesti, Romania

International Nuclear Information System (INIS)

Ivana, T.; Epure, Gh.

2009-01-01

Nuclear Fuel Plant (FCN) is a facility that produces fuel bundles of CANDU-6 type for the CANDU nuclear power plant. Only natural and depleted uranium in bulk and itemized form are present as nuclear materials in this facility. Uranium and wastes from the plant are handled, processed, treated and stored throughout the entire facility. The nuclear materials with natural and depleted uranium are entirely under nuclear safeguards. The amount of uranium present in the plant in different forms and activities together with zircaloy, beryllium and other hazardous substances, wastes, explosive materials at high temperatures, etc. lead to special measures undertaken by Nuclear Safety Department (DNS) to ensure nuclear safety. Different aspects of safety are continuously monitored in the plant: operational safety, industrial safety, radiological safety, labour safety, informational safety. The emergency preparedness and response, physical protection and the security of the plant and of the transportation of radioactive materials are contributing to cover the multitude of safety aspects. The safety culture of workers built directly on the safety components completes this activity in the plant. In addition the aspects of safety, security and safeguards are in permanent synergy, parts of the three components being included in each other. In the future the policy of FCN will be focused so that any improvement of one of the safety components will be reflected in improving the other safety aspects. (authors)

Exercises for radiological and nuclear emergency response. Planing - performance - evaluation

International Nuclear Information System (INIS)

Bayer, A.; Faleschini, J.; Goelling, K.; Stapel, R.; Strobl, C.

2010-01-01

The report of the study group emergency response seminar covers the following topics: (A) purpose of exercises and exercise culture: fundamentals and appliances for planning, performance and evaluation; (B) exercises in nuclear facilities; (C) exercises of national authorities and aid organizations on nuclear scenarios; exercises of national authorities and aid organizations on other radiological scenarios; (D) exercises in industrial plants, universities, medical facilities and medical services, and research institutes; (E) transnational exercises, international exercises; (F): exercises on public information.

Main lessons based on the Chernobyl nuclear power plant accident liquidation experience

International Nuclear Information System (INIS)

Vasil'chenko, V.N.; Nosovskij, A.V.

2006-01-01

The authors review the main lessons of the Chernobyl nuclear power plant accident and the liquidation of its consequences in the area of the nuclear reactors safety operation, any major accident management, liquidation accident consequences criteria, emergency procedures, preventative measures and treatment irradiated victims, the monitoring methods etc. The special emphasis is put on the questions of the emergency response and the antiaccidental measures planning in frame of international cooperation program

Emerging nuclear energy systems and nuclear weapon proliferation

International Nuclear Information System (INIS)

Gsponer, A.; Sahin, S.; Jasani, B.

1983-01-01

Generally when considering problems of proliferation of nuclear weapons, discussions are focused on horizontal proliferation. However, the emerging nuclear energy systems currently have an impact mainly on vertical proliferation. The paper indicates that technologies connected with emerging nuclear energy systems, such as fusion reactors and accelerators, enhance the knowledge of thermonuclear weapon physics and will enable production of military useful nuclear materials (including some rare elements). At present such technologies are enhancing the arsenal of the nuclear weapon states. But one should not forget the future implications for horizontal proliferation of nuclear weapons as some of the techniques will in the near future be within the technological and economic capabilities of non-nuclear weapon states. Some of these systems are not under any international control. (orig.) [de

The application of geographic information system to radiological and nuclear emergency monitoring

International Nuclear Information System (INIS)

Sadaniowski, I.V.; Rodriguez, M.; Rojas, C.A.; Jordan, O.D.

2010-01-01

The Geographic Information System (GIS) implementation for the preparation and response in case of to radiological and nuclear emergencies is being developed in the Emergency Control Center of the Argentina Nuclear Regulatory Authority, since many years ago. Additionals features have been incorporated such as integration with the results of radiological monitoring, improving and expanding its benefits both in the preparation stage and during the work of emergency response. This paper shows the specific application of GIS to radiological monitoring in case of emergency situations such as during the search of orphan sources and the characterization of geographic context around nuclear power plants and atomic centers. The GIS provides essential data cartographic for the monitoring with sophisticated detectors, to integrate with the information received with infrastructure, urban and rural population maps, physical features of the place, satellite images, etc. The monitoring results are analyzed and compared with relevant information for decision making during the response, like evacuation routes, affected population, security forces in the area, radiological characterization, application of protective actions, hospitals, schools, etc. These two integrated tools improve preparedness and response system in case of radiological or nuclear emergency. (authors) [es

Development of incident progress prediction technologies for nuclear emergency preparedness. Current status and future subjects

International Nuclear Information System (INIS)

Yoshida, Yoshitaka; Yamamoto, Yasunori; Kusunoki, Takayoshi; Kawasaki, Ikuo; Yanagi, Chihiro; Kinoshita, Ikuo; Iwasaki, Yoshito

2014-01-01

Nuclear licensees are required to maintain a prediction system during normal condition for using a nuclear emergency by the Basic Plan for Disaster Prevention of government. With prediction of the incident progress, if the present condition of nuclear power plant is understood appropriately and it grows more serious with keeping the present situation, it is in predicting what kind of situation will be occurred in the near future, choosing the effective countermeasures against the coming threat, and understanding the time available of intervention time. Following the accident on September 30 1999 in the nuclear fuel fabrication facility in Tokai Village of Ibaraki Prefecture, the Institute of Nuclear Safety System started development of incident progress prediction technologies for nuclear emergency preparedness. We have performed technical applications and made improvements in nuclear emergency exercises and verified the developed systems using the observed values of the Fukushima Daiichi Nuclear Power Plant accident. As a result, our developed Incident Progress Prediction System was applied to nuclear emergency exercises and we accumulated knowledge and experience by which we improved the system to make predictions more rapidly and more precisely, including for example, the development of a prediction method for leak size of reactor coolant. On the other hand, if a rapidly progressing incident occurs, since end users need simple and quick predictions about the public's protection and evacuation areas, we developed the Radioactive Materials Release, Radiation Dose and Radiological Protection Area Prediction System which changed solving an inverse problem into a forward problem solution. In view of the water-level-decline incident of the spent fuel storage facility at the Fukushima Daiichi Nuclear Power Plant, the spent fuel storage facility water level and the water temperature evaluation tool were improved. Such incident progress prediction technologies were

Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination

Directory of Open Access Journals (Sweden)

Dean Kyne

2016-07-01

Full Text Available Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

Emerging Environmental Justice Issues in Nuclear Power and Radioactive Contamination.

Science.gov (United States)

Kyne, Dean; Bolin, Bob

2016-07-12

Nuclear hazards, linked to both U.S. weapons programs and civilian nuclear power, pose substantial environment justice issues. Nuclear power plant (NPP) reactors produce low-level ionizing radiation, high level nuclear waste, and are subject to catastrophic contamination events. Justice concerns include plant locations and the large potentially exposed populations, as well as issues in siting, nuclear safety, and barriers to public participation. Other justice issues relate to extensive contamination in the U.S. nuclear weapons complex, and the mining and processing industries that have supported it. To approach the topic, first we discuss distributional justice issues of NPP sites in the U.S. and related procedural injustices in siting, operation, and emergency preparedness. Then we discuss justice concerns involving the U.S. nuclear weapons complex and the ways that uranium mining, processing, and weapons development have affected those living downwind, including a substantial American Indian population. Next we examine the problem of high-level nuclear waste and the risk implications of the lack of secure long-term storage. The handling and deposition of toxic nuclear wastes pose new transgenerational justice issues of unprecedented duration, in comparison to any other industry. Finally, we discuss the persistent risks of nuclear technologies and renewable energy alternatives.

Nuclear plants near borders: environmental, legal, economic and political aspects

International Nuclear Information System (INIS)

Carle, R.

1990-01-01

Over the last few years, the legal framework of the development of nuclear energy within Europe has focussed on the special problems posed by nuclear plants located near national boundaries. The problems which may be caused by such plants must clearly be handled in the same way as for any other installations and the governments concerned need to define mutually acceptable conditions. Joint committees have already been formed between some countries, most notably to deal with nuclear plant safety issues. Special agreements have been reached covering the use of river water, public information and mutual assistance in case of accident. The key to the whole process is a progressive standardization of regulations concerning the environment, safety, radiological protection, non-proliferation, public information and emergency plans in case of accidents. (UK)

Integrated Nuclear Recycle Plant

International Nuclear Information System (INIS)

Patodi, Anuj; Parashar, Abhishek; Samadhiya, Akshay K.; Ray, Saheli; Dey, Mitun; Singh, K.K.

2017-01-01

Nuclear Recycle Board (NRB), Tarapur proposes to set up an 'Integrated Nuclear Recycle Plant' at Tarapur. This will be located in the premises of BARC facilities. The project location is at coastal town of Tarapur, 130 Km north of Mumbai. Project area cover of INRP is around 80 hectares. The plant will be designed to process spent fuel received from Pressurized Heavy Water Reactors (PHWRs). This is the first large scale integrated plant of the country. INRP will process spent fuel obtained from indigenous nuclear power plants and perform left over nuclear waste disposal

Operating procedure automation to enhance safety of nuclear power plants

International Nuclear Information System (INIS)

Husseiny, A.A.; Sabri, Z.A.; Adams, S.K.; Rodriguez, R.J.; Packer, D.; Holmes, J.W.

1989-01-01

Use of logic statements and computer assist are explored as means for automation and improvement on design of operating procedures including those employed in abnormal and emergency situations. Operating procedures for downpower and loss of forced circulation are used for demonstration. Human-factors analysis is performed on generic emergency operating procedures for three strategies of control; manual, semi-automatic and automatic, using standard emergency operating procedures. Such preliminary analysis shows that automation of procedures is feasible provided that fault-tolerant software and hardware become available for design of the controllers. Recommendations are provided for tests to substantiate the promise of enhancement of plant safety. Adequate design of operating procedures through automation may alleviate several major operational problems of nuclear power plants. Also, automation of procedures is necessary for partial or overall automatic control of plants. Fully automatic operations are needed for space applications while supervised automation of land-based and offshore plants may become the thrust of new generation of nulcear power plants. (orig.)

Technical subsidies for the operation of IRD/CNEN emergency vehicles in the case of a nuclear accident at the Angra Nuclear Power Plant with associated radioactive releases to the atmosphere

International Nuclear Information System (INIS)

Leao, J.L.B.

1982-03-01

Technical support is provided for the operation of an emergency vehicle of Instituto de Radioprotecao e Dosimetria/Comissao Nacional de Energia Nuclear, Rio de Janeiro, Brazil, in the event of uncontrolled release of radioactivity from the Angra Nuclear Power Plant (NPP) to the atmosphere. It is based on internationally adopted emergency decision process philosophy, the concept of 'Protective Action Guide' (PAG), the exposure pathways relevant to nuclear accidents, the measuring systems to be used in obtaining the exposure rate in the effluent 'plume', the methods utilized to predict dose to the population, radioiodine suppression measures, the monitoring instrumentation available to the emergency group, some post-accident considerations and finally, the monitoring that may be carried out from an aircraft. Information is given about the NPP operator's responsabilities with respect to the prediction of the consequences of an accident, as well as methods for thyroid and whole body dose estimation based on exposure to the radioiodine and noble gases present in the effluent plume. The example of the Three Mile Island's incident is used to formulate some observations regarding collective dose to the public estimates derived from measurements made from a helicopter. (Author) [pt

Modernization of the WWER 440/230 nuclear power plant environmental protection system

Energy Technology Data Exchange (ETDEWEB)

Mikheev, N.V.; Kamenskaya, A.N.; Kulyukhin, S.A.; Novichenko, V.L.; Rumer, I.A. [Russian Academy of Sciences, Institute of Physical Chemistry, Moscow (Russian Federation); Antonov, B.V.; Kornienko, A.G.; Meshkov, V.M.; Rogov, M.F. [Rosenergoatom Concern, Moscow (Russian Federation)

2001-07-01

The papers reports a new approach to the problem of increasing environmental protection during severe accidents at WWER 440/230 nuclear power plants. The environmental protection system that we propose has three, not two protection levels, and can be introduced with minor modernization of the equipment available at WWER 440/230 nuclear power plants: 1. a jet-vortex condenser; 2. the sprinkler system; 3. a sorption module. The proposed modernization not only makes it possible to avoid emergency discharge of radioactive air and steam mix into the environment under any accident scenario, but also would substantially contribute to the safety of WWER 440/230 nuclear power plants. (author)

Resilience and Brittleness in a Nuclear Emergency Response Simulation: Focusing on Team Coordination Activity

International Nuclear Information System (INIS)

Costa, Wagner Schenkel; Buarque, Lia; Voshell, Martin; Branlat, Matthieu; Woods, David D.; Gomes, Jose Orlando

2008-01-01

The current work presents results from a cognitive task analysis (CTA) of a nuclear disaster simulation. Audio-visual records were collected from an emergency room team composed of individuals from 26 different agencies as they responded to multiple scenarios in a simulated nuclear disaster. This simulation was part of a national emergency response training activity for a nuclear power plant located in a developing country. The objectives of this paper are to describe sources of resilience and brittleness in these activities, identify cues of potential improvements for future emergency simulations, and leveraging the resilience of the emergency response System in case of a real disaster. Multiple CTA techniques were used to gain a better understanding of the cognitive dimensions of the activity and to identify team coordination and crisis management patterns that emerged from the simulation training. (authors)

Nuclear plant simulation using the Nuclear Plant Analyzer

International Nuclear Information System (INIS)

Beelman, R.J.; Laats, E.T.; Wagner, R.J.

1984-01-01

The Nuclear Plant Analyzer (NPA), a state-of-the-art computerized safety analysis and engineering tool, was employed to simulate nuclear plant response to an abnormal transient during a training exercise at the US Nuclear Regulatory Commission (USNRC) in Washington, DC. Information relative to plant status was taken from a computer animated color graphics display depicting the course of the transient and was transmitted to the NRC Operations Center in a manner identical to that employed during an actual event. Recommendations from the Operations Center were implemented during on-line, interactive execution of the RELAP5 reactor systems code through the NPA allowing a degree of flexibility in training exercises not realized previously. When the debriefing was conducted, the RELAP5 calculations were replayed by way of the color graphics display, adding a new dimension to the debriefing and greatly enhancing the critique of the exercise

Challenges to a Man-Machine Interface System in Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Jung, Yeon Sub [KHNP, Daejeon (Korea, Republic of)

2009-10-15

When the APR1400 project started nearly 20 years ago, advanced features such as intelligent alarms, computer-based procedures, and soft control technology were introduced. Although some of these technologies had been utilized in fossil plants, APR1400 opened a new horizon in MMIS for nuclear power plants. Currently, however, it appears that further challenges do not exist in the MMIS area. Engineers are simply busy in designing and constructing the next nuclear plant without exploiting the new features of MMIS. This paper explains newly emerging and feasible technology and suggests new ideas for MMIS compared with other industries.

Challenges to a Man-Machine Interface System in Nuclear Power Plants

International Nuclear Information System (INIS)

Jung, Yeon Sub

2009-01-01

When the APR1400 project started nearly 20 years ago, advanced features such as intelligent alarms, computer-based procedures, and soft control technology were introduced. Although some of these technologies had been utilized in fossil plants, APR1400 opened a new horizon in MMIS for nuclear power plants. Currently, however, it appears that further challenges do not exist in the MMIS area. Engineers are simply busy in designing and constructing the next nuclear plant without exploiting the new features of MMIS. This paper explains newly emerging and feasible technology and suggests new ideas for MMIS compared with other industries

Licensed bases management for advanced nuclear plants

International Nuclear Information System (INIS)

O'Connell, J.; Rumble, E.; Rodwell, E.

2001-01-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

Licensed bases management for advanced nuclear plants

Energy Technology Data Exchange (ETDEWEB)

O' Connell, J [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E; Rodwell, E [EPRI, Palo Alto, CA (United States)

2001-07-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

Nuclear power plant outages

International Nuclear Information System (INIS)

1998-01-01

The Finnish Radiation and Nuclear Safety Authority (STUK) controls nuclear power plant safety in Finland. In addition to controlling the design, construction and operation of nuclear power plants, STUK also controls refuelling and repair outages at the plants. According to section 9 of the Nuclear Energy Act (990/87), it shall be the licence-holder's obligation to ensure the safety of the use of nuclear energy. Requirements applicable to the licence-holder as regards the assurance of outage safety are presented in this guide. STUK's regulatory control activities pertaining to outages are also described

The innovative simulator for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Kurosawa, A [The Inst. of Applied Energy, Tokyo (Japan); Ohashi, H; Akiyama, M [Univ. of Tokyo (Japan). Dept. of Nuclear Engineering

1994-12-31

Nuclear power simulators are becoming more and more important tools for ensuring the safety and the reliability during the whole cycle of plants from design to operation. Recently, there has been remarkable progress in computer science such as increase of computing speed, refinement of mathematical models and emergence of various AI technologies. By fully exploiting this progress to nuclear plant simulators, it becomes possible to achieve much faster, more extensive and more realistic simulation than ever. The Institute of Applied Energy (IAE) has organized a feasibility study on the advanced simulator since 1990, to develop the concept of nuclear power plant simulators in future. In this study, several academic organizations make fundamental researches on parallelization of transient analyses, large-scale parallel computing, thermal-hydraulic analysis using cellular automata, code development methodology by module-integration and task scheduling methods for parallel compilers. The concept and impact of the innovative simulator, as a multipurpose simulator complex, are summarized from the viewpoints of wide range scenarios including severe accidents, 3D multi-media interface, much faster than real-time simulation, and innovative algorithms for analyses of thermal-hydraulics, structure, neutronkinetics and their coupled phenomena. (orig.) (2 refs., 2 figs.).

The innovative simulator for nuclear power plants

International Nuclear Information System (INIS)

Kurosawa, A.; Ohashi, H.; Akiyama, M.

1994-01-01

Nuclear power simulators are becoming more and more important tools for ensuring the safety and the reliability during the whole cycle of plants from design to operation. Recently, there has been remarkable progress in computer science such as increase of computing speed, refinement of mathematical models and emergence of various AI technologies. By fully exploiting this progress to nuclear plant simulators, it becomes possible to achieve much faster, more extensive and more realistic simulation than ever. The Institute of Applied Energy (IAE) has organized a feasibility study on the advanced simulator since 1990, to develop the concept of nuclear power plant simulators in future. In this study, several academic organizations make fundamental researches on parallelization of transient analyses, large-scale parallel computing, thermal-hydraulic analysis using cellular automata, code development methodology by module-integration and task scheduling methods for parallel compilers. The concept and impact of the innovative simulator, as a multipurpose simulator complex, are summarized from the viewpoints of wide range scenarios including severe accidents, 3D multi-media interface, much faster than real-time simulation, and innovative algorithms for analyses of thermal-hydraulics, structure, neutronkinetics and their coupled phenomena. (orig.) (2 refs., 2 figs.)

The Fukushima Daiichi Nuclear Power Plant Accident: OECD/NEA Nuclear Safety Response and Lessons Learnt

International Nuclear Information System (INIS)

2013-01-01

Following the March 2011 accident at the Fukushima Daiichi nuclear power plant, all NEA member countries took early action to ensure and confirm the continued safety of their nuclear power plants and the protection of the public. After these preliminary safety reviews, all countries with nuclear facilities carried out comprehensive safety reviews, often referred to as 'stress tests', which reassessed safety margins of nuclear facilities with a primary focus on challenges related to conditions experienced at the Fukushima Daiichi nuclear power plant, for example extreme external events and the loss of safety functions, or capabilities to cope with severe accidents. As appropriate, improvements are being made to safety and emergency response systems to ensure that nuclear power plants are capable of withstanding events that lead to loss of electrical power and/or cooling capability. In the weeks following the accident, the NEA immediately began establishing expert groups in the nuclear safety and radiological protection areas, as well as contributing to information exchange with the Japanese authorities and other international organisations. It promptly provided a forum for high-level decision makers and regulators within the G8-G20 frameworks. The NEA actions taken at the international level in response to the accident have been carried out primarily by the three NEA standing technical committees concerned with nuclear and radiation safety issues - the Committee on Nuclear Regulatory Activities (CNRA), the Committee on the Safety of Nuclear Installations (CSNI) and the Committee on Radiation Protection and Public Health (CRPPH) - under the leadership of the CNRA. More than two years following the accident, the NEA continues to assist the Japanese authorities in dealing with their nuclear safety and recovery efforts as well as to facilitate international co-operation on nuclear safety and radiological protection matters. It is strongly supporting the establishment of

Development of life evaluation technology for nuclear power plant components

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Jin [Sungkyunkwan Univ., Seoul (Korea, Republic of); Kwon, J. D. [Yeungnam Univ., Gyeongsan (Korea, Republic of); Kang, K. J. [Chonnam National Univ., Gwangju (Korea, Republic of)] (and others)

2001-03-15

This research focuses on development of reliable life evaluation technology for nuclear power plant (NPP) components, and is divided into two parts, development of life evaluation systems for pressurized components and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered: development of expert systems for integrity assessment of pressurized components, development of integrity evaluation systems of steam generator tubes, prediction of failure probability for NPP components based on probabilistic fracture mechanics, development of fatigue damage evaluation technique for plant life extension, domestic round robin analysis for pressurized thermal shock of reactor vessels, domestic round robin analysis of constructing P--T limit curves for reactor vessels, and development of data base for integrity assessment. For evaluation of applicability of emerging technology to operating plants, on the other hand, the following eight topics are covered: applicability of the Leak-Before-Break analysis to Cast S/S piping, collection of aged material tensile and toughness data for aged Cast S/S piping, finite element analyses for load carrying capacity of corroded pipes, development of Risk-based ISI methodology for nuclear piping, collection of toughness data for integrity assessment of bi-metallic joints, applicability of the Master curve concept to reactor vessel integrity assessment, measurement of dynamic fracture toughness, and provision of information related to regulation and plant life extension issues.

The link between off-site-emergency planning and plant-internal accident management

Energy Technology Data Exchange (ETDEWEB)

Braun, H.; Goertz, R.

1995-02-01

A variety of accident management measures has been developed and implemented in the German nuclear power plants. They constitute a fourth level of safety in the defence-in-depth concept. The containment venting system is an important example. A functioning link with well defined lines of communication between plant-internal accident management and off-site disaster emergency planning has been established.

Development of life evaluation technology for nuclear power plant components

Energy Technology Data Exchange (ETDEWEB)

Kim, Young Jin; Kim, Yun Jae; Choi, Jae Boong [Sungkyunkwan Univ., Seoul (Korea, Republic of)] (and others)

2002-03-15

This project focuses on developing reliable life evaluation technology for nuclear power plant components, and is divided into two parts, development of a life evaluation system for nuclear pressure vessels and evaluation of applicability of emerging technology to operating plants. For the development of life evaluation system for nuclear pressure vessels, the following seven topics are covered in this project: defect assessment method for steam generator tubes, development of fatigue monitoring system, assessment of corroded pipes, domestic round robin analysis for constructing P-T limit curve for RPV, development of probabilistic integrity assessment technique, effect of aging on strength of dissimilar welds, applicability of LBB to cast stainless steel, and development of probabilistic piping fracture mechanics.

COOLING WATER ISSUES AND OPPORTUNITIES AT U.S. NUCLEAR POWER PLANTS

International Nuclear Information System (INIS)

Vine, Gary

2010-01-01

This report has been prepared for the Department of Energy, Office of Nuclear Energy (DOE-NE), for the purpose of providing a status report on the challenges and opportunities facing the U.S. commercial nuclear energy industry in the area of plant cooling water supply. The report was prompted in part by recent Second Circuit and Supreme Court decisions regarding cooling water system designs at existing thermo-electric power generating facilities in the U.S. (primarily fossil and nuclear plants). At issue in the courts have been Environmental Protection Agency regulations that define what constitutes 'Best Technology Available' for intake structures that withdraw cooling water that is used to transfer and reject heat from the plant's steam turbine via cooling water systems, while minimizing environmental impacts on aquatic life in nearby water bodies used to supply that cooling water. The report was also prompted by a growing recognition that cooling water availability and societal use conflicts are emerging as strategic energy and environmental issues, and that research and development (R and D) solutions to emerging water shortage issues are needed. In particular, cooling water availability is an important consideration in siting decisions for new nuclear power plants, and is an under-acknowledged issue in evaluating the pros and cons of retrofitting cooling towers at existing nuclear plants. Because of the significant ongoing research on water issues already being performed by industry, the national laboratories and other entities, this report relies heavily on ongoing work. In particular, this report has relied on collaboration with the Electric Power Research Institute (EPRI), including its recent work in the area of EPA regulations governing intake structures in thermoelectric cooling water systems.

Managing aging in nuclear power plants: Insights from NRC maintenance team inspection reports

Energy Technology Data Exchange (ETDEWEB)

Fresco, A.; Subudhi, M.; Gunther, W.; Grove, E.; Taylor, J. [Brookhaven National Lab., Upton, NY (United States)

1993-12-01

A plant`s maintenance program is the principal vehicle through which age-related degradation is managed. From 1988 to 1991, the NRC evaluated the maintenance program of every nuclear power plant in the United States. Forty-four out of a total of 67 of the reports issued on these in-depth team inspections were reviewed for insights into the strengths and weaknesses of the programs as related to the need to understand and manage the effects of aging on nuclear plant systems, structures, and components. Relevant information was extracted from these inspection reports and sorted into several categories, including Specific Aging Insights, Preventive Maintenance, Predictive Maintenance and Condition Monitoring, Post Maintenance Testing, Failure Trending, Root Cause Analysis and Usage of Probabilistic Risk Assessment in the Maintenance Process. Specific examples of inspection and monitoring techniques successfully used by utilities to detect degradation due to aging have been identified. The information also was sorted according to systems and components, including: Auxiliary Feedwater, Main Feedwater, High Pressure Injection for both BWRs and PWRs, Service Water, Instrument Air, and Emergency Diesel Generator Air Start Systems, and Emergency Diesel Generators Air Start Systems, emergency diesel generators, electrical components such as switchgear, breakers, relays, and motor control centers, motor operated valves and check valves. This information was compared to insights gained from the Nuclear Plant Aging Research (NPAR) Program. Attributes of plant maintenance programs where the NRC inspectors felt that improvement was needed to properly address the aging issue also are discussed.

The role of industrial-sanitary laboratory of medical aid station of Federal administration in prophylaxis of emergency situations at the plants of nuclear-energy complex and liquidation of their after-effects

International Nuclear Information System (INIS)

Antipin, E.B.

1995-01-01

On the example of several radiation accidents the author summarized the personal practical experience in organization of work in industrial-sanitary laboratories based at the nuclear energy plants of nuclear-energy complex, in respect of prophylaxis of emergency radiation situations and liquidation of their after-effects. It is pointed out that successful activity in rendering emergency medical aid in emergency situations, caused by radiation accidents, is possible only subject to close contact of science, practical medical care and sanitary service which should become a part of the uniform public health system. 4 refs

Nuclear emergency preparedness: national organisation

Energy Technology Data Exchange (ETDEWEB)

El Messaoudi, M.; Essadki, H.; Lferde, M.; Moutia, Z. [Faculte des Sciences, Dept. de Physique, Rabat (Morocco)

2006-07-01

As in all other industries, the nuclear facilities can be the object of accidents whose consequences go beyond the limits of their site and consequently radioactive releases would be issued in the environment justifying the protection measures of population. Even if all the precautions were taken during the stages from the design to the operation, to reduce the risk of accident in nuclear installations, this risk can not be completely suppressed. For the radiological risk, as for the other major risks, the protection of the public always was taken in consideration by public power. The nuclear emergency plan gives the opportunity to have a quick appropriate reaction to a sudden event, which has (or might have) direct consequences for the population. The Moroccan public authorities had proceeded to reinforce at the national level, the control of nuclear safety and protection against radiation by the set up of a new nuclear safety authority. Evidently, the organization and the management of a nuclear and/or radiological emergency were at centre of this reform. Taking into account the subjective risk of radiological terrorism, the authorities should reinforce measurements guaranteeing radiological safety and security, and elaborate the appropriate emergency plans. The aim of this paper is to give a progress report on nuclear emergency plan aspects and to present a corresponding organization which could be applied by national authority. (authors)

Nuclear emergency preparedness: national organisation

International Nuclear Information System (INIS)

El Messaoudi, M.; Essadki, H.; Lferde, M.; Moutia, Z.

2006-01-01

As in all other industries, the nuclear facilities can be the object of accidents whose consequences go beyond the limits of their site and consequently radioactive releases would be issued in the environment justifying the protection measures of population. Even if all the precautions were taken during the stages from the design to the operation, to reduce the risk of accident in nuclear installations, this risk can not be completely suppressed. For the radiological risk, as for the other major risks, the protection of the public always was taken in consideration by public power. The nuclear emergency plan gives the opportunity to have a quick appropriate reaction to a sudden event, which has (or might have) direct consequences for the population. The Moroccan public authorities had proceeded to reinforce at the national level, the control of nuclear safety and protection against radiation by the set up of a new nuclear safety authority. Evidently, the organization and the management of a nuclear and/or radiological emergency were at centre of this reform. Taking into account the subjective risk of radiological terrorism, the authorities should reinforce measurements guaranteeing radiological safety and security, and elaborate the appropriate emergency plans. The aim of this paper is to give a progress report on nuclear emergency plan aspects and to present a corresponding organization which could be applied by national authority. (authors)

Medical rescue for nuclear or radiologic emergencies

International Nuclear Information System (INIS)

Chen Xiaohua; Nie Suifeng

2011-01-01

Nuclear or radiologic emergencies are defined as incidents that are caused by radioactive substance or by other sources of radiation and can pose a serious hazard to public health. In case of nuclear or radiologic emergencies, radioactive rays will damage the human body and bring about psychological and mental stress, resulting in a series of social psychological effects. The key to medical rescue for nuclear or radiologic emergencies is to take effective measures which can minimize the body harm resulting from nuclear or radiologic emergencies and maintain social stability. This article reviews the personnel protection, on-the-spot salvage, treatments of various harm, and prevention of public psychological effect following nuclear or radiologic emergencies. (authors)

Complex nuclear safety evaluation of the Bohunice V-1 nuclear power plant

International Nuclear Information System (INIS)

Kriz, Z.

1991-01-01

The safety concept of V-230 type reactor units dates back to the late 1960s. The units fail to be sufficiently dimensioned for emergency cooling of the reactor core and are fitted with no containment. So far, operating experience is good. The availability factor is 71.5% for unit 1 and 77.8% for unit 2. There occur 1 to 3 unscheduled shutdowns annually. The quality of steam generator tubes is very good. A complex safety assessment of the plant was accomplished in 1990. It concerned the concept and criteria of safety assessment, the earthquake situation, the condition of the primary coolant circuit equipment, the control system, the effect of the human factor, and preparedness of emergency plans. OSART and ASSET missions were accomplished at the plant. Based on the results of the missions as well as of inspections by the State Surveillance over Nuclear Safety, the decision has been adopted to operate the plant not longer than till 1995; the further fate of the plant will be decided on according to a future technical and economic analysis. (M.D.)

Recommended criteria for the evaluation of on-site nuclear power plant emergency exercises

International Nuclear Information System (INIS)

Lafortune, J.F.

1997-01-01

A review of existing Canadian and International emergency exercise evaluation criteria and approaches has been conducted. Based on the results of the review, criteria are proposed for the evaluation of on-site emergency exercises for Canadian nuclear power stations. The proposed criteria are performance-based. They are comprehensive, yet remain adaptable to all stations and accident scenarios. They are primarily aimed at radiological emergency exercises, but are entirely applicable to fire or other conventional exercises. This report also addresses evaluation preparation and methodology. (author). 21 refs., 6 tabs

Technical report on dc power supplies in nuclear power plants

International Nuclear Information System (INIS)

1977-06-01

Emergency electrical power supplies, both a.c. and d.c. for nuclear power plants are important to safety. For this reason, the electric power systems for operating nuclear plants and those plants under licensing review have been required to provide a high degree of reliability. It is this high reliability that provides confidence that sufficient safety margin exists against loss of all d.c. power for extended periods of time to allow an orderly examination of safety issues, such as this. However, because of the importance of the a.c. and d.c. power systems, the staff has been expending effort to review the reliability of these systems and shall continue to do so in the future

Practices and Experience in Stakeholder Involvement for Post-nuclear Emergency Management - Summary of the workshop

International Nuclear Information System (INIS)

Anon.

2011-01-01

One of the most important aspects of post-accident consequence management is the involvement of stakeholders: in the planning, preparation and execution as well as in sustaining efforts over the long term. Having recognised the significance of stakeholder participation in several International Nuclear Emergency Exercises (INEX), the NEA Committee on Radiation Protection and Public Health (CRPPH) decided to organise the Practices and Experience in Stakeholder Involvement for Post-nuclear Emergency Management Workshop to explore these issues. This summary highlights the key issues discussed during the workshop, which brought together 75 emergency management and communication specialists from 16 countries. In light of the accident at the Fukushima Daiichi nuclear power plant, the experience shared during this workshop will be central to further improving national emergency management arrangements

Environmental monitoring program for radiological emergencies at the Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro, Brazil

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

1997-12-31

In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra do Reis, Rio de Janeiro, the Emergency Response Team of the Institute of Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. A monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measure in case of a radiological accident is presented. For the selection of the monitoring points, the program takes into account atmospheric diffusion, population conglomerates and their habits, water and land use; it includes the entire Emergency Planning Zone of 15 km radius. The program has been organized in the form of a handbook to facilitate handling by field teams 2 refs., 1 fig.; e-mail: lilia at ird.gov.br

Development of Emergency Operating Strategies for Beyond Design Basis External Event(BDBEE)s in Korean WH Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Yoon, Duk-Joo; Lee, Seung-Chan; Sung, Je-Joong; Ha, Sang-Jun [KHNP CRI, Daejeon (Korea, Republic of); Hong, Soon-Joon; Hwang, Su-Hyun; Lee, Byung-Chul; Park, Kang-Min [FNC Tech. Co., Yongin (Korea, Republic of)

2015-10-15

Westinghouse developed and connected emergency operating procedures into a set of FLEX Support Guidelines(FSGs). This paper explains that Korean WH(Westinghouse) type nuclear power plants develop emergency operating strategies for ELAP(extended loss of all AC power), which include guidelines to use permanent and portable equipment as necessary to prevent core damage until AC power is restored from a reliable alternate source of AC power. The Korean emergency operating response strategies were developed to cope with a ELAP such as Fukushima event. The strategies include guidelines to prevent fuel damage using the FLEX equipment. Operators should take actions to prepare FLEX equipment within license basis SBO coping time. The loss of all AC power has been analyzed to identify the behavior of major NSSS process variables using RELAP computer code. The accident analysis showed that the plant does not result in fuel damage in 72 hours after an ELAP if operators take actions to cool RCS with opening of SG ADV in 5 gpm seal leak case. In this scenario, because ELAP is in process and all power cannot be used, operator should operate the FLEX equipment in order to actuate active equipment using the EOP fo SBO response. This strategy will prevent entering SAMG because this actions result in core cooling and stay in core exit temperature less than 650 .deg. C. Korean emergency operating guidelines(EOGs) will be developed using this strategies for response to the BDBEE.

Development of on-line operator aid system (OASYSTM) for nuclear power plants

International Nuclear Information System (INIS)

Kang, Ki Sig; Choi, Seong Soo; Kim, Han Gon; Chang, Soon Heung; Jeong, Hee Kyo; Yi, Chul Un

1994-01-01

In this paper, the development of On - line operator Aid SYStem (OASYS TM ) are discussed by focusing attention on the importance of the operator's role for nuclear power plants. The OASYS TM is under development to support the operator's decision making process and to enhance the safety of a nuclear power plant by providing the plant operators with timely and proper guideline during abnormal and emergency conditions. The OASYS TM has capabilities for the signal validation/management, the alarm processing, the failure diagnosis using abnormal operating procedures, and the dynamic tracking of emergency operating procedures using function restoration guidelines and optimal recovery guidelines with a series of complex logic steps covering a broad spectrum of event sequences. The proposed system is being implemented on a SUN-4/75 Workstation using C and Quintus TM prolog language. For verification studies a full-scope real-time simulator is being used. Test results show that the OASYS TM is capable of diagnosing a plant failure quickly and providing an operator guideline with fast response time. After verification the OASYS TM will be installed in the simulator II of Kori nuclear training center

GIS Application in Atucha I Nuclear Power Plant Exercise Argentina, 2007

International Nuclear Information System (INIS)

Sadaniowski, I.V.; Telleria, D.M.; Jordan, O.D.; Boutet, L.I.; Kunst, J.J.; Bruno, H.A.; Hernandez, D.G.; Rodriguez, M.; Cateriano, M.A.; Rey, H.L.

2011-01-01

Geographic Information Systems (GIS) are tools applied to assist in the assessment and solution of many geographical related issues. Recently, their applications have been extended to the areas of disasters and environmental emergencies. GIS not only could be used as a diagnostic tool. Combined with adequate information and other tools capable to predict the transfer of pollutants in the environment and the associated impacts to the public, GIS could be used to support emergency planning and response. The Nuclear Regulatory Authority (NRA) of Argentina has incorporated in 2003 the GIS technology like an innovative resource for its preparation and response activities in emergencies. For this, the NRA acquired the necessary technology (hardware and software) and the technical specialist who were joined to expert's team in the nuclear and radiological emergencies field. The GIS stays operative as support tool in the Emergencies Control Center of NRA. In this paper, the use of GIS as a tool for analysis and advice is presented. The GIS is being used for preparation and development of nuclear emergencies trials and exercises, carried out on-site and off-site at the Nuclear Power Plant Atucha I Buenos Aires, Argentina, in cooperation with civil defense, national and state security and army forces and intensive public involvement. The databases were conformed with information from different sources, including the result of interviews to different actors, as well as other local and national government agencies and forces. Also, educational institutions, local medical centers, etc., were consulted. The information was enriched with outings to field in the surroundings of nuclear power plant. The scope and the detail of the information for this exercise covers 30 kilometers surroundings the nuclear power plant, with a range of significantly different geographical and population conditions. When loading the information in the GIS, a classification scheme is applied and

GIS application in Atucha I nuclear power plant exercise Argentina, 2007

International Nuclear Information System (INIS)

Sadaniowski, Ivana; Jordan, Osvaldo; Boutet, Luis; Kunst, Juan; Bruno, Hector; Hernandez, Daniel; Rodriguez, Monica; Cateriano, Miguel; Rey, Hugo; Telleria, Diego

2008-01-01

Full text: Geographic Information Systems (GIS) are tools applied to assist in the assessment and solution of many geographical related issues. Recently, their applications have been extended to the areas of disasters and environmental emergencies. GIS not only could be used as a diagnostic tool. Combined with adequate information and other tools capable to predict the transfer of pollutants in the environment and the associated impacts to the public, GIS could be used to support emergency planning and response. The Nuclear Regulatory Authority (NRA) of Argentina has incorporated in 2003 the GIS technology like an innovative resource for its preparation and response activities in emergencies. For this, the NRA acquired the necessary technology (hardware and software) and the technical specialist who were joined to expert's team in the nuclear and radiological emergencies field. The GIS stays operative as support tool in the Emergencies Control Center of NRA. In this paper, the use of GIS as a tool for analysis and advice is presented. The GIS is being used for preparation and development of nuclear emergencies trials and exercises, carried out on-site and off-site at the Nuclear Power Plant Atucha I Buenos Aires, Argentina, in cooperation with civil defense, national and state security and army forces and intensive public involvement. The databases were conformed with information from different sources, including the result of interviews to different actors, as well as other local and national government agencies and forces. Also, educational institutions, local medical centers, etc., were consulted. The information was enriched with outings to field in the surroundings of nuclear power plant. The scope and the detail of the information for this exercise covers 30 kilometers surroundings the nuclear power plant, with a range of significantly different geographical and population conditions. When loading the information in the GIS, a classification scheme is applied

Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme, Training Materials

International Nuclear Information System (INIS)

2013-01-01

The aim of these training materials is to provide a practical tool for emergency planning for a State embarking on a nuclear power programme, and to fulfil, in part, functions assigned to the IAEA under the Convention on Assistance in the Case of a Nuclear Accident or Radiological Emergency (the Assistance Convention). Under Article 5.a(ii) of the Assistance Convention, one function of the IAEA is to collect and disseminate to States Parties and Member States information concerning methodologies, techniques and available results of research relating to such emergencies. One of the concerns associated with nuclear power is the possibility that a State embarking on a nuclear power programme might not have sufficient capabilities and therefore would not be adequately prepared to respond to a radiation emergency caused by severe accident conditions. Protecting the public, the environment and property in the event of a failure of any level of defence in depth is the most important safety objective. A robust framework for emergency preparedness and response to a radiation emergency forms the last level of defence in depth and, as such, must be developed and implemented by any State embarking on a nuclear power programme, using best international practices. The establishment of capabilities and arrangements for emergency preparedness and response to severe accident conditions is one of the principal tasks in the development of a national infrastructure for nuclear power. State of the art emergency preparedness and response is a key element in achieving overall plant safety. This training course complements the IAEA publication 'Considerations in Emergency Preparedness and Response for a State Embarking on a Nuclear Power Programme' (EPR-Embarking 2012). These materials are designed to help States apply the guidance in EPR-Embarking 2012, in order to develop the capability to adequately prepare for and respond to a radiation emergency after the commissioning and start of

Design data and safety features of commerical nuclear power plant

International Nuclear Information System (INIS)

Heddleson, F.A.

1976-06-01

Design data, safety features, and site characteristics are summarized for 34 nuclear power units in 17 power stations in the United States. Six pages of data are presented for each plant, consisting of thermal-hydraulic and nuclear factors, containment features, emergency-core-cooling systems, site features, circulating water system data, and miscellaneous factors. An aerial perspective is also presented for each plant. This volume covers Light Water Reactors (LWRs) with dockets 50-508 through 50-549, four HTGRs--50-171, 50-267, 50-450/451, 50-463/464, the Atlantic Floating Station 50-477/478, and the Clinch River Breeder 50-537

Nuclear power plant siting

International Nuclear Information System (INIS)

Sulkiewicz, M.; Navratil, J.

The construction of a nuclear power plant is conditioned on territorial requirements and is accompanied by the disturbance of the environment, land occupation, population migration, the emission of radioactive wastes, thermal pollution, etc. On the other hand, a nuclear power plant makes possible the introduction of district heating and increases the economic and civilization activity of the population. Due to the construction of a nuclear power plant the set limits of negative impacts must not be exceeded. The locality should be selected such as to reduce the unfavourable effects of the plant and to fully use its benefits. The decision on the siting of the nuclear power plant is preceded by the processing of a number of surveys and a wide range of documentation to which the given criteria are strictly applied. (B.H.)

Survey the of building and dietary structure of local residents around Yangjiang and Hongyanhe nuclear power plants

International Nuclear Information System (INIS)

Qian Yekan; Lei Cuiping; Sun Quanfu; Fan Yaohua; Huang Zhibiao; Cui Yong

2011-01-01

Objective: To provide a guide in the course of the daily operation and accident emergency response. Methods: The survey was conducted with questionnaires among heads of households collected by stratified radom sampling. The head of a household was asked about residential type and structure, the sources of drinking water, milk, type and frequency of main vegetables. Results: Two-storied and more than two-storied houses were dominant around Yangjiang nuclear power plant, single-storey houses and tile-roofed houses were dominant around Hongyanhe nuclear power plant. The top three of wall construction materials around the two nuclear power plants were orderly brick, stone and beton. Glass window shelters were in the majority. Drinking water of residents was mainly from wells and waterworks. Milk comes from nonlocal packaged products. The top five high frequency vegetables the residents around Yangjiang nuclear power plants eat were orderly cabbage, zucchini, string beans, tong dish, cucumber, and those around Yangjiang nuclear power plant were orderly chinese cabbage, leek, celery, cabbage, spinach. Conclusion: Building and dietary structure around Yangjiang and Hongyanhe nuclear power plants are incongruence. Government can make decisions to collect foods for nuclides monitoring according to building and dietary structure baseline data, and take emergency measures to direct nuclear safety radiation protection for residents when nuclear accident takes place. (authors)

Multiple external hazards compound level 3 PSA methods research of nuclear power plant

Science.gov (United States)

Wang, Handing; Liang, Xiaoyu; Zhang, Xiaoming; Yang, Jianfeng; Liu, Weidong; Lei, Dina

2017-01-01

2011 Fukushima nuclear power plant severe accident was caused by both earthquake and tsunami, which results in large amount of radioactive nuclides release. That accident has caused the radioactive contamination on the surrounding environment. Although this accident probability is extremely small, once such an accident happens that is likely to release a lot of radioactive materials into the environment, and cause radiation contamination. Therefore, studying accidents consequences is important and essential to improve nuclear power plant design and management. Level 3 PSA methods of nuclear power plant can be used to analyze radiological consequences, and quantify risk to the public health effects around nuclear power plants. Based on multiple external hazards compound level 3 PSA methods studies of nuclear power plant, and the description of the multiple external hazards compound level 3 PSA technology roadmap and important technical elements, as well as taking a coastal nuclear power plant as the reference site, we analyzed the impact of off-site consequences of nuclear power plant severe accidents caused by multiple external hazards. At last we discussed the impact of off-site consequences probabilistic risk studies and its applications under multiple external hazards compound conditions, and explained feasibility and reasonableness of emergency plans implementation.

Maintenance management of emergency power supply equipment (uninterruptible power supply) in Tokai reprocessing plant

International Nuclear Information System (INIS)

Nishida, Kyosuke; Hiyama, Hisao; Shibata, Satomi; Iwasaki, Shogo; Inami, Shinichi

2009-01-01

Uninterruptible power supply systems are installed in the Tokai reprocessing plant in preparation for the emergency case that the commercial power supply is stopped by an accidental or intentional interruption in the supply of electricity. The uninterruptible power supply system particularly provides a temporary power source to the important devices for the radiation control of nuclear critical monitoring in the plant. Thus, the system is potentially important and essential for nuclear plants. The paper reports the current activities such as regular inspections, replacement of parts and system update, to maintain the function of uninterruptible power supply systems. (author)

Development of a mobile game based on virtual reality tools to sensitize the population about the nuclear power plant's emergency plan

Energy Technology Data Exchange (ETDEWEB)

Ferreira, Lucas H.H.; Mol, Antônio C. de A.; Santo, André C. do E.; Legey, Ana Paula [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Centro Universitário Carioca (Unicarioca), Rio de Janeiro, RJ (Brazil)

2017-07-01

The Angra dos Reis Nuclear Power Plant's emergency plan, it is the bunch of instructions that every citizen must adopt in case of an emergency situation. It is highly important, that all the people living in the power plant's surroundings truly understand every single step of the plan, because only in this way people will know how to react in case of a necessity. To hit this goals, the Brazil's Electronuclear, made educational booklets, in the shape of comic books, trying to guide the population about the plan. On the other hand, we have an increasingly connected world, making possible that digital games, be very well accepted by the population. So this project has as an objective, developing a digital tool, in form of a mobile game that shows in a playful and interactive way for the user, the emergency plan, complementing the educational process and social actions made by many institutions. With the information taken from the booklets, objects and buildings were modeled in Autodesk 3Ds Max, allied with the Unity 3D Game Engine, to make a city, inspired in Angra do Reis (RJ). The player has to follow all the security protocols giving by the Eletronuclear according with the rules provided by the National Nuclear Energy Commission. Is expected, with this game that will be available for the Eletronuclear that more people have the chance to know and believe in the efficiency of the emergency plan already established. (author)

Development of a mobile game based on virtual reality tools to sensitize the population about the nuclear power plant's emergency plan

International Nuclear Information System (INIS)

Ferreira, Lucas H.H.; Mol, Antônio C. de A.; Santo, André C. do E.; Legey, Ana Paula

2017-01-01

The Angra dos Reis Nuclear Power Plant's emergency plan, it is the bunch of instructions that every citizen must adopt in case of an emergency situation. It is highly important, that all the people living in the power plant's surroundings truly understand every single step of the plan, because only in this way people will know how to react in case of a necessity. To hit this goals, the Brazil's Electronuclear, made educational booklets, in the shape of comic books, trying to guide the population about the plan. On the other hand, we have an increasingly connected world, making possible that digital games, be very well accepted by the population. So this project has as an objective, developing a digital tool, in form of a mobile game that shows in a playful and interactive way for the user, the emergency plan, complementing the educational process and social actions made by many institutions. With the information taken from the booklets, objects and buildings were modeled in Autodesk 3Ds Max, allied with the Unity 3D Game Engine, to make a city, inspired in Angra do Reis (RJ). The player has to follow all the security protocols giving by the Eletronuclear according with the rules provided by the National Nuclear Energy Commission. Is expected, with this game that will be available for the Eletronuclear that more people have the chance to know and believe in the efficiency of the emergency plan already established. (author)

Knowledge and abilities catalog for nuclear power plant operators: boiling water reactors

International Nuclear Information System (INIS)

1986-09-01

The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWR) (NUREG-1123) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog and Examiners' Handbook for Developing Operator Licensing Examinations (NUREG-1121) will cover those topics listed under Title 10, Code of Federal Regulations, Part 55. The BWR Catalog contains approximately 7000 knowledge and ability (K/A) statements for ROs and SROs at boiling water reactors. Each K/A statement has been rated for its importance to the safe operation of the plant in a manner ensuring personnel and public health and safety. The BWR K/A Catalog is organized into five major sections: Plant-wide Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Function, Emergency and Abnormal Plant Evolutions, Components, and Theory. The BWR Catalog represents a modification of the form and content of the K/A Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors (NUREG-1122). First, categories of knowledge and ability statements have been redefined. Second, the scope of the definition of emergency and abnormal plant evolutions has been revised in line with a symptom-based approach. Third, K/As related to the operational applications of theory have been incorporated into the delineations for both plant systems and emergency and abnormal plant evolutions, while K/As pertaining to theory fundamental to plant operation have been delineated in a separate theory section. Finally, the components section has been revised

Images of nuclear power plants

International Nuclear Information System (INIS)

Hashiguchi, Katsuhisa; Misumi, Jyuji; Yamada, Akira; Sakurai, Yukihiro; Seki, Fumiyasu; Shinohara, Hirofumi; Misumi, Emiko; Kinjou, Akira; Kubo, Tomonori.

1995-01-01

This study was conducted to check and see, using Hayashi's quantification method III, whether or not the respondents differed in their images of a nuclear power plant, depending on their demographic variables particularly occupations. In our simple tabulation, we compared subject groups of nuclear power plant employees with general citizens, nurses and students in terms of their images of a nuclear power plant. The results were that while the nuclear power plant employees were high in their evaluations of facts about a nuclear power plant and in their positive images of a nuclear power plant, general citizens, nurses and students were overwhelmingly high in their negative images of a nuclear power plant. In our analysis on category score by means of the quantification method III, the first correlation axis was the dimension of 'safety'-'danger' and the second correlation axis was the dimension of 'subjectivity'-'objectivity', and that the first quadrant was the area of 'safety-subjectivity', the second quadrant was the area of 'danger-subjectivity', the third quadrant as the area of 'danger-objectivity', and the forth quadrant was the area of 'safety-objectivity'. In our analysis of sample score, 16 occupation groups was compared. As a result, it was found that the 16 occupation groups' images of a nuclear power plant were, in the order of favorableness, (1) section chiefs in charge, maintenance subsection chiefs, maintenance foremen, (2) field leaders from subcontractors, (3) maintenance section members, operation section members, (4) employees of those subcontractors, (5) general citizens, nurses and students. On the 'safety-danger' dimension, nuclear power plant workers on the one hand and general citizens, nurses and students on the other were clearly divided in terms of their images of a nuclear power plant. Nuclear power plant workers were concentrated in the area of 'safety' and general citizens, nurses and students in the area of 'danger'. (J.P.N.)

Licensed bases management for advanced nuclear plants

Energy Technology Data Exchange (ETDEWEB)

O' Connell, J. [Duke Engineering and Services, Marlborough, MA (United States); Rumble, E.; Rodwell, E. [EPRI, Palo Alto, CA (United States)

2001-07-01

Prospective Advanced Nuclear Plant (ANP) owners must have high confidence that the integrity of the licensed bases (LB) of a plant will be effectively maintained over its life cycle. Currently, licensing engineers use text retrieval systems, database managers, and checklists to access, update, and maintain vast and disparate licensing information libraries. This paper describes the demonstration of a ''twin-engine'' approach that integrates a program from the emerging class of concept searching tools with a modern Product Data Management System (PDMS) to enhance the management of LB information for an example ANP design. (author)

The feature of emergency diesel generator relaying protection in Tianwan nuclear power station

International Nuclear Information System (INIS)

Jiang Xiaopeng; Shi Yan; Li Cong

2014-01-01

This paper mainly introduces the function and feature of emergency diesel generator in nuclear power plant, which plays an important role in nuclear accident. It minutely tells about the feature and configuration of relay protection and discusses the rationality of protection scheme, which shows that it can be completely contented all kinds of operation states. It is an analysis and argument about the principle of relay protection in detail, that would operate correctly when emergency diesel generator be in abnormal operating and serious fault conditions, such as cut off emergency diesel generator in order to avoid more harm to emergency diesel generator. It analyzes how the relay responses quickly and locks up the protection action under perturbations in the external power, so it can avoid unnecessary resection of emergency diesel generator to emergency power supply loss and effect of nuclear safety. It also analyzes the flexible use of protection setting of the protective relay to meet various operating status. It elaborates the particularity of relay protection which is due to the particularity of nuclear safety. It analyses the possibility of relay protection which has to be applied to other equipment and the protection setting that was provided by design institute, and puts forward the author's viewpoints. (authors)

Off-site nuclear emergency management

International Nuclear Information System (INIS)

Miska, H.

2003-01-01

Full text: Urgent protective measures for the possibly affected population are the main items to be addressed here, that means actions to be planned and taken in the pre-release and release phase of a nuclear accident. Since we will focus an off-site nuclear emergency management, the utility or licensee only plays a subordinate role, but nevertheless may be the potential cause of all actions. At the other end, there is the possible affected population, the environment, and also economic values. Emergency preparedness and response aims at minimizing adverse effects from the power plant to the values to protect. In the early phase of an accident under consideration here, prompt and sharp actions are necessary to ensure efficacy. On the other hand, the available information on the situation is most limited in this phase such that pre-determined actions based on simple criteria are indispensable. The responsibility for early response actions normally rest with a regional authority which may have some county administrations at subordinate level. The leader of the regional staff has to decide upon protective measures to be implemented at county or municipal level; thus, coherence of the response is ensured at least at a regional level. The decision will be governed at the one side by the existing or predicted radiological situation, on the other side an practical limitations like availability of teams and means. The radiological situation has to be assessed by an advisory team that compiles all information from the utility, the weather conditions, and monitoring results. While the staff leader is experienced through response to major non-nuclear events, the advisors mainly come from the environmental side, having no experience in taking swift decisions in an emergency, but are used to control and prevent. This might be the source of conflicts as observed in several exercises. The radiation protection advisors collect information from the utility, especially about time

Elecnuc. Nuclear power plants in the world

International Nuclear Information System (INIS)

2003-01-01

This 2003 version of Elecnuc contents information, data and charts on the nuclear power plants in the world and general information on the national perspectives concerning the electric power industry. The following topics are presented: 2002 highlights; characteristics of main reactor types and on order; map of the French nuclear power plants; the worldwide status of nuclear power plants on 2002/12/3; units distributed by countries; nuclear power plants connected to the Grid by reactor type groups; nuclear power plants under construction; capacity of the nuclear power plants on the grid; first electric generations supplied by a nuclear unit; electrical generation from nuclear plants by country at the end 2002; performance indicator of french PWR units; trends of the generation indicator worldwide from 1960 to 2002; 2002 cumulative Load Factor by owners; nuclear power plants connected to the grid by countries; status of license renewal applications in Usa; nuclear power plants under construction; Shutdown nuclear power plants; exported nuclear power plants by type; exported nuclear power plants by countries; nuclear power plants under construction or order; steam generator replacements; recycling of Plutonium in LWR; projects of MOX fuel use in reactors; electricity needs of Germany, Belgium, Spain, Finland, United Kingdom; electricity indicators of the five countries. (A.L.B.)

Upgrade the intervention levels derived for water and foods, to be include in the PERE 607 procedure the external radiological emergency plan in the Laguna Verde nuclear power plant

International Nuclear Information System (INIS)

Llado Castillo, R.; Aguilar Pacheco, R.

1998-01-01

The work shows the results obtained in the upgrade the intervention levels derived for water and foods, to be include in the PERE 607 procedure the external radiological emergency plan in the Laguna Verde nuclear power plant

COOLING WATER ISSUES AND OPPORTUNITIES AT U.S. NUCLEAR POWER PLANTS

Energy Technology Data Exchange (ETDEWEB)

Gary Vine

2010-12-01

This report has been prepared for the Department of Energy, Office of Nuclear Energy (DOE-NE), for the purpose of providing a status report on the challenges and opportunities facing the U.S. commercial nuclear energy industry in the area of plant cooling water supply. The report was prompted in part by recent Second Circuit and Supreme Court decisions regarding cooling water system designs at existing thermo-electric power generating facilities in the U.S. (primarily fossil and nuclear plants). At issue in the courts have been Environmental Protection Agency regulations that define what constitutes “Best Technology Available” for intake structures that withdraw cooling water that is used to transfer and reject heat from the plant’s steam turbine via cooling water systems, while minimizing environmental impacts on aquatic life in nearby water bodies used to supply that cooling water. The report was also prompted by a growing recognition that cooling water availability and societal use conflicts are emerging as strategic energy and environmental issues, and that research and development (R&D) solutions to emerging water shortage issues are needed. In particular, cooling water availability is an important consideration in siting decisions for new nuclear power plants, and is an under-acknowledged issue in evaluating the pros and cons of retrofitting cooling towers at existing nuclear plants. Because of the significant ongoing research on water issues already being performed by industry, the national laboratories and other entities, this report relies heavily on ongoing work. In particular, this report has relied on collaboration with the Electric Power Research Institute (EPRI), including its recent work in the area of EPA regulations governing intake structures in thermoelectric cooling water systems.

The Meteorological Monitoring program at a former nuclear weapons plant

International Nuclear Information System (INIS)

Maxwell, D.R.; Bowen, B.M.

1994-01-01

The purpose of the Meteorological Monitoring program at Rocky Flats Plant (RFP) is to provide meteorological information for use in assessing the transport, and diffusion, and deposition of effluent actually or potentially released into the atmosphere by plant operations. Achievement of this objective aids in protecting health and safety of the public, employees, and environment, and directly supports Emergency Response programs at RFP. Meteorological information supports the design of environmental monitoring networks for impact assessments, environmental surveillance activities, remediation activities, and emergency responses. As the mission of the plant changes from production of nuclear weapons parts to environmental cleanup and economic development, smaller releases resulting from remediation activities become more likely. These possible releases could result from airborne fugitive dust, evaporation from collection ponds, or grass fires

International measures for supporting the Ukraine in decommissioning Chernobyl nuclear power plant

International Nuclear Information System (INIS)

Wolf, J.

2006-01-01

The destruction of Block 4 of the Ukranian nuclear power plant in Chernobyl on 26 April 1986 was the largest and most momentous accident in the civil use of nuclear energy. Its far-reaching and lasting ecological, heath-related and economic effects confronted the then Soviet and later the Ukraine with grave problems. Particularly after the dissolution of the Eastern Bloc and the emergence of information about the safety shortcomings of RBMK-type (Chernobyl-type) reactors the Western states pressed for the decommissioning of these reactors. At the G7 summit in Naples in 1994 the Ukraine was offered an action plan of support if it were willing to close down Chernobyl nuclear power plant. This initiative led to the signing on 20 December 1995 of a Memorandum of Understanding on the Closure of Chernobyl Nuclear Power Plant between the G7 states, the European Commission and the Ukraine. It contained an assurance by President Kuchma that Chernobyl nuclear power plant would be closed by the year 2000

The handling of nuclear emergencies in Argentina

International Nuclear Information System (INIS)

Hernandez, Daniel; Jordan, Osvaldo; Kunst, Juan; Bruno, Hector

2008-01-01

Full text: In 1998, the Executive signed the decree 1390, which defined the scope and the procedures corresponding to the Nuclear Activity Law. In this decree, the new functions of the Nuclear Regulatory Authority (ARN) are described, being the most important related to preparation and response for a nuclear emergency the following ones: 1) ARN must provide protection from harmful effects of ionizing radiations under normal conditions and emergency situations; 2) ARN must advise the Executive in case of radiological and nuclear emergencies; 3) ARN shall establish the criteria for the emergency plans of the facilities and train the members of neighbor public to the facilities in case of nuclear emergencies; 4) The emergency plans developed by local, provincial and national authorities must be approved by the ARN; 5) ARN shall lead the actions within the area covered by the emergency plans of the facilities. Security Forces and the Representatives of Civil Institutions shall report the designated ARN officer. The ARN recognized immediately the responsibility imposed by this law and, at the same time, the opportunity of improving the handling of emergencies through a centralized direction of the operations. Under this frame, ARN created the Radiological Emergencies Intervention System (SIER) with the goal of taking charge of the preparation and the handling of emergency situations. From the beginning, the purpose of the SIER was to improve the preparation and response to nuclear emergencies in a regular form, bearing in mind the cultural and socioeconomic situation of the country, as well as the local peculiarities. The first steep to achieve such a target was to gain the confidence of other organizations included in the response on the ARN technical and operational aptitude to lead the actions inside the emergency area and, later, to establish the pertinent arrangements. The strategy chosen by ARN to respond to nuclear emergencies consists in establishing an expert

Nuclear emergency planning in Norway

International Nuclear Information System (INIS)

Baarli, J.

1986-01-01

The nuclear emergency planning in Norway is forming a part of the Search and Rescue Service of the country. Due to the fact that Norway do not have any nucleat power reactor, the nuclear emergency planning has not been given high priority. The problems however are a part of the activity of the National Institute of Radiation Hygiene, and the emergency preparedness is at the present time to a large extent based on the availability of professional health physicists and their knowledge, rather than established practices

Selection/licensing of nuclear power plant operators

International Nuclear Information System (INIS)

Saari, L.M.

1983-07-01

An important aspect of nuclear power plant (NPP) safety is the reactor operator in the control room. The operators are the first individuals to deal with an emergency situation, and thus, effective performance on their part is essential for safe plant operations. Important issues pertaining to NPP reactor operators would fall within the personnel subsystem of our safety system analysis. While there are many potential aspects of the personnel subsystem, a key first step in this focus is the selection of individuals - attempting to choose individuals for the job of reactor operator who will safely perform the job. This requires a valid (job-related) selection process. Some background information on the Nuclear Regulatory Commission (NRC) licensing process used for selecting NPP reactor operators is briefly presented and a description of a research endeavor now underway at Battelle for developing a valid reactor operator licensing examination is included

Nuclear power plant control room operators' performance research

International Nuclear Information System (INIS)

Gray, L.H.; Haas, P.M.

1984-01-01

A research program is being conducted to provide information on the performance of nuclear power plant control room operators when responding to abnormal/emergency events in the plants and in full-scope training simulators. The initial impetus for this program was the need for data to assess proposed design criteria for the choice of manual versus automatic action for accomplishing safety-related functions during design basis accidents. The program also included studies of training simulator capabilities, of procedures and data for specifying and verifying simulator performance, and of methods and applications of task analysis

Operation of Finnish nuclear power plants. Quarterly report, 3rd quarter 1997

International Nuclear Information System (INIS)

Tossavainen, K.

1998-04-01

Quarterly reports on the operation of Finnish nuclear power plants describe events and observations relating to nuclear and radiation safety that the Radiation and Nuclear Safety Authority of Finland (STUK) considers safety significant. Safety improvements at the plants are also described. The Report also includes a summary of the radiation safety of plant personnel and of the environment and tabulated data on the plants' production and load factors. The Finnish nuclear power plant units were in power operation in the third quarter of 1997, except for the annual maintenance outages of Loviisa plant units which lasted well over a month in all. There was also a brief interruption in electricity generation at Olkiluoto 1 for repairs and at Olkiluoto 2 due to a disturbance at the turbine plant. All plant units were in long-term test operation at upgraded reactor power level approved by STUK. The load factor average of all plant units was 87.6 %. One event in the third quarter was classified level 1 on the International Nuclear Event Scale (INES). It was noted at Loviisa 2 that one of four pressurized water tanks in the plant unit's emergency cooling system had been inoperable for a year. Other events in this quarter were INES level 0. Occupational doses and radioactive releases off-site were below authorized limits. Radioactive substances were measurable in samples collected around the plants in such quantities only as have no bearing on the radiation exposure of the population. (orig.)

76 FR 1469 - Calvert Cliffs Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2...

Science.gov (United States)

2011-01-10

... Nuclear Power Plant, LLC; Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Environmental Assessment... Plant, LLC, the licensee, for operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2... Impact Statement for License Renewal of Nuclear Plants, Calvert Cliffs Nuclear Power Plant (NUREG-1437...

A new series of international nuclear emergency exercises (INEX)

International Nuclear Information System (INIS)

Halil-Burcin Okyar; Lazo, Edward; Siemann, Michael

2014-01-01

The INEX series of international nuclear emergency exercises, organised under the auspices of the NEA Working Party on Nuclear Emergency Matters (WPNEM), has proven successful in testing, investigating and improving national and international response arrangements for nuclear accidents and radiological emergencies. The Fukushima Daiichi nuclear power plant (NPP) accident occurred during INEX-4 and had a direct impact on NEA technical standing committees' work programmes. The WPNEM played an important role during the emergency, following and studying the insights and ideas that drive nuclear emergency management decision making. It collected crucial information on governmental decisions and recommendations with respect to the accident situation, and implemented a framework study to assist in the collection of NEA member country experiences that would facilitate the identification of commonalities in national assessment approaches and results. The findings triggered the INEX-5 exercise, which will build upon the experiences and lessons learnt from past nuclear accidents/incidents, and the success of previous INEX exercises. This exercise is intended to test mechanisms for decision making at the national level, particularly in uncertain circumstances or in the absence of data, to examine arrangements for international co-operation and coordination of data and information exchange among countries and arrangements for practical support and assistance between groups of countries or geographical regions. It will also investigate the long-term issues beyond the early response phase. The WPNEM agreed on a tightly focused scope, which will consist of a tabletop exercise or moderated workshop that is not based on a real time test. The exercise will be a common scenario based on a re-enactment of a nuclear power plant accident, although not the Fukushima accident. It will consider coincident impacts on multiple units and include impacts on other critical national

Nuclear emergencies

International Nuclear Information System (INIS)

1991-01-01

This leaflet, which is in the form of a fold-up chart, has panels of text which summarize the emergencies that could arise and the countermeasures and emergency plans that have been prepared should nuclear accident occur or affect the United Kingdom. The levels of radiation doses at which various measures would be introduced are outlined. The detection and monitoring programmes that would operate is illustrated. The role of NRPB and the responsible government departments are set out together with an explanation of how the National Arrangements for Incidents involving Radioactivity would be coordinated. (UK)