Training practices to support decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Bourassa, J.; Clark, C.R.; Kazennov, A.; Laraia, M.; Rodriguez, M.; Scott, A.; Yoder, J.

2006-01-01

Adequate numbers of competent personnel must be available during any phase of a nuclear facility life cycle, including the decommissioning phase. While a significant amount of attention has been focused on the technical aspects of decommissioning and many publications have been developed to address technical aspects, human resource management issues, particularly the training and qualification of decommissioning personnel, are becoming more paramount with the growing number of nuclear facilities of all types that are reaching or approaching the decommissioning phase. One of the keys to success is the training of the various personnel involved in decommissioning in order to develop the necessary knowledge and skills required for specific decommissioning tasks. The operating organisations of nuclear facilities normally possess limited expertise in decommissioning and consequently rely on a number of specialized organisations and companies that provide the services related to the decommissioning activities. Because of this there is a need to address the issue of assisting the operating organisations in the development and implementation of human resource management policies and training programmes for the facility personnel and contractor personnel involved in various phases of decommissioning activities. The lessons learned in the field of ensuring personnel competence are discussed in the paper (on the basis of information and experiences accumulated from various countries and organizations, particularly, through relevant IAEA activities). Particularly, the following aspects are addressed: transition of training from operational to decommissioning phase; knowledge management; target groups, training needs analysis, and application of a systematic approach to training (SAT); content of training for decommissioning management and professional staff, and for decommissioning workers; selection and training of instructors; training facilities and tools; and training as

IAEA world survey on nuclear power plant personnel training

International Nuclear Information System (INIS)

1999-01-01

Training of personnel is acknowledged to be essential for safe and reliable operation of nuclear power plants. The preparation of this TECDOC was recommended by the IAEA International Working group on Nuclear Power Plant Personnel Training and Qualification and represents a unique compilation of information including all aspects of NPP personnel training from 23 Member States and 129 training organizations. The basic aims of this survey are: to provide a worldwide overview of all aspects of NPP personnel training; to foster both national and international cooperation between organizations involved in nuclear training; to provide the means of exchange of experiences and practices in systematic approach to training (SAT). The survey provides information for each corresponding country on the: national system and organization of training; job positions for which SAT is used; training programmes for key operations, maintenance, instructor and other jobs; role of management and the regulatory body; training facilities; recommended training practices; availability of training personnel from organizations outside the country; and contact points. The three main parts of the publication are the summary, the analysis of training programmes for each job position and the analysis of training resources, and the country reports

Specific schedule conditions for the formation of personnel of A or B category working in nuclear facilities. Option research center

CERN Document Server

Int. At. Energy Agency, Wien

2002-01-01

This document describes the specific dispositions relative to the Research Center, for the formation to the conventional and radiation risks prevention of personnel of A or B category working in nuclear facilities. The application domain, the applicable documents, the liability, the specificity of the Research Center and of the retraining, the Passerelle formation, are presented. (A.L.B.)

Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel. That is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

Recruitment, qualification and training of personnel for nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2002-01-01

The objective of this Safety Guide is to outline the various factors that should to be considered in order to ensure that the operating organization has a sufficient number of qualified personnel for safe operation of a nuclear power plant. In particular, the objective of this publication is to provide general recommendations on the recruitment and selection of plant personnel and on the training and qualification practices that have been adopted in the nuclear industry since the predecessor Safety Guide was published in 1991. In addition, this Safety Guide seeks to establish a framework for ensuring that all managers and staff employed at a nuclear power plant demonstrate their commitment to the management of safety to high professional standards. This Safety Guide deals specifically with those aspects of qualification and training that are important to the safe operation of nuclear power plants. It provides recommendations on the recruitment, selection, qualification, training and authorization of plant personnel; that is, of all personnel in all safety related functions and at all levels of the plant. Some parts or all of this Safety Guide may also be used, with due adaptation, as a guide to the recruitment, selection, training and qualification of staff for other nuclear installations (such as research reactors or nuclear fuel cycle facilities). Section 2 gives guidance on the recruitment and selection of suitable personnel for a nuclear power plant. Section 3 gives guidance on the establishment of personnel qualification, explains the relationship between qualification and competence, and identifies how competence may be developed through education, experience and training. Section 4 deals with general aspects of the training policy for nuclear power plant personnel: the systematic approach, training settings and methods, initial and continuing training, and the keeping of training records. Section 5 provides guidance on the main aspects of training programmes

Public's right to information: An independent safety assessment of Department of Energy nuclear reactor facilities

International Nuclear Information System (INIS)

Stokely, E.

1981-02-01

The events at TMI prompted the Under Secretary of the Department of Energy (DOE) to establish the Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee. This Committee was assigned the task of assessing the adequacy of nuclear facility personnel qualification and training at DOE-owned reactors in light of the Three Mile Island accident. The Committee was also asked to review recommendations and identify possible implications for DOE's nuclear facilities

Decommissioning of Nuclear Facilities: Training and Human Resource Considerations

International Nuclear Information System (INIS)

2008-01-01

One of the cornerstones of the success of nuclear facility decommissioning is the adequate competence of personnel involved in decommissioning activities. The purpose of this publication is to provide methodological guidance for, and specific examples of good practices in training as an integral part of human resource management for the personnel performing decommissioning activities. The use of the systematic methodology and techniques described in this publication may be tailored and applied to the development of training for all types of nuclear facilities undergoing decommissioning. Examples of good practices in other aspects of human resources, such as knowledge preservation, management of the workforce and improvement of human performance, are also covered. The information contained in this publication, and the examples provided in the appendices and enclosed CD-ROM, are representative of the experience of decommissioning of a wide variety of nuclear facilities.

Assuring the competence of nuclear power plant contractor personnel

International Nuclear Information System (INIS)

2001-07-01

quality; the contractors performing work on-site or off-site (Section 3); contractors involved on a short-term or long-term basis; contractors involved in plant routine activities or performing unique/specific activities; contractor activities dealing with plant safety systems or systems important for safety, which may make more demands on contractor personnel competence. Contractor personnel provide essential services to nuclear power plants and other nuclear facilities, particularly during plant outages or for projects involving major upgrading of plant. Typical services are: unique services offered by specialised contractors; augmentation of NPP personnel for particular tasks; general services provided on a permanent basis. In providing these services contractor personnel encounter similar problems to those that challenge NPP personnel. Typical examples are assessment of risk, quality assurance, compliance with procedures, communications, teamwork, work in hazardous environments and concerns about nuclear safety. Accordingly, contractor personnel must be competent and effectively interface with NPP personnel when performing assigned duties. Assurance is required that contractor personnel meet the qualification criteria before undertaking any activities at a NPP site, as the NPP has a responsibility for establishing qualification criteria for its own personnel and for contractor personnel. The objective of this TECDOC is to assist NPPs and other organisations to ensure that NPP contractor personnel are competent to undertake their assigned tasks. This TECDOC addresses the competence of contractor personnel for an operating nuclear power plant or for a nuclear power plant under decommissioning. This TECDOC deals specifically with contractor personnel working on-site at a nuclear power plant; however, the principles addressed here have similar applicability to off-site work undertaken by contractors. This publication comprises 11 sections and 17 annexes containing

Assuring the competence of nuclear power plant contractor personnel

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

quality; the contractors performing work on-site or off-site (Section 3); contractors involved on a short-term or long-term basis; contractors involved in plant routine activities or performing unique/specific activities; contractor activities dealing with plant safety systems or systems important for safety, which may make more demands on contractor personnel competence. Contractor personnel provide essential services to nuclear power plants and other nuclear facilities, particularly during plant outages or for projects involving major upgrading of plant. Typical services are: unique services offered by specialised contractors; augmentation of NPP personnel for particular tasks; general services provided on a permanent basis. In providing these services contractor personnel encounter similar problems to those that challenge NPP personnel. Typical examples are assessment of risk, quality assurance, compliance with procedures, communications, teamwork, work in hazardous environments and concerns about nuclear safety. Accordingly, contractor personnel must be competent and effectively interface with NPP personnel when performing assigned duties. Assurance is required that contractor personnel meet the qualification criteria before undertaking any activities at a NPP site, as the NPP has a responsibility for establishing qualification criteria for its own personnel and for contractor personnel. The objective of this TECDOC is to assist NPPs and other organisations to ensure that NPP contractor personnel are competent to undertake their assigned tasks. This TECDOC addresses the competence of contractor personnel for an operating nuclear power plant or for a nuclear power plant under decommissioning. This TECDOC deals specifically with contractor personnel working on-site at a nuclear power plant; however, the principles addressed here have similar applicability to off-site work undertaken by contractors. This publication comprises 11 sections and 17 annexes containing

Standards for psychological assessment of nuclear facility personnel. Technical report

International Nuclear Information System (INIS)

Frank, F.D.; Lindley, B.S.; Cohen, R.A.

1981-07-01

The subject of this study was the development of standards for the assessment of emotional instability in applicants for nuclear facility positions. The investigation covered all positions associated with a nuclear facility. Conclusions reached in this investigation focused on the ingredients of an integrated selection system including the use of personality tests, situational simulations, and the clinical interview; the need for professional standards to ensure quality control; the need for a uniform selection system as organizations vary considerably in terms of instruments presently used; and the need for an on-the-job behavioral observation program

Qualification of nuclear power plant inspection, examination, and testing personnel. Revision 1, September 1980

International Nuclear Information System (INIS)

Anon.

1981-01-01

Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, requires that the quality assurance program provide for indoctrination and training of personnel performing activities affecting quality as necessary to ensure that quality assurance personnel achieve and maintain suitable proficiency. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of inspection, examination, and testing personnel for all types of nuclear power plants

Results of nuclear security culture survey on personnel at nuclear power plants

International Nuclear Information System (INIS)

Yoo, Hosik; Lee, Jeong-Ho

2015-01-01

Highlights: • A new surveying questionnaire for evaluating the security awareness of personnel was developed. • The developed surveying tools consist of four categories and 44 questions in total. • The surveying tools developed in this study can be used in other countries. - Abstract: A survey to evaluate awareness of the nuclear security culture of personnel at nuclear facilities was developed. The survey was made up of a series of questionnaires that were divided into four categories, beliefs and attitude, operating systems, leadership behaviors and staff behaviors. Each category contained six to 16 questions. The category on beliefs and attitude was composed of questions that asked plant workers on how much consideration facility personnel give to issues of security when doing his/her work. The section pertaining to operating systems for nuclear security consisted of questions on guidance documents, information security, and education and training. The questions on leadership behaviors were separated into two parts, one for managers and another for staff. These include questions relating to communication between management and staff, surveillance work related to nuclear security and the sharing of information. The last category of questions concerned staff behaviors. It consisted of questions on knowledge, procedures and implementation related to nuclear security. A survey was conducted on 858 people who worked at nuclear power plants using the questionnaire that was developed in this study. The survey was performed between October 7 to 17, 2014. The survey results were collected and analyzed. A numerical value was given to each question, so that the results of the survey were represented as a score. The data revealed that awareness of the nuclear security culture increased with age. This increase stopped when staff members entered their 50s. It is believed that a person in his/her 50s has a greater degree of experience and passion for their work than

Civaux nuclear facilities. 2009 annual report

International Nuclear Information System (INIS)

2010-01-01

This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of Civaux, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

Chooz nuclear facilities. 2009 annual report

International Nuclear Information System (INIS)

2010-01-01

This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of Chooz, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

Brennilis nuclear facilities. 2009 annual report

International Nuclear Information System (INIS)

2010-01-01

This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of Brennilis, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

An independent safety assessment of Department of Energy nuclear reactor facilities: Safety overview and management function

International Nuclear Information System (INIS)

Booth, M.; Brodsky, R.S.; Frankhouser, W.L.

1981-02-01

The Under Secretary of Energy established the Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee in October, 1979, in the aftermath of the Three Mile Island (TMI) nuclear accident, to assess the adequacy of training of personnel at DOE nuclear facilities. Subsequently, in February, 1980, the charge to this Committee was modified to assess all implications of the Kemeny Commission report on TMI with regard to DOE nuclear reactors, excluding those in the Division of Naval Reactors. The modified charge was also limited, for the time being, to reactor facilities instead of all nuclear facilities. This report describes the portion of the revised assessment activities that was assigned to the Assessment Support Team

Nuclear Test Personnel Review

Science.gov (United States)

FOIA Electronic Reading Room Privacy Impact Assessment DTRA No Fear Act Reporting Nuclear Test Personnel Review NTPR Fact Sheets NTPR Radiation Dose Assessment Documents US Atmospheric Nuclear Test History Documents US Underground Nuclear Test History Reports NTPR Radiation Exposure Reports Enewetak

Increasing the effectiveness of the physical protection system on a nuclear facility

Energy Technology Data Exchange (ETDEWEB)

Vaz, Antonio C.A.; Conti, Thadeu N., E-mail: acavaz@ipen.br, E-mail: tnconti@ipen.br [Instituto de Pesquisas Energéticas e Nucleares (IPEN/CNEN-SP), São Paulo, SP (Brazil)

2017-07-01

The malicious use of radioactive material could be devastating, particularly in the case of a nuclear explosive device, it could be unpredictably disruptive resulting in the dispersal of radioactive material, like it was in the Fukushima Daiichi Nuclear Power Plant disaster. Physical Protection System (PPS) plays an important role in ensuring that individuals, organizations and institutions remain vigilant and that sustained measures are taken to prevent and combat the threat of sabotage or of using radioactive material for malicious acts. PPS is an integrated system of people, equipment and procedures used to protect nuclear facilities and radioactive sources against threat, theft or sabotage. In the operator's perspective, this paper study factors influencing the performance of a PPS in a nuclear facility suggesting ways to increase the system effectiveness. The human factor, the physical and the psychological work environment has a large impact on how personnel perform their work and comply with nuclear security requirements. Apathy and corporatism are two human behaviors that collaborate negatively and make decrease the effectiveness of any PPS. Job satisfaction reduces the probability that personnel will become less reliable and/or obstructive in extreme cases an insider threat. Managers must recognize individual and group needs and the relationship among personnel so that they may motivate personnel by creating a supportive working environment that reduces workplace stress. An effective PPS can result in a significant increase in the effectiveness of the security of radioactive material and associated facilities. (author)

Increasing the effectiveness of the physical protection system on a nuclear facility

International Nuclear Information System (INIS)

Vaz, Antonio C.A.; Conti, Thadeu N.

2017-01-01

The malicious use of radioactive material could be devastating, particularly in the case of a nuclear explosive device, it could be unpredictably disruptive resulting in the dispersal of radioactive material, like it was in the Fukushima Daiichi Nuclear Power Plant disaster. Physical Protection System (PPS) plays an important role in ensuring that individuals, organizations and institutions remain vigilant and that sustained measures are taken to prevent and combat the threat of sabotage or of using radioactive material for malicious acts. PPS is an integrated system of people, equipment and procedures used to protect nuclear facilities and radioactive sources against threat, theft or sabotage. In the operator's perspective, this paper study factors influencing the performance of a PPS in a nuclear facility suggesting ways to increase the system effectiveness. The human factor, the physical and the psychological work environment has a large impact on how personnel perform their work and comply with nuclear security requirements. Apathy and corporatism are two human behaviors that collaborate negatively and make decrease the effectiveness of any PPS. Job satisfaction reduces the probability that personnel will become less reliable and/or obstructive in extreme cases an insider threat. Managers must recognize individual and group needs and the relationship among personnel so that they may motivate personnel by creating a supportive working environment that reduces workplace stress. An effective PPS can result in a significant increase in the effectiveness of the security of radioactive material and associated facilities. (author)

Personnel neutron dosimetry at Department of Energy facilities

International Nuclear Information System (INIS)

Brackenbush, L.W.; Endres, G.W.R.; Selby, J.M.; Vallario, E.J.

1980-08-01

This study assesses the state of personnel neutron dosimetry at DOE facilities. A survey of the personnel dosimetry systems in use at major DOE facilities was conducted, a literature search was made to determine recent advances in neutron dosimetry, and several dosimetry experts were interviewed. It was concluded that personnel neutron dosimeters do not meet current needs and that serious problems exist now and will increase in the future if neutron quality factors are increased and/or dose limits are lowered

Study on Nuclear Facility Cyber Security Awareness and Training Programs

International Nuclear Information System (INIS)

Lee, Jung-Woon; Song, Jae-Gu; Lee, Cheol-Kwon

2016-01-01

Cyber security awareness and training, which is a part of operational security controls, is defined to be implemented later in the CSP implementation schedule. However, cyber security awareness and training is a prerequisite for the appropriate implementation of a cyber security program. When considering the current situation in which it is just started to define cyber security activities and to assign personnel who has responsibilities for performing those activities, a cyber security awareness program is necessary to enhance cyber security culture for the facility personnel to participate positively in cyber security activities. Also before the implementation of stepwise CSP, suitable education and training should be provided to both cyber security teams (CST) and facility personnel who should participate in the implementation. Since such importance and urgency of cyber security awareness and training is underestimated at present, the types, trainees, contents, and development strategies of cyber security awareness and training programs are studied to help Korean nuclear facilities to perform cyber security activities more effectively. Cyber security awareness and training programs should be developed ahead of the implementation of CSP. In this study, through the analysis of requirements in the regulatory standard RS-015, the types and trainees of overall cyber security training programs in nuclear facilities are identified. Contents suitable for a cyber security awareness program and a technical training program are derived. It is suggested to develop stepwise the program contents in accordance with the development of policies, guides, and procedures as parts of the facility cyber security program. Since any training programs are not available for the specialized cyber security training in nuclear facilities, a long-term development plan is necessary. As alternatives for the time being, several cyber security training courses for industrial control systems by

Study on Nuclear Facility Cyber Security Awareness and Training Programs

Energy Technology Data Exchange (ETDEWEB)

Lee, Jung-Woon; Song, Jae-Gu; Lee, Cheol-Kwon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2016-10-15

Cyber security awareness and training, which is a part of operational security controls, is defined to be implemented later in the CSP implementation schedule. However, cyber security awareness and training is a prerequisite for the appropriate implementation of a cyber security program. When considering the current situation in which it is just started to define cyber security activities and to assign personnel who has responsibilities for performing those activities, a cyber security awareness program is necessary to enhance cyber security culture for the facility personnel to participate positively in cyber security activities. Also before the implementation of stepwise CSP, suitable education and training should be provided to both cyber security teams (CST) and facility personnel who should participate in the implementation. Since such importance and urgency of cyber security awareness and training is underestimated at present, the types, trainees, contents, and development strategies of cyber security awareness and training programs are studied to help Korean nuclear facilities to perform cyber security activities more effectively. Cyber security awareness and training programs should be developed ahead of the implementation of CSP. In this study, through the analysis of requirements in the regulatory standard RS-015, the types and trainees of overall cyber security training programs in nuclear facilities are identified. Contents suitable for a cyber security awareness program and a technical training program are derived. It is suggested to develop stepwise the program contents in accordance with the development of policies, guides, and procedures as parts of the facility cyber security program. Since any training programs are not available for the specialized cyber security training in nuclear facilities, a long-term development plan is necessary. As alternatives for the time being, several cyber security training courses for industrial control systems by

Organization of the internal dosimetry in the Spanish nuclear facilities

International Nuclear Information System (INIS)

Manchena, P.; Soliet, E.

1998-01-01

From the beginning of the exploitation of the nuclear energy of Espanna, the nuclear facilities have had Services of Personal Dosimetry with the appropriate means to determine the dose. so much internal as external, of the personnel that mentioned facilities works. All the nuclear power stations use advanced systems of teams with object of detecting the radionuclides incorporation in the organism and calculation programs based on the recent recommendations of the International Commission of Radiological Protection (ICRP) for the determination of the derived doses

Staffing, recruitment, training, qualification and certification of operating personnel of nuclear power plants

International Nuclear Information System (INIS)

1999-10-01

Safety of public, occupational workers and the protection of environment should be assured while activities for economic and social progress are pursued. These activities include the establishment and utilisation of nuclear facilities and the use of radioactive sources. This safety guide provides guidance on the aspects of staffing, recruitment, training, qualification and certification of operating personnel of nuclear power plants

Disaster countermeasures around nuclear facilities

International Nuclear Information System (INIS)

Tatsuta, Yoshinori

1982-01-01

The following matters are described. Safety regulation administration for nuclear power plants; nuclear disaster countermeasures in the United States; disaster countermeasures around nuclear facilities (a report of the ad hoc committee in Nuclear Safety Commission), including general requirements, the scope of areas to take the countermeasures, emergency environmental monitoring, guidelines for taking the countermeasures, and emergency medical treatment. In the nuclear safety administration, the system of stationing safety expert personnel on the sites of nuclear power generation and qualifying the persons in charge of reactor operation in the control room is also introduced. As for the disaster countermeasures, such as the detection of an abnormal state, the notification of the abnormality to various organs concerned, the starting of emergency environmental monitoring, the establishment of the countermeasure headquarters, and emergency measures for the local people. (Mori, K.)

General problems specific to hot nuclear materials research facilities

International Nuclear Information System (INIS)

Bart, G.

1996-01-01

During the sixties, governments have installed hot nuclear materials research facilities to characterize highly radioactive materials, to describe their in-pile behaviour, to develop and test new reactor core components, and to provide the industry with radioisotopes. Since then, the attitude towards the nuclear option has drastically changed and resources have become very tight. Within the changed political environment, the national research centres have defined new objectives. Given budgetary constraints, nuclear facilities have to co-operate internationally and to look for third party research assignments. The paper discusses the problems and needs within experimental nuclear research facilities as well as industrial requirements. Special emphasis is on cultural topics (definition of the scope of nuclear research facilities, the search for competitive advantages, and operational requirements), social aspects (overageing of personnel, recruitment, and training of new staff), safety related administrative and technical issues, and research needs for expertise and state of the art analytical infrastructure

Ensuring the safety of nuclear facilities located in large cities

International Nuclear Information System (INIS)

Ryazantsev, E.P.; Kolyadin, V.I.; Bylkin, B.K.; Zverkov, Yu.A.

2002-01-01

The problems of ensuring the safety of nuclear facilities and other facilities representing a radiation hazard (hereinafter referred to as 'nuclear facilities') which are located in large cities are considered in the light of the experience with the 'Kurchatov Institute' Russian Research Centre. The accumulation of substantial quantities of spent nuclear fuel and radwaste at the Centre was an inevitable consequence of the military and civilian nuclear research programmes which started there in 1943. A comprehensive programme has been developed for reducing the impact of ionizing radiation on the Centre's personnel, the population living near the Centre and the local environment. The authors describe the basic elements of a programme for decommissioning reactor facilities and eliminating spent fuel and radwaste storage sites and also describe how the programme is progressing. (author)

Decree of the State Office for Nuclear Safety No. 146/1997 of 18 June 1997 specifying activities which have an immediate impact on nuclear safety, and activities which are particularly important with respect to radiation protection, requirements for qualification and professional training, procedures for examining special professional competence and for granting certificates to selected personnel, and the scope and structure of documentation to be approved for permitting the training of selected personnel

International Nuclear Information System (INIS)

1997-01-01

The Decree specifies requirements in the following fields: (a) activities which have an immediate impact on nuclear safety and activities which are particularly important with respect to radiation protection; (b) requirements for the qualification of selected personnel; (c) requirements for professional training of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources who are to gain special professional competence; (d) examination commission; (e) examination of special professional competence of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources; (f) granting permission to perform activities of selected personnel; and (g) scope and structure of documentation required to permit professional training of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources. (P.A.)

Nuclear Station Facilities Improvement Planning

International Nuclear Information System (INIS)

Hooks, R. W.; Lunardini, A. L.; Zaben, O.

1991-01-01

An effective facilities improvement program will include a plan for the temporary relocation of personnel during the construction of an adjoining service building addition. Since the smooth continuation of plant operation is of paramount importance, the phasing plan is established to minimize the disruptions in day-to-day station operation and administration. This plan should consider the final occupancy arrangements and the transition to the new structure; for example, computer hookup and phase-in should be considered. The nuclear industry is placing more emphasis on safety and reliability of nuclear power plants. In order to do this, more emphasis is placed on operations and maintenance. This results in increased size of managerial, technical and maintenance staffs. This in turn requires improved office and service facilities. The facilities that require improvement may include training areas, rad waste processing and storage facilities, and maintenance facilities. This paper discusses an approach for developing an effective program to plan and implement these projects. These improvement projects can range in magnitude from modifying a simple system to building a new structure to allocating space for a future project. This paper addresses the planning required for the new structures with emphasis on site location, space allocation, and internal layout. Since facility planning has recently been completed by Sargent and Leyden at six U. S. nuclear stations, specific examples from some of those plants are presented. Site planning and the establishment of long-range goals are of the utmost importance when undertaking a facilities improvement program for a nuclear station. A plan that considers the total site usage will enhance the value of both the new and existing facilities. Proper planning at the beginning of the program can minimize costs and maximize the benefits of the program

Physical security of nuclear facilities

International Nuclear Information System (INIS)

Dixon, H.

1987-01-01

A serious problem with present security systems at nuclear facilities is that the threats and standards prepared by the NRC and DOE are general, and the field offices are required to develop their own local threats and, on that basis, to prepared detailed specifications for security systems at sites in their jurisdiction. As a result, the capabilities of the systems vary across facilities. Five steps in particular are strongly recommended as corrective measures: 1. Those agencies responsible for civil nuclear facilities should jointly prepare detailed threat definitions, operational requirements, and equipment specifications to protect generic nuclear facilities, and these matters should be issued as policy. The agencies should provide sufficient detail to guide the design of specific security systems and to identify candidate components. 2. The DOE, NRC, and DOD should explain to Congress why government-developed security and other military equipment are not used to upgrade existing security systems and to stock future ones. 3. Each DOE and NRC facility should be assessed to determine the impact on the size of the guard force and on warning time when personnel-detecting radars and ground point sensors are installed. 4. All security guards and technicians should be investigated for the highest security clearance, with reinvestigations every four years. 5. The processes and vehicles used in intrafacility transport of nuclear materials should be evaluated against a range of threats and attack scenarios, including violent air and vehicle assaults. All of these recommendations are feasible and cost-effective. The appropriate congressional subcommittees should direct that they be implemented as soon as possible

Some aspects of increasing the quality of personnel training for nuclear power plants in Czechoslovakia

International Nuclear Information System (INIS)

Jacko, J.; Frimmelova, A.

1989-01-01

Nuclear power plant personnel in Czechoslovakia is subject to periodical training in accordance with the Unified System of Nuclear Facility Personnel Training. This training is the responsibility of the Educational and Training Centre of the Nuclear Plant Research Institute in Trnava. Nuclear plant personnel is divided into 7 groups as follows: A - supervisory technical-administrative management staff; B - selected operating personnel such as shift supervisors, unit supervisors, reactor operators and secondary circuit operators; C - engineering-technical personnel of technical and maintenance departments; D - managing shift-operating staff; E - workers at technical plant departments; F - operational shift workers and servicemen; and G - maintenance personnel. These groups are respected in the training, which includes basic training, re-training and additional training. The basic training comprises 8 stages: general theoretical education; specialized theoretical education; on-the-job training in a plant designated for training; training on a simulator (group B); preparing for and taking final examinations for the certificate; doubling in the NPP designated for training (groups B, D, F); preparation in the NPP of future employment; preparing for and taking the state examination for obtaining the license (group B). Details of the management of the training process, experience gained during the implementation of the training and challenges for future improvement of the system are outlined. (P.A.)

User's guide for evaluating physical security capabilities of nuclear facilities by the EASI method

International Nuclear Information System (INIS)

Bennett, H.A.

1977-06-01

This handbook is a guide for evaluating physical security of nuclear facilities using the ''Estimate of Adversary Sequence Interruption (EASI)'' method and a hand-held programmable calculator. The handbook is intended for use by personnel at facilities where special nuclear materials are used, processed, or stored. It may also be used as a design aid for such facilities by potential licensees

Development of methods for nuclear power plant personnel qualifications and training

International Nuclear Information System (INIS)

Jorgensen, C.C.; Carter, R.J.

1984-01-01

The Nuclear Regulatory Commission (NRC) has proposed additions and revisions to Title 10 of the Code of Federal Regulations, Parts 50 and 55, and to Regulatory Guides 1.8 and 1.149. ORNL is developing methods and some aspects of the technical basis for the implementation and assessment of training programs, personnel qualifications, and simulation facilities. The paper describes the three methodologies which were developed during the FY-1984 research: a task sort procedure (TSORT); a simulation facility evaluation methodology; and a task analysis profiling system (TAPS)

Seismic design considerations for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Soni, R.S.; Kushwaha, H.S.; Venkat Raj, V.

2001-01-01

During the last few decades, there have been considerable advances in the field of a seismic design of nuclear structures and components housed inside a Nuclear power Plant (NPP). The seismic design and qualification of theses systems and components are carried out through the use of well proven and established theoretical as well as experimental means. Many of the related research works pertaining to these methods are available in the published literature, codes, guides etc. Contrary to this, there is very little information available with regards to the seismic design aspects of the nuclear fuel cycle facilities. This is probably on account of the little importance attached to these facilities from the point of view of seismic loading. In reality, some of these facilities handle a large inventory of radioactive materials and, therefore, these facilities must survive during a seismic event without giving rise to any sort of undue radiological risk to the plant personnel and the public at large. Presented herein in this paper are the seismic design considerations which are adopted for the design of nuclear fuel cycle facilities in India. (author)

Applying new safeguards technology to existing nuclear facilities

International Nuclear Information System (INIS)

Harris, W.J.; Wagner, E.P.

1979-01-01

The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is desinged for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both safeguards and production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

Applying new safeguards technology to existing nuclear facilities

International Nuclear Information System (INIS)

Johnson, C.E.; Wagner, E.P.

1979-01-01

The application and operation of safeguards instrumentation in a facility containing special nuclear material is most successful when the installation is designed for the operation of the specific facility. Experience at the Idaho National Engineering Laboratory demonstrates that installation designs must consider both Safeguards and Production requirements of specific facilities. Equipment selection and installation design influenced by the training and experience of production operations and safeguards personnel at a specific facility help assure successful installation, reliable operation, and minimal operator training. This minimizes impacts on existing plant production activities while maximizing utility of the safeguards information obtained

Occupational exposure of nuclear medicine personnel

International Nuclear Information System (INIS)

Roessler, M.

1982-01-01

The results are given of measurements of the radiation burden of personnel in departments of nuclear medicine in the years 1979 to 1981 using film dosemeters and ring thermoluminescence dosemeters evaluated by the national personnel dosemeter service. The relations are examined of the exposure of hands and the preparation of radiopharmaceuticals and especially their use for examinations. Certain organizational measures are indicated for reducina radiation burden in a laboratory for the preparation of radiopharmaceuticals. The results of measurements and evaluations of radiation burden of personnel of nuclear medicine departments are confronted with conclusions published in the literature. (author)

Principles for enhancing professionalism of nuclear personnel

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-03-01

The management principles in this publication were developed by a committee of senior utility officials with assistance by the staff of the Institute of Nuclear Power Operations (INPO) and with input from virtually all U.S. nuclear utilities. The principles are aimed at creating an environment within a nuclear power plant that promotes a healthy respect for the unique technology that nuclear electric power represents and, thus, to promote great care and conservative, thoughtful decision-making by the nuclear plant staff. The scope of the principles includes all nuclear personnel and gives guidance in the selection and development of management and supervisory personnel and other key individuals in the areas of operations, maintenance, technical support and engineering. Utility managers are encouraged to make in-depth comparisons between these principles and their day-to-day policies and practices, and to use such efforts as opportunities to communicate their organization's management philosophy to all nuclear personnel.

Principles for enhancing professionalism of nuclear personnel

International Nuclear Information System (INIS)

1989-01-01

The management principles in this publication were developed by a committee of senior utility officials with assistance by the staff of the Institute of Nuclear Power Operations (INPO) and with input from virtually all U.S. nuclear utilities. The principles are aimed at creating an environment within a nuclear power plant that promotes a healthy respect for the unique technology that nuclear electric power represents and, thus, to promote great care and conservative, thoughtful decision-making by the nuclear plant staff. The scope of the principles includes all nuclear personnel and gives guidance in the selection and development of management and supervisory personnel and other key individuals in the areas of operations, maintenance, technical support and engineering. Utility managers are encouraged to make in-depth comparisons between these principles and their day-to-day policies and practices, and to use such efforts as opportunities to communicate their organization's management philosophy to all nuclear personnel

Testing lifting systems in nuclear facilities

International Nuclear Information System (INIS)

Kling, H.; Laug, R.

1984-01-01

Lifting systems in nuclear facilities must be inspected at regular intervals after having undergone their first acceptance test. These inspections are frequently carried out by service firms which not only employ the skilled personnel required for such jobs but also make available the necessary test equipment. The inspections in particular include a number of sophisticated load tests for which test load systems have been developed to allow lifting systems to be tested so that reactor specific boundary conditions are taken into account. In view of the large number of facilities to be inspected, the test load system is a modular system. (orig.) [de

Decommissioning of nuclear power facilities

International Nuclear Information System (INIS)

Nosovskij, A.V.; Vasil'chenko, V.N.; Klyuchnikov, A.A.; Yashchenko, Ya.V.

2005-01-01

This is the first manual in Ukraine giving the complete review of the decommissioning process of the nuclear power facilities including the issues of the planning, design documentation development, advanced technology description. On the base of the international and domestic experience, the issues on the radwaste management, the decontamination methods, the equipment dismantling, the remote technology application, and also the costs estimate at decommissioning are considered. The special attention to the personnel safety provision, population and environment at decommissioning process is paid

Concerning control of radiation exposure to workers in nuclear reactor facilities for testing and nuclear reactor facilities in research and development phase (fiscal 1987)

International Nuclear Information System (INIS)

1988-01-01

A nuclear reactor operator is required by the Nuclear Reactor Control Law to ensure that the radiation dose to workers engaged in the operations of his nuclear reactor is controlled below the permissible exposure doses that are specified in notifications issued based on the Law. The present note briefly summarizes the data given in the Reports on Radiation Control, which have been submitted according to the Nuclear Reactor Control Law by the operators of nuclear reactor facilities for testing and those in the research and development phase, and the Reports on Control of Radiation Exposure to Workers submitted in accordance with the applicable administrative notices. According to these reports, the measured exposure to workers in 1987 were below the above-mentioned permissible exposure doses in all these nuclear facilities. The 1986 and 1987 measurements of radiation exposure dose to workers in nuclear reactor facilities for testing are tabulated. The measurements cover dose distribution among the facilities' personnel and workers of contractors. They also cover the total exposure dose for all workers in each of four plants operated under the Japan Atomic Energy Research Institute and the Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

Building a medical system for nuclear facilities

International Nuclear Information System (INIS)

Maeda, Mitsuya

2016-01-01

To build a medical system for nuclear facilities, I explained what kinds of actions were performed with the TEPCO Fukushima Daiichi Nuclear Power Plant Accident and what kinds of actions are going to be performed in the future. We examined the health and medical care of the emergency workers in nuclear facilities including TEPCO Fukushima Daiichi Nuclear Power Plant from 2014 to 2015 in the Ministry of Health, Labour and Welfare (MHLW). We carried out a detailed hearing from stakeholders of electric companies and medical institutions about the medical system in nuclear facilities carrying out urgent activities. It has been said that the electric company is responsible to maintain the medical system for affected workers in nuclear facilities. However, TEPCO could not find the medical staff, such as doctors, by their own effort at the TEPCO Fukushima Daiichi Nuclear Power Plant Accident. The network of doctors familiar with emergency medical care support dispatched the medical staff after July of 2011. The stakeholders indicated that the following six tasks must be resolved: (1) the fact that no electric company performs the action of bringing up medical staff who can be dispatched into nuclear facilities in emergencies in 2015; (2) bringing up personnel in charge of radiation management and logistics other than the medical staff, such as doctors; (3) cooperation with the community medicine system given the light and shade by nuclear facilities; (4) performing training for the many concurrent wounded based on the scenario of a severe accident; (5) indicating both the condition of the contract and the guarantee of status that is appropriate for dispatched medical staffs; and (6) clarifying the organization of the network of stakeholders. The stakeholders showed the future directionality as follows: (1) To recruit the medical staff expected to be dispatched into nuclear facilities, (2) to carry out the discussion and conveyance training to strengthen cooperation with

Saint-Laurent-des-Eaux nuclear facilities. 2009 annual report

International Nuclear Information System (INIS)

2010-01-01

This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of Saint-Laurent-des-Eaux, and then the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities, administrative procedures carried out in 2009), incidents and accidents registered in 2009, radioactive and chemical effluents released by the facilities in the environment, other pollutions, management of radioactive wastes, and, finally, the actions carried out in the domain of transparency and public information. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

Qualification of quality assurance program audit personnel for nuclear power plants - August 1980

International Nuclear Information System (INIS)

Anon.

1981-01-01

Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, to 10 CFR Part 50, Domestic Licensing of Production and Utilization Facilities, establishes overall quality assurance requirements for the design, construction, and operation of safety-related structures, and components of nuclear power plants. Criterion XVIII, Audits, of Appendix B establishes requirements for conducting audits of the quality assurance program. This guide describes a method acceptable to the NRC staff for complying with the Commission's regulations with regard to qualification of quality assurance program audit personnel for nuclear power plants

DoD Nuclear Weapons Personnel Reliability Assurance

Science.gov (United States)

2016-04-27

systems, positive control material (PCM) and equipment, and special nuclear material (SNM) and subject to a nuclear weapons personnel reliability...assurance implementation guidance for consistency and compliance with this issuance. c. Conducts programmatic reviews, manages audits , and directs...personnel reliability assurance education and training materials . 2.4. ASSISTANT SECRETARY OF DEFENSE FOR HEALTH AFFAIRS (ASD(HA)). Under the authority

Use of control room simulators for training of nuclear power plant personnel

International Nuclear Information System (INIS)

2004-09-01

Safety analysis and operational experience consistently indicate that human error is the greatest contributor to the risk of a severe accident in a nuclear power plant. Subsequent to the Three Mile Island accident, major changes were made internationally in reducing the potential for human error through improved procedures, information presentation, and training of operators. The use of full scope simulators in the training of operators is an essential element of these efforts to reduce human error. The operators today spend a large fraction of their time training and retraining on the simulator. As indicated in the IAEA Safety Guide on Recruitment, Qualification and Training of Personnel for Nuclear Power Plants, NS-G-2.8, 2002, representative simulator facilities should be used for training of control room operators and shift supervisors. Simulator training should incorporate normal, abnormal and accident conditions. The ability of the simulator to closely represent the actual conditions and environment that would be experienced in a real situation is critical to the value of the training received. The objective of this report is to provide nuclear power plant (NPP) managers, training centre managers and personnel involved with control room simulator training with practical information they can use to improve the performance of their personnel. While the emphasis in this publication is on simulator training of control room personnel using full scope simulators, information is also provided on how organizations have effectively used control room simulators for training of other NPP personnel, including simulators other than full-scope simulators

Site security personnel training manual

International Nuclear Information System (INIS)

1978-10-01

As required by 10 CFR Part 73, this training manual provides guidance to assist licensees in the development of security personnel training and qualifications programs. The information contained in the manual typifies the level and scope of training for personnel assigned to perform security related tasks and job duties associated with the protection of nuclear fuel cycle facilities and nuclear power reactors

Automated entry control system for nuclear facilities

International Nuclear Information System (INIS)

Ream, W.K.; Espinoza, J.

1985-01-01

An entry control system to automatically control access to nuclear facilities is described. The design uses a centrally located console, integrated into the regular security system, to monitor the computer-controlled passage into and out of sensitive areas. Four types of entry control points are used: an unmanned enclosed portal with metal and SNM detectors for contraband detection with positive personnel identification, a bypass portal for contraband search after a contraband alarm in a regular portal also with positive personnel identification, a single door entry point with positive personnel identification, and a single door entry point with only a magnetic card-type identification. Security force action is required only as a response to an alarm. The integration of the entry control function into the security system computer is also described. The interface between the entry control system and the monitoring security personnel utilizing a color graphics display with touch screen input is emphasized. 2 refs., 7 figs

Work performed by the nuclear industry - personnel structure and personnel requirement

International Nuclear Information System (INIS)

Simon, M.

1984-01-01

The development of the nuclear industry in the Federal Republic of Germany can be phased as follows: Phase 1 (1956-1968): initial stage, Phase 2 (1968-1975): expansion of the business volume, Phase 3 (1975-1982): decreasing business volume, more conditions and technical requirements, Phase 4 (after 1982): consolidation of technologies and project management. Accordingly, the requirements made on the personnel employed in the nuclear industry had to change. Between 1982 and today, there has been a decrease of personnel employed in nuclear industry to about 35.000. This decrease is mainly due to the supplying industry. Adding to this figure the number of people employed in research centres, authorities and experts, there are over 40.000 nuclear technology jobs, a figure which, taking into account indirect employment effect, could be in the range of 100.000 to 150.000. (orig./HSCH) [de

Nuclear power plant personnel training process management system

International Nuclear Information System (INIS)

Arjona Vazquez, Orison; Venegas Bernal, Maria del Carmen; Armeteros Lopez, Ana L.

1996-01-01

The system in charge the management of the training process personnel from a nuclear power plant was designed taking into account all the requirements stated in the training guide for nuclear power plant personnel and their evaluation, which were prepared by the IAEA in 1995 in order to implement the SAT in the training programs for nuclear plant personnel. In the preparations of formats and elements that shape the system, account has been taken of the views expressed in such a guide, in some other bibliography that was consulted, and in the authors own opinion mainly with regard to those issues which the guide does not go deeper into

Potential Benefits to the Philippines of a Nuclear Facility

International Nuclear Information System (INIS)

Asuncion-Astronomo, A.; Romallosa, K.M.D.; Olivares, R.U.

2015-01-01

During the late 1950’s, the Philippines was one of the many countries which began the pursuit of the beneficial applications of atomic energy. With the commissioning of the first Philippine Research Reactor (PRR-1) which attained its first criticality in 1963, our country had the capability for radioisotope production, activation analysis of materials, irradiation studies and various opportunities for basic and applied nuclear science research. The Nuclear Power Plant (PNNP-1) in training plant operators and regulators for the first Philippine Nuclear Power Plant (PNPP-1) in Bataan, which was eventually mothballed in 1986. It is thus unfortunate that the only operating nuclear facility in the country, the PRR-1 encountered technical problems during an upgrade and was shut down in 1988. The problem was not resolved and eventually led to the decommissioning of the PRR-1 in 2005. Without an operating nuclear facility available in the country, the number of personnel knowledgeable and skilled in reactor and nuclear science and engineering has greatly declined and lagged behind our counterparts. This has been the situation for more than two decaded and can only be addressed if the country decides to put up a new nuclear facility. It is acknowledged that putting up a nuclear facility is a major undertaking which requires careful planning, preparation and investment. Thus, a decision by any country to embark on this poster, we will provide an overview of the many potential benefits as well as challenges of establishing a new research reactor and/or accelerator facility in the country. The global distribution, comparisons, capabilities and the different application of these facilities will presented as well.(author)

Occupational radiation exposure in nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1979-01-01

Full text: This symposium forms an essential part of the continuing tradition of subjecting nuclear energy to periodic review to assess the adequacy of radiation protection practices and experiences and to identify those areas needing further study and development. Specifically, the symposium focused on a review of statistical data on radiation exposure experience to workers in the nuclear fuel cycle through 1978. The technical sessions were concerned with occupational exposures: experienced in Member States; in research and development facilities; in nuclear power plants; in nuclear Fuel reprocessing facilities; in waste management facilities; and techniques to minimize doses. A critical review was made of internal and external exposures to the following occupational groups: uranium miners; mill workers; fuel fabricators; research personnel, reactor workers; maintenance staff; hot cell workers; reprocessing plant personnel; waste management personnel. In particular, attention was devoted to the work activities causing the highest radiation exposures and successful techniques which have been used to minimize individual and collective doses. Also there was an exchange of information on the trends of occupational exposure over the lifespan of individual nuclear power plants and other facilities in the nuclear fuel cycle. During the last session there was a detailed panel discussion on the conclusions and future needs highlighted during the symposium. While past symposia on nuclear power and its fuel cycle have presented data on occupational dose statistics, this symposium was the first to focus attention on the experience and trends of occupational exposure in recent years. The papers presented an authoritative account of the status of the levels and trends of the average annual individual dose as well as the annual collective dose for occupational workers in most of the world up to 1979. From the data presented it became evident that considerable progress has been

Transportation security personnel training manual

International Nuclear Information System (INIS)

1978-11-01

Objective of this manual is to train security personnel to protect special nuclear materials and nuclear facilities against theft and sabotage as required by 10 CFR Part 73. This volume contains the introduction and rationale

Risk perception among nuclear power plant personnel: A survey

International Nuclear Information System (INIS)

Kivimaeki, M.; Kalimo, R.

1993-01-01

This study investigated risk perception, well-being, and organizational commitment among nuclear power plant personnel. The study group, 428 employees from a nuclear power plant, completed a questionnaire which included the same questions as those in previous surveys on risk perception of lay persons and industrial workers. Hazards at work were not seen as a sizable problem by nuclear power plant personnel. The study group estimated the safety of nuclear power plants better and the possibility of a serious nuclear accident as more unlikely than the general public. Compared to employees in other industrial companies, the overall perceived risks at work among plant personnel did not exceed the respective perceptions of the reference groups. Risk-related attitudes did not explain well-being among plant personnel, but the relationship between the perceived probability of a serious nuclear accident at work and organizational commitment yielded to a significant correlation: Those plant workers who estimated the likelihood of an accident higher were less committed to the organization. 21 refs., 2 tabs

Qualification of nuclear power plant operations personnel

International Nuclear Information System (INIS)

1984-01-01

With the ultimate aim of reducing the possibility of human error in nuclear power plant operations, the Guidebook discusses the organizational aspects, the staffing requirements, the educational systems and qualifications, the competence requirements, the ways to establish, preserve and verify competence, the specific aspects of personnel management and training for nuclear power plant operations, and finally the particular situations and difficulties to be overcome by utilities starting their first nuclear power plant. An important aspect presented in the Guidebook is the experience in training and qualification of nuclear power plant personnel in various countries: Argentina, Belgium, Canada, Czechoslovakia, France, Federal Republic of Germany, Spain, Sweden, United Kingdom and United States of America

Basic training of nuclear power reactor personnel

International Nuclear Information System (INIS)

Palabrica, R.J.

1981-01-01

The basic training of nuclear power reactor personnel should be given very close attention since it constitutes the foundation of their knowledge of nuclear technology. Emphasis should be given on the thorough understanding of basic nuclear concepts in order to have reasonable assurance of successful assimilation by those personnel of more specialized and advanced concepts to which they will be later exposed. Basic training will also provide a means for screening to ensure that those will be sent for further spezialized training will perform well. Finally, it is during the basic training phase when nuclear reactor operators will start to acquire and develop attitudes regarding reactor operation and it is important that these be properly founded. (orig.)

Reports and operational engineering: An independent safety assessment of Department of Energy nuclear reactor facilities

International Nuclear Information System (INIS)

Rochman, A.; Washburn, B.W.

1981-02-01

The Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee, established via an October 24, 1979 memorandum from the Department of Energy (DOE) Under Secretary, was instructed to review the ''Kemeny Commission'' recommendations and to identify possible implications for DOE's nuclear facilities. As a result of this review, the Committee recommended that DOE carry out assessments in seven categories. The assessments would address specific topics identified for each category as delineated in the NFPQT ''Guidelines for Assessing the Safe Operation of DOE-Owned Reactors,'' dated May 7, 1980. The Committee recognized that similar assessments had been ongoing in the DOE program and safety overview organizations since the Three Mile Island nuclear accident and it was the Committee's intent to use the results of those ongoing assessments as an input to their evaluations. This information would be supplemented by additional studies consisting of the subject-related documents used at each reactor facility studied, and an on-site review of these reactor facilities by professional personnel within the Department of Energy, its operating contractors and independent consultants. 1 tab

Experience with training of operating and maintenance personnel of nuclear power plants

International Nuclear Information System (INIS)

Pospisil, M.; Cencinger, F.

1988-01-01

The system is described of the specialist training of personnel for Czechoslovak nuclear power plants. Training consists of basic training, vocational training and training for the respective job. Responsible for the training is the Research Institute for Nuclear Power Plants; actual training takes place at three training centres. Personnel are divided into seven categories for training purposes: senior technical and economic staff, shift leaders, whose work has immediate effect on nuclear safety, engineering and technical personnel of technical units, shift leaders of technical units, personnel in technical units, shift service personnel and operating personnel, maintenance workers. Experience with training courses run at the training centre is summed up. Since 1980 the Centre has been training personnel mainly for the Dukovany nuclear power plant. Recommendations are presented for training personnel for the Temelin nuclear power plant. (Z.M.)

An automated entry control system for nuclear facilities

International Nuclear Information System (INIS)

Ream, W.K.; Espinoza, J.

1985-01-01

An entry control system to automatically control access to nuclear facilities is described. The design uses a centrally located console, integrated into the regular security system, to monitor the computer-controlled passage into and out of sensitive areas. Four types of entry control points are used: an unmanned enclosed portal with metal and SNM detectors for contraband detection with positive personnel identification, a bypass portal for contraband search after a contraband alarm in a regular portal also with positive personnel identification, a single door entry point with positive personnel identification, and a single door entry point with only a magnetic card-type identification. Security force action is required only as a response to an alarm. The integration of the entry control function into the security system computer is also described. The interface between the entry control system and the monitoring security personnel utilizing a color graphics display with touch screen input is emphasized

Personnel training at EDF's nuclear and fossil generation division and its application for the personnel of a nuclear power station abroad

International Nuclear Information System (INIS)

Rabouhams, J.

1991-01-01

Safety in nuclear power stations relies so much upon human competence that the training of the personnel has to respond to the basic need of having personnel who are competent in their job permanently available. EDF has designed, organized and managed a large volume of training in order to provide its personnel involved in the operation of nuclear power station with initial training, training, retraining and improvement within the framework of quality organization. To deal with this training in the most efficient way EDF has developed various training aids ranging from booklets to fullscope simulator or fullscope mockups which are continually updated. All EDF experience has been used to train Daya Bay nuclear power plant personnel who have been monitored throughout the training programmes. Adequate safety conduct and attitudes including the socio-cultural background have been developed during the training. The principle teaching method was shadow training in other words the transfer in situ of knowledge, know how, and conduct from an experienced engineer. (author)

Self-imposed self-assessment program at a DOE Nuclear Facility

International Nuclear Information System (INIS)

Geoffrion, R.R.; Loud, J.J.; Walter, E.C.

1996-01-01

The Nuclear Materials and Technology (NMT) Division at Los Alamos National Laboratory (LANL) has implemented a performance-based self-assessment program at the TA-55 plutonium facility. The program was conceptualized and developed by LANL's internal assessment group, AA-2. The management walkaround program fosters continuous improvement in NMT products and performance of its activities. The program, based on experience from the Institute of Nuclear Power Operations, is endorsed at the site by the U.S. Department of Energy (DOE) Environment, Safety, and Health (ES ampersand H) personnel and by the Defense Nuclear Facility Safety Board. The self-assessment program focuses on how work is actually performed rather than on paperwork or process compliance. Managers critically and continually assess ES ampersand H, conduct of operations, and other functional area requirements

Certification of Canadian nuclear power plant personnel

International Nuclear Information System (INIS)

Newbury, F.

2014-01-01

The Canadian Nuclear Safety Commission (CNSC) regulates the use of nuclear energy and materials to protect health, safety, security of Canadians and the environment, and to implement Canada's international commitments on the peaceful use of nuclear energy. As part of its mandate, the CNSC requires certification of those who work in positions with direct impact on the safety of Canadian nuclear power plants (NPPs) and research reactors. Other positions, such as exposure device operators and radiation safety officers at other nuclear facilities, also require CNSC certification. In this paper, the certification process of Canadian NPP personnel will be examined. In keeping with the CNSC's regulatory philosophy and international practice, licensees bear the primary responsibility for the safe operation of their NPPs. They are therefore held entirely responsible for training and testing their workers, in accordance with applicable regulatory requirements, to ensure they are fully qualified to perform their duties. The CNSC obtains assurance that all persons it certifies are qualified to carry out their respective duties. It achieves this by overseeing a regime of licensee training programs and certification examinations, which are based on a combination of appropriate regulatory guidance and compliance activities. Reviews of the knowledge-based certification examination methodology and of lessons learned from Fukushima have generated initiatives to further strengthen the CNSC's certification programs for NPP workers. Two of those initiatives are discussed in this paper. (author)

Operation technology of air treatment system in nuclear facilities

CERN Document Server

Chun, Y B; Hwong, Y H; Lee, H K; Min, D K; Park, K J; Uom, S H; Yang, S Y

2001-01-01

Effective operation techniques were reviewed on the air treatment system to protect the personnel in nuclear facilities from the contamination of radio-active particles and to keep the environment clear. Nuclear air treatment system consisted of the ventilation and filtering system was characterized by some test. Measurement of air velocity of blowing/exhaust fan in the ventilation system, leak tests of HEPA filters in the filtering, and measurement of pressure difference between the areas defined by radiation level were conducted. The results acquired form the measurements were reflected directly for the operation of air treatment. In the abnormal state of virus parts of devices composted of the system, the repairing method, maintenance and performance test were also employed in operating effectively the air treatment system. These measuring results and techniques can be available to the operation of air treatment system of PIEF as well as the other nuclear facilities in KAERI.

IAEA activities in nuclear power plant personnel training and qualification

International Nuclear Information System (INIS)

Mautner-Markhof, F.

1993-01-01

Training to achieve and maintain the qualification and competence of nuclear power personnel is essential for safe and economic nuclear power. Technical Cooperation Meeting on Training-Related Activities for Nuclear Power Plant (NPP) Personnel in the countries of Central and Eastern Europe (CEEC) and of the former Soviet Union (FSU) has as its main objective the identification, through information exchange and discussion, of possible Technical Cooperation (TC) projects to assist Member States in meeting NPP personnel training needs and priorities, including the enhancing of training capabilities

The effects of the Brazilian regulatory inspection programme on nuclear medicine facilities

Energy Technology Data Exchange (ETDEWEB)

Alves, C E G R; Azevedo, E M; Mendes, L C G; Franca, W F L; Gutterres, R F; Goncalves, M [Comissao Nacional de Energia Nuclear-CGMI/CNEN, Rua General Severiano 90, 22290-901, Rio de Janeiro (Brazil); De Sa, L V; Da Rosa, L A R [Instituto de Radioprotecao e Dosimetria-IRD/CNEN, Avenida Salvador Allende s/n, 22780-160, Rio de Janeiro (Brazil)], E-mail: telo@xexeu.org

2009-12-01

This paper aims to demonstrate the importance of the regulatory inspections carried out by the Brazilian regulatory body in the area of nuclear medicine. The main aspects observed during the inspections are presented as well as the time evolution of the non-compliances, according to their occurrence by type. We also evaluate factors concerning the working of the nuclear medicine facility responsible for solving the non-compliances. The results suggest a decrease of occurrence of non-compliances with time that can be related to the strictness of the inspections and the awareness of the personnel in the nuclear medicine facilities. An analysis of radiation dose exposure levels for the professionals involved in nuclear medicine was carried out; although dose values are below regulatory dose limits, their occurrence is not decreasing satisfactorily. Results indicate the need for staff training and commitment of the responsible nuclear medicine facility staff to the radiological protection procedures. Our results also emphasise the importance of continuous coercive actions to improve the level of radiological protection in nuclear medicine facilities in compliance with the standards established by the national regulatory authority and international recommendations.

Qualification of NDE personnel in the nuclear industry

International Nuclear Information System (INIS)

Epps, T.N.

1984-01-01

There has been evidence of ineffective programs for certifying nondestructive examination (NDE) personnel who conduct periodic inservice examinations in nuclear power plants under ASME Section XI Code requirements. This was brought to the attention of a group from the electric utility industry, the Electric Power Research Institute (EPRI), some NDE consultants and representatives from the American Society of Mechanical Engineers (ASME) by the Nuclear Regulatory Commission (NRC) in a May, 1982 meeting in Bethesda, Maryland. One problem pointed out by the NRC was the lack of a clear definition of qualification requirements for certification of NDE personnel who conduct ASME Section XI Inservice Inspection work in nuclear power plants. The NRC requested that the nuclear industry resolve this problem by formulating definitive qualification requirements for personnel certification that could be made an industry requirement. In June, 1982 the EPRI NDE Subcommittee held a general meeting for utility representatives to discuss the results of the May, 1982 meeting to develop a plan for industry response to the issue. The consensus was that an Ad Hoc Committee of utility representatives be convened to develop a document outlining qualification requirements for vertification of NDE personnel. The Ad Hoc Committee was formally convened on September 29, 1982

NPP safety and personnel training. XII International conference. Abstracts

International Nuclear Information System (INIS)

2011-01-01

The 12th International conference NPP Safety and Personnel Training took place in Obninsk, October 4-7, 2011. The issues of nuclear technologies safety are considered.The problems of life-cycle management of nuclear facilities are discussed. The criteria of assessment of physical protection systems of nuclear facilities are presented [ru

Nuclear facilities of EdF's operational hot base of Tricastin. 2009 annual report

International Nuclear Information System (INIS)

2010-01-01

This annual report is established on account of article 21 of the 2006-686 French law from June 13, 2006, relative to the transparency and safety in the nuclear domain. It describes, first, the nuclear facilities of the EdF operational hot base of Tricastin, then, the measures taken to ensure their safety (personnel radioprotection, actions implemented for nuclear safety improvement, organisation in crisis situation, external and internal controls, technical assessment of the facilities), and finally the procedures of management of radioactive wastes. A glossary and the viewpoint of the Committee of Hygiene, safety and working conditions about the content of the document conclude the report. (J.S.)

An independent safety assessment of Department of Energy nuclear reactor facilities: Procedures, operations and maintenance

International Nuclear Information System (INIS)

Toto, G.; Lindgren, A.J.

1981-02-01

The 1979 accident at the Three Mile Island commercial nuclear power plant has led to a number of studies of nuclear reactors, in both the public and private sectors. One of these is that of the Department of Energy's (DOE) Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee, which has outlined tasks for assessment of 13 reactors owned by DOE and operated by contractors. This report covers one of the tasks, the assessment of procedures, operations, and maintenance at the DOE reactor facilities, based on a review of actual documents used at the reactor sites

Selection, qualification and training of personnel for nuclear power plants

International Nuclear Information System (INIS)

Anon.

1981-01-01

This standard provides criteria for the selection, qualification and training of personnel for stationary nuclear power plants. Qualifications, responsibilities, and training of personnel in operating and support organizations appropriate for the safe and efficient operation of nuclear power plants are addressed

Nuclear security. DOE actions to improve the personnel clearance program

International Nuclear Information System (INIS)

Fultz, Keith O.; Bannerman, Carl J.; Daniel, Beverly A.

1988-11-01

The status of the Department of Energy's (DOE) implementation of recommendations in our two reports on DOE's personnel security clearance program was determined. The recommendations were aimed at improving the timeliness, accuracy, and efficiency of personnel security clearance decisions. Specifically, the objective was to determine and report on steps DOE is taking to implement these recommendations. In summary, it was found that DOE has either initiated action or is studying ways to address all the recommendations, but none of the recommendations have been completely implemented. The effectiveness of the DOE actions will depend, in part, on the adequacy of its internal control system for overseeing and evaluating program operations. DOE's personnel security clearance program is intended to provide reasonable assurance that personnel with access to classified information and materials are trustworthy. The Department requests that the Office of Personnel Management or the Federal Bureau of Investigation collect personal data on each person who requires such access to do his or her job. Based on these background investigations, DOE officials authorize individuals whose personal histories indicate that they are trustworthy to have access to classified information, secured facilities, and controlled materials as needed to perform their jobs. DOE has five types of these authorizations or personnel security clearances and must update information on personnel holding each type at 5-year intervals to confirm their continuing reliability. The five types are based on the types of security interests to which the person needs access, e.g., persons needing nuclear weapons-related data must have a Q clearance, and persons with a top secret clearance can have access to national security data classified as top secret

Control in personnel exposure at HIRUP facility during the period 2006-2010

International Nuclear Information System (INIS)

Ojha, Shashikala; Suman, Santosh Kumar; Murali, S.

2012-01-01

HIRUP facility is designed to handle MCi of 60 Co, fabrication of sealed source, is carried out in hot cell. The design safety features allow the handling of sealed sources and other gamma emitters under suitable containment systems. The NP Unit of the facility provides personnel monitoring programmes viz., TLD/DRD monitoring for the radiation workers. 60 Co and other gamma emitters pose mainly external hazard during the handling of sealed source in hot cell. TLD is processed to assess the external exposure of personnel. Air activity and gross bg contamination at the work place is periodically monitored and reported. The TLD users of HIRUP are periodically referred for internal monitoring - whole body counting and bio-assay to estimate internal exposure. There is no reported internal exposure so far. Personnel from IAD and BRIT facility are provided with personnel monitoring coverage by HP Unit; the TLD is issued with respective institution no. as - 0283, 4288. Each person gets identified by individual TLD number, renewed TLD issue on quarterly service period. Based on job requirement such as handling of high activity, additional Wrist TLDs are provided. The used TLD of IAD and BRIT are sent for processing. The dose report obtained, enlists personnel exposure details. HP Unit does the report making to the concerned agencies enlisting the operational status, total occupational exposure of the facility (person mSv), average exposure (mSv) and few other details. Details of exposure for 2006 - 2010 (non-zero exposure cases), indicate that for IAD collective exposure got reduced by 78.5 %, average exposure got reduced by 62.6 %; for BRIT collective exposure got reduced by 58.2 %, average exposure got reduced by 46.8 %, at HIRUP facility. There is a decreasing trend in personnel exposure over the period 2006-2010, is due to HP safety protocol, on job HP surveillance and related safety measures. The personnel exposure is controlled as per ALARA, decreasing trend in the

3. national conference on training of personnel for nuclear power

International Nuclear Information System (INIS)

Jacko, J.

1983-01-01

A national conference with international participation was held in Podbanske to evaluate the results and experiences with the training of personnel for nuclear power in training centres of the sector of fuel and energy, within the educational system and at other workplaces. The rational development of the system of personnel training must contribute towards reducing the hazards of nuclear power caused by the human factor. The results and experiences were evaluated gained in the process of the unified system of training personnel for nuclear power plants, namely training centres of various institutions, institutions of higher education and in-operation training of personnel. In 1984, the first Czechoslovak simulator of a WWER 440 unit will be put into operation. (M.D.)

Control in personnel exposure of RCD/FCD facility RLG during the period 2005 - 2008

International Nuclear Information System (INIS)

Murali, S.; Thanamani, S.; Sapkal, J.A.; Bairwa, Satya Manoj

2010-01-01

Full text: Radio Chemistry Wing, RLG, houses Radio Chemistry Division and Fuel Chemistry Division and certain common utility services. The personnel in the facility carry out radiochemical operations involving isotopes of Pu and other actinides. The HP Unit, Radio Chemistry Wing provides essential safety coverage to the personnel of the facility. The lab personnel of RCD/FCD facility at RLG carry out active operations, such operations held in suitable containment systems, under the HP supervision by RHC Unit advising safe work practices. The lab personnel are provided with monitoring programmes viz. TLD, Bio-assay and Lung counting periodically. Presently the dose limit for occupational exposure is 20 mSv per annum with 100 mSv for 5 consecutive calendar years. The present paper on TLD dose report enlists the details of the personnel exposure year wise and highlights the control in personnel exposure due to the safe procedures followed. The decreasing trend in the average personnel exposure over the period 2005 - 2008 validates the practice of adherence to safety procedures, though the amount of activity handled in the facility has increased by a few folds

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

Training of personnel for nuclear power in Ceske Energeticke Zavody Concern

International Nuclear Information System (INIS)

Hodny, J.; Krestan, J.

1983-01-01

The projects of training of personnel and recruitment of apprentices have to be started 10 years prior to the commissioning of a nuclear power plant. Training starts three years prior to the physical start-up. The education and training of personnel in the nuclear programme including the implementation of their social background is an equivalent component of nuclear safety. The most important aspects are presented of personnel training with regard to organization, recruitment, theoretical and practical education and training, material and technical provisions and social programme. At present personnel training and the education of specialists have reached a high standard but the problem of social care of personnel in future plants is serious and has not been solved. (M.D.)

Personnel reliability impact on petrochemical facilities monitoring system's failure skipping probability

Science.gov (United States)

Kostyukov, V. N.; Naumenko, A. P.

2017-08-01

The paper dwells upon urgent issues of evaluating impact of actions conducted by complex technological systems operators on their safe operation considering application of condition monitoring systems for elements and sub-systems of petrochemical production facilities. The main task for the research is to distinguish factors and criteria of monitoring system properties description, which would allow to evaluate impact of errors made by personnel on operation of real-time condition monitoring and diagnostic systems for machinery of petrochemical facilities, and find and objective criteria for monitoring system class, considering a human factor. On the basis of real-time condition monitoring concepts of sudden failure skipping risk, static and dynamic error, monitoring systems, one may solve a task of evaluation of impact that personnel's qualification has on monitoring system operation in terms of error in personnel or operators' actions while receiving information from monitoring systems and operating a technological system. Operator is considered as a part of the technological system. Although, personnel's behavior is usually a combination of the following parameters: input signal - information perceiving, reaction - decision making, response - decision implementing. Based on several researches on behavior of nuclear powers station operators in USA, Italy and other countries, as well as on researches conducted by Russian scientists, required data on operator's reliability were selected for analysis of operator's behavior at technological facilities diagnostics and monitoring systems. The calculations revealed that for the monitoring system selected as an example, the failure skipping risk for the set values of static (less than 0.01) and dynamic (less than 0.001) errors considering all related factors of data on reliability of information perception, decision-making, and reaction fulfilled is 0.037, in case when all the facilities and error probability are under

Review of the nuclear safety exercises carried out in French industrial facilities

International Nuclear Information System (INIS)

Kissel, Ph.P.; Renard, C.; Meramedjian, H.N.

1977-01-01

For several years the Commissariat a l'Energie Atomique (CEA) has been organizing nuclear safety exercises in most nuclear industrial facilities, especially in fuel element fabrication plants, many of which are classified as basic nuclear facilities. The subject and extent of each exercise are decided by mutual agreement between the management of the facility and the CEA officials in charge of Assistance in Protection and Nuclear Safety (APSN). The authors deal with such subjects as criticality accidents (evacuation of facilities, regrouping of personnel, rescue operations etc.) and fire involving large quantities of radioactive material (protection of the environment by spraying water on fumes laden with radioactive aerosols etc.). During these exercises use is made of the resources available with the safety services of the facility, one or more mobile nuclear action teams of the CEA and the appropriate resources within the competence of public authorities, e.g. Civil Defence, the fire brigades, the Gendarmerie etc. Each exercise is followed by a meeting which gives an opportunity for constructive criticism and for the adoption of measures best suited for solving problems which invariably arise, such as choice of methods and resources, co-ordination of their simultaneous or gradual application and so on. (author)

Survey of technology for decommissioning of nuclear fuel cycle facilities. 8. Remote handling and cutting techniques

Energy Technology Data Exchange (ETDEWEB)

Ogawa, Ryuichiro; Ishijima, Noboru [Japan Nuclear Cycle Development Inst., Oarai, Ibaraki (Japan). Oarai Engineering Center

1999-03-01

In nuclear fuel cycle facility decommissioning and refurbishment, the remote handling techniques such as dismantling, waste handling and decontamination are needed to reduce personnel radiation exposure. The survey research for the status of R and D activities on remote handling tools suitable for nuclear facilities in the world and domestic existing commercial cutting tools applicable to decommissioning of the facilities was conducted. In addition, the drive mechanism, sensing element and control system applicable to the remote handling devices were also surveyed. This report presents brief surveyed summaries. (H. Itami)

A new Brazilian regulation for the security of nuclear material and nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Tavares, Renato L.A.; Filho, Josélio S.M.; Torres, Luiz F.B.; Lima, Alexandre R., E-mail: renato.tavares@cnen.gov.br, E-mail: joselio@cnen.gov.br, E-mail: ltorres@cnen.gov.br, E-mail: alexandre.lima@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Diretoria de Radioproteção e Segurança Nuclear; Lima, Fabiano P.C., E-mail: fabianopetruceli@outlook.com [Presidência da República, Brasilia, DF (Brazil). Gabinete de Segurança Institucional

2017-07-01

The present paper aims to outline the challenges related to the elaboration and concepts involved in a regulatory transition from a purely prescriptive approach to a combined approach that mixes performance-based concepts and evaluation metrics based on statistical data of equipment and personnel. This methodology might represent an improvement compared to a purely prescriptive approach, in which the regulatory authority defines the measures to be taken by operators of nuclear facilities to prevent theft, sabotage events, and mitigate their consequences. The prescriptive approach, despite having the advantages of clarity in the definition of requirements, simplicity in regulatory terms (inspections to verify compliance), and homogeneity in relation to various facilities, does not allow a clear and effective performance measurement, may provide insufficient or excessive security measures (with excessive expenditure of material and human resources), and the possibility of providing a false sense of security. It is known that, in many countries, the state-sponsored nuclear security regime mixes elements of the two mentioned approaches, prescriptive and based on performance, which is not Brazilian practice nowadays. Such methodological developments happened globally due to the increase of threat level for nuclear facilities and materials. The currently regulation in force is CNEN-NE 2.01, which provides a set of measures intended to implement Physical Protection Systems in Nuclear, Radiological Facilities as well as Transport Operations, and all documents related to security of such issues. The new regulation, named CNEN-NN 2.01, will focus only on Nuclear Material and Facilities (two other regulations specific for Security of Radioactive Sources and Transport Operations are under elaboration process). CNEN NN 2.01 is intended to provide further adherence to new international recommendations, e.g, IAEA INFCIRC 225 Rev.5 (NSS 13), which is currently regarded as the â

A new Brazilian regulation for the security of nuclear material and nuclear facilities

International Nuclear Information System (INIS)

Tavares, Renato L.A.; Filho, Josélio S.M.; Torres, Luiz F.B.; Lima, Alexandre R.; Lima, Fabiano P.C.

2017-01-01

The present paper aims to outline the challenges related to the elaboration and concepts involved in a regulatory transition from a purely prescriptive approach to a combined approach that mixes performance-based concepts and evaluation metrics based on statistical data of equipment and personnel. This methodology might represent an improvement compared to a purely prescriptive approach, in which the regulatory authority defines the measures to be taken by operators of nuclear facilities to prevent theft, sabotage events, and mitigate their consequences. The prescriptive approach, despite having the advantages of clarity in the definition of requirements, simplicity in regulatory terms (inspections to verify compliance), and homogeneity in relation to various facilities, does not allow a clear and effective performance measurement, may provide insufficient or excessive security measures (with excessive expenditure of material and human resources), and the possibility of providing a false sense of security. It is known that, in many countries, the state-sponsored nuclear security regime mixes elements of the two mentioned approaches, prescriptive and based on performance, which is not Brazilian practice nowadays. Such methodological developments happened globally due to the increase of threat level for nuclear facilities and materials. The currently regulation in force is CNEN-NE 2.01, which provides a set of measures intended to implement Physical Protection Systems in Nuclear, Radiological Facilities as well as Transport Operations, and all documents related to security of such issues. The new regulation, named CNEN-NN 2.01, will focus only on Nuclear Material and Facilities (two other regulations specific for Security of Radioactive Sources and Transport Operations are under elaboration process). CNEN NN 2.01 is intended to provide further adherence to new international recommendations, e.g, IAEA INFCIRC 225 Rev.5 (NSS 13), which is currently regarded as the â

Grass-roots approach: developing qualified nuclear personnel

International Nuclear Information System (INIS)

Anon.

1983-01-01

Nuclear power plants experiencing personnel recruitment problems are trying a grass-roots approach to increase the manpower pool. The Philadelphia Electric Co. and the Toledo Edison Co. are working with local educational institutions to offer nuclear-technology training specific to the needs of nuclear plants. The utilities' investment covers much of the cost of instruction as well as continued training for employees

Determination of radionuclides. Fingerprint determination on protection clothing from the controlled areas in nuclear facilities

International Nuclear Information System (INIS)

Scholand, Soeren

2014-01-01

ENS (Euro Nuclear Services) in Coevorden, Netherlands, is decontaminating und providing protection clothing for the personnel in nuclear facilities. The capacity of the laundry is about 750 kg/h. The clean laundry section is cleaning non-contaminated or very low contaminated articles, i.e. socks or underwear. Fingerprint is defined as the activity of certain radionuclides that differs in the different nuclear facilities. For the reception inspection the dose rate measured with scintillation detectors is compared with the customer specific fingerprint. The total activity is usually 2000 Bq/g. The dose rate limit is 0.3 mSv/h.

Emergency planning and response: An independent safety assessment of Department of Energy nuclear reactor facilities

International Nuclear Information System (INIS)

Knuth, D.; Boyd, R.

1981-02-01

The Department of Energy (DOE) has formed a Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee to assess the implications of the recommendations contained in the President's Commission Report on the Three Mile Island (TMI) Accident (the Kemeny Commission report) that are applicable to DOE's nuclear reactor operations. Thirteen DOE nuclear reactors have been reviewed. The assessments of the 13 facilities are based on information provided by the individual operator organizations and/or cognizant DOE Field Offices. Additional clarifying information was supplied in some, but not all, instances. This report indicates how these 13 reactor facilities measure up in light of the Kemeny and other TMI-related studies and recommendations, particularly those that have resulted in upgraded Nuclear Regulatory Commission (NRC) requirements in the area of emergency planning and response

PROJECTIZING AN OPERATING NUCLEAR FACILITY

International Nuclear Information System (INIS)

Adams, N

2007-01-01

This paper will discuss the evolution of an operations-based organization to a project-based organization to facilitate successful deactivation of a major nuclear facility. It will describe the plan used for scope definition, staff reorganization, method estimation, baseline schedule development, project management training, and results of this transformation. It is a story of leadership and teamwork, pride and success. Workers at the Savannah River Site's (SRS) F Canyon Complex (FCC) started with a challenge--take all the hazardous byproducts from nearly 50 years of operations in a major, first-of-its-kind nuclear complex and safely get rid of them, leaving the facility cold, dark, dry and ready for whatever end state is ultimately determined by the United States Department of Energy (DOE). And do it in four years, with a constantly changing workforce and steadily declining funding. The goal was to reduce the overall operating staff by 93% and budget by 94%. The facilities, F Canyon and its adjoined sister, FB Line, are located at SRS, a 310-square-mile nuclear reservation near Aiken, S.C., owned by DOE and managed by Washington Group International subsidiary Washington Savannah River Company (WSRC). These facilities were supported by more than 50 surrounding buildings, whose purpose was to provide support services during operations. The radiological, chemical and industrial hazards inventory in the old buildings was significant. The historical mission at F Canyon was to extract plutonium-239 and uranium-238 from irradiated spent nuclear fuel through chemical processing. FB Line's mission included conversion of plutonium solutions into metal, characterization, stabilization and packaging, and storage of both metal and oxide forms. The plutonium metal was sent to another DOE site for use in weapons. Deactivation in F Canyon began when chemical separations activities were completed in 2002, and a cross-functional project team concept was implemented to successfully

X-ray and nuclear radiation facilities: personnel safety features

International Nuclear Information System (INIS)

Mason, W.J.; Pipes, E.W.; Rucker, T.R.; Smith, D.N.; West, C.M.

1976-10-01

The Oak Ridge Y-12 Plant is a research and production installation. The nature and versatility of this work require the use of a large number and variety of x-ray and radiographic sources for nondestructive testing and material analyses. Presently, there are over 80 x-ray generators in the plant, which range in size from small, portable units which operate at a less than 50 kilovolts potential and 0.1 milliampere current to an electron linear accelerator which operates at 12-million electron volts and produces a radiation beam of such intensity that it could deliver a lethal dose to man in a fraction of a minute. There are also almost 50 gamma and neutron sources in use in the plant. These units range in size from a few millicuries to several hundred curies. Although the radiation safety at each of these facilities was considered adequate, the administrative and maintenance procedures became unduly complicated. Accordingly, engineering standards and uniform operating procedures were considered necessary to alleviate these complications and, in so doing, provide an improved measure of radiation safety. Development and implementation of these standards are described and the general philosophy and approach to these standards are outlined. Use of a matrix (type of installation versus radiation safety feature) to facilitate equipment classification and personnel safety feature requirements is presented. Included is a set of the standards showing formats, matrices, etc., and the detailed standards for each safety feature

Internal dosimetry for occupationally exposed personnel in nuclear medicine

International Nuclear Information System (INIS)

Garcia, M.T.; Alfaro, L.M.M.; Angeles, C.A.

2013-01-01

Internal dosimetry plays an important role in nuclear medicine dosimetry control of personnel occupationally exposed, and that in recent years there has been a large increase in the use of radionuclides both in medical diagnosis as radiotherapy. But currently, in Mexico and in many parts of the world, this internal dosimetry control is not performed. The Instituto Nacional de lnvestigaciones Nucleares de Mexico (ININ) together with the Centro Oncologico de Toluca (ISEMMYM) have developed a simple and feasible methodology for monitoring of personnel working in these facilities. It was aimed to carry out the dosimetry of the personnel, due to the incorporation of I-131, using the spectrometric devices that the hospital has, a gamma camera. The first step in this methodology was to make a thyroid phantom to meet the specifications of the ninth ANSI. This phantom is compared under controlled conditions with RMC- II phantom used for system calibration of the ININ internal dosimetry (ACCUSCAN - Ll), and with another phantom developed in Brazil with ANSI specifications, in order to determine the variations in measurements due to the density of the material of each of the phantoms and adjust to the system ACCUSCAN, already certificate. Furthermore, necessary counts were performed with the gamma camera of the phantom developed at ININ, with a standard source of 133 Ba which simulates the energy of 131 I. With these data, were determined the counting efficiencies for a distance of 15 to 20 cm between the surface of the phantom and the the plate of the detectors. Another important aspect was to determine the lower limit of detection (LLD). In this paper we present the results obtained from the detectors calibration of the gamma camera of the hospital.

A study on surveillance equipment at the exit/entry control point of nuclear facility

International Nuclear Information System (INIS)

Park, C. S.; Kim, D. Y.; Cha, H. L.; Kim, H. D.; Hong, J. S.

1999-01-01

Exit/Entry control is an essential measure at both entrances of the protected area and vital area of nuclear facility at which physical protection is required under the relevant laws and regulations. Especially, when there are heavy traffics of personnel and process equipment in those areas, automated surveillance devices have to be introduced to timely and efficiently screen out internal and external adversaries from achieving their goals of stealing of nuclear material and/or sabotage of the facility. The major portion of this study involves with integration and processing of signals from radiation detector, metal detector, and image monitor. This integrated device together with positive personal identification device which will be reinforced in near future would contribute to the establishment of total exit/entry control point of nuclear facility

Personnel Radiation Protection at the ITER Nuclear Fusion Facility

International Nuclear Information System (INIS)

Coniglio, A.; Sandri, S.; D'Arienzo, M.

2006-01-01

The hosting site for the ITER nuclear fusion experiment was finally chosen in France (Cadarache). The radiation protection program for the ITER personnel involved into operation and maintenance activities will be then tested in the near future. Related studies were mainly carried out during the last ten years and important assessments were performed at the Frascati ENEA Research Center in Italy. In this ambit individual and collective doses to the operators were calculated for different categories of working activities involving more and less critical systems. The radiation protection organization was outlined and the related program was proposed. A short review of the analyses performed in this field by the Italian investigators of the ENEA Radiation Protection Institute is shown here. The principal parameter taken into account in these evaluations was the collective dose due to the different working activities. This quantity has been assessed considering the following radiological source terms: a) the prompt radiation during the plasma burning phase, b) the gamma radiation due to the neutron activation of the solid structures, c) the activated corrosion products (ACPs) generated in the water cooling system (WCS) by corrosion of the inner wall of the piping under the neutron flux, d) tritium concentration in the atmosphere of the working premises. Individual doses have been integrated over the different worker typology, considering the design evolution for the different systems and the required person power. Ordinary, inspection and maintenance activities were taken into account to assess the person power, sometime also construction, plant modifications and unscheduled maintenance were included in the working activities list. The collective dose assessed for ITER fusion projects has been compared with that of the fission power stations and analogies and differences have been pointed out. In this review the dose assessment process is recalled starting from the

Personnel Radiation Protection at the ITER Nuclear Fusion Facility

Energy Technology Data Exchange (ETDEWEB)

Coniglio, A.; Sandri, S. [ENEA, Radiation Protection Institute, Frascati (Italy); D' Arienzo, M. [RFX, Padova (Italy)

2006-07-01

The hosting site for the ITER nuclear fusion experiment was finally chosen in France (Cadarache). The radiation protection program for the ITER personnel involved into operation and maintenance activities will be then tested in the near future. Related studies were mainly carried out during the last ten years and important assessments were performed at the Frascati ENEA Research Center in Italy. In this ambit individual and collective doses to the operators were calculated for different categories of working activities involving more and less critical systems. The radiation protection organization was outlined and the related program was proposed. A short review of the analyses performed in this field by the Italian investigators of the ENEA Radiation Protection Institute is shown here. The principal parameter taken into account in these evaluations was the collective dose due to the different working activities. This quantity has been assessed considering the following radiological source terms: a) the prompt radiation during the plasma burning phase, b) the gamma radiation due to the neutron activation of the solid structures, c) the activated corrosion products (ACPs) generated in the water cooling system (WCS) by corrosion of the inner wall of the piping under the neutron flux, d) tritium concentration in the atmosphere of the working premises. Individual doses have been integrated over the different worker typology, considering the design evolution for the different systems and the required person power. Ordinary, inspection and maintenance activities were taken into account to assess the person power, sometime also construction, plant modifications and unscheduled maintenance were included in the working activities list. The collective dose assessed for ITER fusion projects has been compared with that of the fission power stations and analogies and differences have been pointed out. In this review the dose assessment process is recalled starting from the

Quality assurance for external personnel monitoring in nuclear industrial facilities, CNNC

International Nuclear Information System (INIS)

Zhang Yansheng; Dai Jun; Li Taosheng

1993-01-01

More than 6000 personnel are currently being monitored for occupational exposure in CNNC, China. Personnel monitoring is one of the important items of radiation protection. The data of individual dose are not only indispensable for radiation safety assessment but also the basis for radiation protection measures to be taken. Possibly, it could provide basic information for epidemiological studies, optimization procedure of radiation protection (risk/benefit analyses) and medical or legal purposes. Obviously, personnel monitoring and its quality assurance are very significant

Nuclear power plant personnel training and its evaluation. A guidebook

International Nuclear Information System (INIS)

1996-01-01

The Guidebook will prove especially useful for, and is addressed primarily to: nuclear power operating organizations establishing or upgrading their NPP personnel training systems; regulatory personnel responsible for setting requirements and/or evaluating NPP personnel training; and organizations (within or outside the operating organization) responsible for the development, implementation and evaluation of training programmes for NPP personnel. Figs, tabs

Proceedings of the ninth symposium on the training of nuclear facility personel

International Nuclear Information System (INIS)

1991-04-01

This document provides reports presented on training of nuclear facility personnel. The papers were presented in the following categories: engineering technical staff; specialty training; customer perspective/plant side; human factors/soft science; maintenance; simulator centered training; hands-on training devices; management training; and reduced O ampersand M costs through training. Individual papers have been cataloged separately. (FI)

System of radiation monitoring of nuclear hazardous facilities in Institute of Atomic Energy of National Nuclear Centre

International Nuclear Information System (INIS)

Azarov, V.A.; Meshin, M.M.; Shuklin, G.S.

1996-01-01

Issues of radiation monitoring (RM) at reactor complex of Inst. of Atomic Energy (IAE) are discussed in report. The National Nuclear Centre's reactor base consists of 2 complexes situated in 2 different locations: Bajkal-1 and IGR. So far as IAE has common mythology for RM at all hazardous nuclear facilities the issues of RM for Baikal-1 and IGR Radiation monitoring system includes: - personal dosimetric control of personnel, maintaining the reactor systems and research laboratories; RM of industrial buildings; - RM of technical areas of technical area of the facility; sanitary system of dosimetry control (DC); etc. The description of stationary DC system of the complex based on 'System' facility are given. Baikal is surround by sanitary area with radius of 5 km and with its centre in the reactor location. Complexity of studying the radiation status on the territory of Baikal-1 and its surroundings is the result of nuclear testing conducted at the test site in the past, reactor operation with open exhaust of coolant into atmosphere while testing on Nuclear Rocket Engines program as well as global fall out of radionuclides

Asymmetrical sabotage tactics, nuclear facilities/materials, and vulnerability analysis

International Nuclear Information System (INIS)

Ballard, J.D.

2002-01-01

Full text: The emerging paradigm of a global community wherein post-modern political violence is a fact of life that must be dealt with by safety and security planners is discussed. This paradigm shift in the philosophy of terrorism is documented by analysis of the emerging pattern of asymmetrical tactics being employed by terrorists. Such philosophical developments in violent political movements suggest a shift in the risks that security and safety personnel must account for in their planning for physical protection of fixed site nuclear source facilities like power generation stations and the eventual storage and transportation of the by-products of these facilities like spent nuclear fuel and other high level wastes. This paper presents a framework for identifying these new political realities and related threat profiles, suggests ways in which security planners and administrators can design physical protection practices to meet these emerging threats, and argues for global adoption of standards for the protection of nuclear facilities that could be used as a source site from which terrorists could inflict a mass contamination event and for standards related to the protection of the waste materials that can be used in the production of radiological weapons of mass victimization. (author)

Nuclear manpower planning and personnel training

International Nuclear Information System (INIS)

Chen, J.H.

1984-01-01

Taiwan Power Company has established a nuclear manpower program to identify human resources, selection and recruitment of entry level engineers and technicians of Nuclear Energy Group. The methodology to estimate the future nuclear manpower demand of Taipower has been clearly described in this article. Also, the manpower program is being used as the bases for nuclear training program development. For safe, reliable and efficient operation of nuclear power plants, Taipower has established a systematic training program for nuclear power stations and headquarter personnel. The training program has been implemented in three stages with different patterns of training program. The first stage of nuclear training before 1975 was completed successfully. The second stage of nuclear training currently conducted since 1975 enlarges domestic training capability. The third stage of nuclear training with a long term training program is now under a systematic and compositive development effort

Study of the adequacy of personnel for the US nuclear program

International Nuclear Information System (INIS)

1981-11-01

The report will emphasize fission topics relative to fusion because of the relative number of personnel involved. However, the commonality of types of personnel and their required educational background are such that the health of the fission educational infrastructure will affect the future supply of fusion technologists. Alternatively, the attractive aspects of some closely related fusion research in universities can help attract the high quality personnel needed in the fission field. The report's recommendations are therefore based on the needs of both programs. A separate study of the detailed requirements for fusion scientific and engineering personnel has been prepared by the Office of Fusion Energy. In this report, the present status of nuclear power, historic personnel requirements, future requirements, and constraints on future supply are analyzed. The intent of this report is to provide a context for conclusions and recommendation of Government actions leading to an adequate supply of nuclear manpower both for the industrial and Government components of the nuclear enterprise

Hypothetical requirements on number of personnel in Czechoslovak nuclear power plants

International Nuclear Information System (INIS)

Halik, J.

1990-01-01

The structural changes of Czechoslovak power prevent prediction of labor force development by extrapolating the existing development trends. Nuclear power demands a different qualification and occupation structure of the labor force than conventional power generation. The prediction of the number of personnel is based on data on the expected installed capacity and on its commissioning. The following organizational structures are envisaged for a nuclear power plant: the divisions of the Director, of production, maintenance, radiation safety and quality control, technology and investment, economics and personnel. A total of 15,654 personnel are envisaged for nuclear power plants in 2005. A brief comparison is submitted of labor demands in nuclear power plants in Czechoslovakia and in the world. (M.D.). 1 fig., 4 tabs., 3 refs

Global nuclear material monitoring with NDA and C/S data through integrated facility monitoring

International Nuclear Information System (INIS)

Howell, J.A.; Menlove, H.O.; Argo, P.; Goulding, C.; Klosterbuer, S.; Halbig, J.

1996-01-01

This paper focuses on a flexible, integrated demonstration of a monitoring approach for nuclear material monitoring. This includes aspects of item signature identification, perimeter portal monitoring, advanced data analysis, and communication as a part of an unattended continuous monitoring system in an operating nuclear facility. Advanced analysis is applied to the integrated nondestructive assay and containment and surveillance data that are synchronized in time. End result will be the foundation for a cost-effective monitoring system that could provide the necessary transparency even in areas that are denied to foreign nationals of both US and Russia should these processes and materials come under full-scope safeguards or bilateral agreements. Monitoring systems of this kind have the potential to provide additional benefits including improved nuclear facility security and safeguards and lower personnel radiation exposures. Demonstration facilities in this paper include VTRAP-prototype, Los Alamos Critical Assemblies Facility, Kazakhstan BM-350 Reactor monitor, DUPIC radiation monitoring, and JOYO and MONJU radiation monitoring

Checking the special professional qualification of selected personnel of Czechoslovak nuclear power facilities

International Nuclear Information System (INIS)

Kovar, P.; Bahnova, V.

1990-01-01

The system of examinations of selected staff members of Czechoslovak nuclear power plants for their special professional quanlification is described in detail. This selected personnel includes secondary circuit operators, primary circuit operators, graduate shift leaders as well as reactor unit managers. Attention is paid to the structure, methodology, contents and criteria of evaluation of the written, oral and practical parts of the examination, which is sat for before the State Examination Commission. Based on the results of the examinations, the Czechoslovak Atomic Energy Commission grants, prolongs or cancels licenses for the particular functions. Over the period from 1985 to March 1989, 394 new licenses were issued, 93 licenses were prolonged and 4 were withdrawn. (Z.M.). 7 figs., 3 tabs., 3 refs

Containers for short-term storage of nuclear materials at the Los Alamos plutonium facility

International Nuclear Information System (INIS)

Hagan, R.; Gladson, J.

1997-01-01

The Los Alamos Plutonium Facility for the past 18 yr has stored nuclear samples for archiving and in support of nuclear materials research and processing programs. In the past several years, a small number of storage containers have been found in a deteriorated condition. A failed plutonium container can cause personnel contamination exposure and expensive physical area decontamination. Containers are stored in a physically secure radiation area vault, making close inspection costly in the form of personnel radiation exposure and work time. A moderate number of these containers are used in support of plutonium processing and must withstand daily handling abuse. A 2-yr evaluation of failed containers and those that have shown no deterioration has been conducted. Based on that study, a program was established to formalize our packing methods and materials and standardize the size and shape of containers that are used for short-term use. A standardized set of containers was designed, evaluated, tested, and procured for use in the facility. This paper reviews our vault storage problems, shows some failed containers, and presents our planned solutions to provide safe and secure containment of nuclear materials

Report of the State Office for Nuclear Safety on state supervision of nuclear safety of nuclear facilities and radiation protection in 1998

International Nuclear Information System (INIS)

1999-05-01

The legislative basis of the authority of the State Office for Nuclear Safety as the Czech national regulatory body is outlined, its organizational scheme is presented, and the responsibilities of the various departments are highlighted. The operation of major Czech nuclear facilities, including the Dukovany NPP which is in operation and the Temelin NPP which is under construction, is described with respect to nuclear safety. Since the Office's responsibilities also cover radiation protection in the Czech Republic, a survey of ionizing radiation sources and their supervision is given. Other topics include, among other things, nuclear material transport, the state system for nuclear materials accountancy and control, central registries for radiation protection, nuclear waste management, the National Radiation Monitoring Network, personnel qualification and training, emergency planning, legislative activities, international cooperation, and public information. (P.A.)

Current status of personnel exposure at nuclear power plants and other medical, industrial and educational facilities in JAPAN

International Nuclear Information System (INIS)

Sasaki, Fumiaki

1991-01-01

The state of radiation exposure of the workers engaging in radiation works in Japanese nuclear power stations, the factors of the radiation exposure of the workers engaging in radiation works, the countermeasures for reducing exposure in nuclear power stations, the state of radiation exposure of doctors, the workers engaging in radiation works, researchers and others in medical, industrial, research and educational and other facilities in Japan, the factors of their radiation exposure and the countermeasures for reducing the exposure, and the comparison of the exposure in nuclear power stations with that in medical, industrial, research and educational facilities are reported. (K.I.)

Nuclear Security in Action at Facilities in Ghana

International Nuclear Information System (INIS)

Dahlstrom, Danielle

2013-01-01

Nuclear security is a national responsibility. An Integrated Nuclear Security Support Plan (INSSP) is a tool that enables States to address nuclear security in a comprehensive way and to strengthen its national nuclear security regime, beginning with the legislative and regulatory framework within a State. Operating areas in nuclear facilities like research reactors which use highly enriched uranium, require additional physical protection measures to ensure the security of the nuclear material and prevent acts of sabotage. Other radioactive materials, like sealed radioactive sources used in radiotherapy machines in hospitals for cancer treatment, need to be protected so that they are not stolen and used with malicious intent. Nuclear and other radioactive material needs to be kept in safe and secure storage, which incorporates various types of physical barriers to prevent theft and unauthorized access. Intrusion detection and assessment systems, like cameras and sensors, help to ensure timely and adequate responses to any security incident. Responding to a nuclear security incident, and mitigating its consequences, requires specialized equipment like isotope identifiers, and competent and well trained personnel. Nuclear Security Support Centres (NSSCs) focus on human resource development as well as technical and scientific support which contribute to the sustainability of nuclear security in a State

Recruitment training and licensing of operating personnel for nuclear power plants

International Nuclear Information System (INIS)

Palabrica, R.J.

1979-01-01

This article covers the step-by-step and most rigid recruitment, training, and licensing procedures undertaken in the selection for personnel involved in nuclear power plant operations. These procedures are true to all countries. However, for developing countries such as the Philippines, a bachelor's degree may be required as compared with the U.S. wherein a high school diploma is the minimum requirement. Because of the complexity of a nuclear facility, the work will require highly capable individuals with mature judgement who can render correct decisions even under highly stressed conditions. Thus during the selection and recruitment of applicants for the operator position, they are not only given aptitude tests but are also subjected to a series of psychological examintions. Once they are accepted, they are made to undergo a comprehensive and in-depth training to ensure that they will be capable of operating the nuclear power plant safely and effectively. Finally, those prospective operators have to pass licensing examinations in order to prove their competence and skills. Retraining programs follow after their training to maintain their skills. (RTD)

Training of nuclear power plant personnel in Canada

International Nuclear Information System (INIS)

Tennant, D.

1993-01-01

All of the utilities, Ontario Hydro, Hydro Quebec and New Brunswick Power, operating Nuclear Power Plants in Canada have Training Centres which provide training for all of their plant personnel whose job activities could affect plant and personnel safety. This report points out the methods used for training, which generally conform to that described by the IAEA as a Systematic Approach to Training (SAT)

Analysis of the formation, expression, and economic impacts of risk perceptions associated with nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Allison, T.; Hunter, S.; Calzonetti, F.J.

1992-10-01

This report investigates how communities hosting nuclear facilities form and express perceptions of risk and how these risk perceptions affect local economic development. Information was collected from site visits and interviews with plant personnel, officials of local and state agencies, and community activists in the hosting communities. Six commercial nuclear fuel production facilities and five nuclear facilities operated for the US Department of Energy by private contractors were chosen for analysis. The results presented in the report indicate that the nature of risk perceptions depends on a number of factors. These factors are (1) level of communication by plant officials within the local community, (2) track record of the facility. operator, (3) process through which community and state officials receive information and form opinions, (4) level of economic links each plant has with the local community, and (15) physical characteristics of the facility itself. This report finds that in the communities studied, adverse ask perceptions have not affected business location decisions, employment levels in the local community, tourism, or agricultural development. On the basis of case-study findings, this report recommends that nuclear facility siting programs take the following observations into account when addressing perceptions of risk. First, the quality of a facility`s participation with community activists, interest groups, and state agencies helps to determine the level of perceived risk within a community. Second, the development of strong economic links between nuclear facilities and their host communities will produce a higher level of acceptance of the nuclear facilities.

Considerations in the safety assessment of sealed nuclear facilities

International Nuclear Information System (INIS)

1991-06-01

This report is a part of the International Atomic Energy Agency's radioactive waste management programme, whose objective is to provide assistance to Member States in developing guidance for identifying safe alternatives for isolating radioactive waste from man and his environment. This report attempts to integrate information from the previous reports on decommissioning of nuclear facilities, mitigation of accidents at such facilities, and performance assessment of disposal systems to provide useful advice and qualitative guidance to those responsible for performance and safety assessments of sealed nuclear facilities by giving an overview of possible approaches and techniques for such assessments. In this context, the establishment of requirements and rules governing the radiological safety of personnel, the general public, and the environment for sealing and post-sealing activities will enable the choice of the most appropriated approach and help to promote consistency in both decommissioning and waste management standards. The near-field effects discussed in this document include gas generation, interactions of the groundwater and the residual water with other components of the system, thermal, thermo-mechanical, radiation effects and chemical and geochemical reactions. 59 refs, figs and tabs

Development of instructors for nuclear power plant personnel training

International Nuclear Information System (INIS)

2004-06-01

In 1996 the IAEA published Technical Reports Series No. 380, Nuclear Power Plant Personnel Training and its Evaluation, A Guidebook, which provides guidance with respect to development, implementation and evaluation of training programmes. The IAEA Technical Working Group on Training and Qualification of Nuclear Power Plant Personnel recommended that an additional publication be prepared to provide further details concerning the development of instructors for NPP personnel training. The quality of nuclear power plant personnel training is strongly dependent on the availability of competent instructors. Instructors must have a comprehensive practical as well as theoretical understanding of all aspects of the subjects being taught and the relationship of the subject to nuclear plant operation. Instructors should have the appropriate knowledge, skills and attitudes (KSAs) in their assigned areas of responsibility. They should thoroughly understand all aspects of the contents of the training programmes and the relationship between these contents and overall plant operation. This means that they should be technically competent and show credibility with the trainees and other plant personnel. In addition, the instructors should be familiar with the basics of adult learning and a systematic approach to training, and should have adequate instructional and assessment skills. This TECDOC provides practical guidance on various aspects of instructor selection, development and deployment, by quoting actual examples from different countries. It highlights the importance of having an appropriate training policy, especially considering the various organisational arrangements that exist in different utilities/countries. This should result in: plant performance improvement, improved human performance, meeting goals and objectives of the business (quality, safety, productivity), and improving training programs. This publication is available in two formats - as a conventional printed

Education and training for security personnel

International Nuclear Information System (INIS)

Chida, Toshiya

2015-01-01

It is said that Physical Protection (PP) has two purposes. One is to prevent from occurring risks of threat and terrorism and the other is to minimize damages which will be happened in case of unusual conditions or emergency situation. To achieve this goal, personnel who perform their duties should have professional knowledge and skills concerning security. However, since newcomers rarely satisfy their knowledge and skill for nuclear security in most cases. Therefore, we have to provide adequate education and training after they joined to our company. To this end, our company, located in Aomori Prefecture focused on security and physical protection for nuclear related facilities. In this paper, personnel training and challenges in order to bring up security personnel at our company will be introduced. (author)

Analysis of the formation, expression, and economic impacts of risk perceptions associated with nuclear facilities

International Nuclear Information System (INIS)

Allison, T.; Hunter, S.; Calzonetti, F.J.

1992-10-01

This report investigates how communities hosting nuclear facilities form and express perceptions of risk and how these risk perceptions affect local economic development. Information was collected from site visits and interviews with plant personnel, officials of local and state agencies, and community activists in the hosting communities. Six commercial nuclear fuel production facilities and five nuclear facilities operated for the US Department of Energy by private contractors were chosen for analysis. The results presented in the report indicate that the nature of risk perceptions depends on a number of factors. These factors are (1) level of communication by plant officials within the local community, (2) track record of the facility. operator, (3) process through which community and state officials receive information and form opinions, (4) level of economic links each plant has with the local community, and (15) physical characteristics of the facility itself. This report finds that in the communities studied, adverse ask perceptions have not affected business location decisions, employment levels in the local community, tourism, or agricultural development. On the basis of case-study findings, this report recommends that nuclear facility siting programs take the following observations into account when addressing perceptions of risk. First, the quality of a facility's participation with community activists, interest groups, and state agencies helps to determine the level of perceived risk within a community. Second, the development of strong economic links between nuclear facilities and their host communities will produce a higher level of acceptance of the nuclear facilities

Summary of NPP personnel training in Czech Republic

International Nuclear Information System (INIS)

1996-01-01

The preparation of NPP personnel is one of the most important phases of the process of construction, commissioning, operation and maintenance of nuclear power facilities. The objective is to improve personnel abilities so that they would be able to assure reliable, safe and economic operation of these facilities with high investment costs. It is the purpose of Nuclear Training Centre Brno (NTC Brno) to provide training and services which are responsive to the technological demands and emerging educational standards and criteria of the NPP and the nuclear industry. Fulfilling this purpose is a challenging task. The staff of NTC Brno, in a joint effort with NPP Dukovany and NPP Temelin, has responded to the challenge with comprehensive programs aimed at meeting customers needs. The programs are broadly based, yet flexible so that they can incorporate specific customer requirements

Presentation of the process External communications on the nuclear facilities operation of the Adjunct Head Office of Nuclear Safety of Comision Nacional de Seguridad Nuclear y Salvaguardias

International Nuclear Information System (INIS)

Espinosa V, J. M.

2012-10-01

The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in use of their attributions granted by the Regulation Law of the constitutional Art. 27 in nuclear matter began the development of the called process External communications on the nuclear facilities operation, with the purpose of negotiating the evaluation of the concerns related with the safety of the nuclear facilities received these of external people to the CNSNS. The process External communications on the nuclear facilities operation will allow to the public's members and the workers that carry out activities inside the mark regulator imposed by the CNSNS that report to this Commission their concerns related with safety for several means (for example, directly to the personnel of the assigned Office, official and public statements, phone communication, electronic mail, etc.) The present article presents the legal mark confers the CNSNS the attributions to develop the mentioned process and exposes the most important elements that compose it. The term External communication on the nuclear facilities operation is defined and also is described how these communications are received, evaluated and closed by the assigned Office. Of equal way the objectives that intents to reach this process are indicated. The intention of the mentioned process is to strengthen the actions that the CNSNS carries out in the execution of its functions to maintain the safety standards in the operation of the nuclear facilities in Mexico. (Author)

Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Culbert, W.H.

1985-10-01

This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit

Concrete structures for nuclear facilities

International Nuclear Information System (INIS)

1996-01-01

The detailed requirements for the design and fabrication of the concrete structures for nuclear facilities and for the documents to be submitted to the Finnish Centre for Radiation and Nuclear Safety (STUK) are given in the guide. It also sets the requirements for the inspection of concrete structures during the construction and operation of facilities. The requirements of the guide primarily apply to new construction. As regards the repair and modification of nuclear facilities built before its publication, the guide is followed to the extent appropriate. The regulatory activities of the Finnish Centre for Radiation and Nuclear Safety during a nuclear facility's licence application review and during the construction and operation of the facility are summarised in the guide YVL 1.1

Simulators for training nuclear power plant personnel

International Nuclear Information System (INIS)

1993-01-01

Simulator training and retraining of operations personnel is essential for their acquiring the necessary knowledge, skills and qualification for operating a nuclear power plant, and for effective feedback of experience including human based operating errors. Simulator training is the most effective way by far of training operations personnel in co-operation and communication in a team, which also involves instilling attitudes and approaches for achieving excellence and individual responsibility and alertness. This technical document provides guidance to Member States on the procurement, setting up and utilization of a simulator training centre; it will also be useful for organizations with previous experience in the use of simulators for training. The document is the result of a series of advisory and consultants meetings held in the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation in 1989-1992. 17 refs, 2 tabs

Training of nuclear power plant operating personnel

International Nuclear Information System (INIS)

Anon.

1980-04-01

A collection is presented containing 11 papers submitted at a conference on the selection and education of specialists for operation and maintenance of nuclear power plants. The conference was attended by specialists from universities and colleges, research institutes and production plants. It debated the methods and aims of both general and specialized theoretical and practical personnel education, the proposals for teaching centre equipment, the use of simulators, computers and other aids in the teaching process; training on school reactors was included. A proposal was put forward of the system of education, the teaching process itself, the content of the basic theoretical subjects, and the method of testing pupils' knowledge. The importance was stressed of establishing a national coordination centre to safeguard the syllabus, methodology, teaching aids, and also the training proper. The system of personnel education in the Paks nuclear power plant, Hungary, is presented as an example. (M.S.)

Monitoring around the secret nuclear facilities of naval ports

International Nuclear Information System (INIS)

Jaskierowicz, D.; Quere, St.

2010-01-01

Based within large industrial cities (Brest, Toulon, Cherbourg) or more rural areas like Crozon (Ile Longue), French navy exploits nuclear facilities where are built, maintained and decommissioned nuclear power submarines and aircraft-carrier. The safety and the security of these installations as well as the non-impact on people and environment are continuously monitored. The DSND, a governmental regulatory body dedicated to the Defense, applies the same regulations enforced by the ASN for civilian nuclear activities. Concerning environmental monitoring, the navy answers to the DSND or the ASN, depending on the type of survey. In every nuclear site, an automatic nuclear monitoring sensor system (2SNM) runs 24/7, with the supervision of specialized personnel in radioprotection. Each year, more than 7000 samples are collected in the ecosystem and thousands of measurements are carried out in four laboratories (LASEM in Cherbourg, Brest and Toulon) - SPRS ILO) of the navy. These results are sent to the DSND and have been integrated since February 2010 to the brand-new public web site of the national monitoring network of radioactivity in the environment (RMN). (author)

Security culture for nuclear facilities

Science.gov (United States)

Gupta, Deeksha; Bajramovic, Edita

2017-01-01

Natural radioactive elements are part of our environment and radioactivity is a natural phenomenon. There are numerous beneficial applications of radioactive elements (radioisotopes) and radiation, starting from power generation to usages in medical, industrial and agriculture applications. But the risk of radiation exposure is always attached to operational workers, the public and the environment. Hence, this risk has to be assessed and controlled. The main goal of safety and security measures is to protect human life, health, and the environment. Currently, nuclear security considerations became essential along with nuclear safety as nuclear facilities are facing rapidly increase in cybersecurity risks. Therefore, prevention and adequate protection of nuclear facilities from cyberattacks is the major task. Historically, nuclear safety is well defined by IAEA guidelines while nuclear security is just gradually being addressed by some new guidance, especially the IAEA Nuclear Security Series (NSS), IEC 62645 and some national regulations. At the overall level, IAEA NSS 7 describes nuclear security as deterrence and detection of, and response to, theft, sabotage, unauthorized access, illegal transfer or other malicious acts involving nuclear, other radioactive substances and their associated facilities. Nuclear security should be included throughout nuclear facilities. Proper implementation of a nuclear security culture leads to staff vigilance and a high level of security posture. Nuclear security also depends on policy makers, regulators, managers, individual employees and members of public. Therefore, proper education and security awareness are essential in keeping nuclear facilities safe and secure.

Nuclear physics accelerator facilities

International Nuclear Information System (INIS)

1988-12-01

This paper describes many of the nuclear physics heavy-ion accelerator facilities in the US and the research programs being conducted. The accelerators described are: Argonne National Laboratory--ATLAS; Brookhaven National Laboratory--Tandem/AGS Heavy Ion Facility; Brookhaven National Laboratory--Relativistic Heavy Ion Collider (RHIC) (Proposed); Continuous Electron Beam Accelerator Facility; Lawrence Berkeley Laboratory--Bevalac; Lawrence Berkeley Laboratory--88-Inch Cyclotron; Los Alamos National Laboratory--Clinton P. Anderson Meson Physics Facility (LAMPF); Massachusetts Institute of Technology--Bates Linear Accelerator Center; Oak Ridge National Laboratory--Holifield Heavy Ion Research Facility; Oak Ridge National Laboratory--Oak Ridge Electron Linear Accelerator; Stanford Linear Accelerator Center--Nuclear Physics Injector; Texas AandM University--Texas AandM Cyclotron; Triangle Universities Nuclear Laboratory (TUNL); University of Washington--Tandem/Superconducting Booster; and Yale University--Tandem Van de Graaff

Nuclear power plant personnel training and its evaluation. A guidebook. Executive summary

International Nuclear Information System (INIS)

1997-05-01

The Guidebook will prove especially useful for, and is addressed primarily to: nuclear power operating organizations establishing or upgrading their NPP personnel training systems; regulatory personnel responsible for setting requirements and/or evaluating NPP personnel training; and organizations (within or outside the operating organization) responsible for the development, implementation and evaluation of training programmes for NPP personnel. Figs

Policies and practices pertaining to the selection, qualification requirements, and training programs for nuclear-reactor operating personnel at the Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Culbert, W.H.

1985-10-01

This document describes the policies and practices of the Oak Ridge National Laboratory (ORNL) regarding the selection of and training requirements for reactor operating personnel at the Laboratory's nuclear-reactor facilities. The training programs, both for initial certification and for requalification, are described and provide the guidelines for ensuring that ORNL's research reactors are operated in a safe and reliable manner by qualified personnel. This document gives an overview of the reactor facilities and addresses the various qualifications, training, testing, and requalification requirements stipulated in DOE Order 5480.1A, Chapter VI (Safety of DOE-Owned Reactors); it is intended to be in compliance with this DOE Order, as applicable to ORNL facilities. Included also are examples of the documentation maintained amenable for audit.

Education and training requirements of nuclear power plant personnel

International Nuclear Information System (INIS)

Donato, R.; Perlas, C.A.; Conti, E.

1978-01-01

This bibliography was compiled by the Scientific Library staff to help in the intensified training program being undertaken by the Philippine Atomic Energy Commission (PAEC) for the nuclear power plant personnel of the Philippines' first nuclear power reactor. This bibliography covers the period 1955 - 1976 of the Nuclear Science Abstracts and is composed of 281 entries. Arrangement of these entries is by broad subject category

Medical screening reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

International Nuclear Information System (INIS)

Arzino, P.A.; Brown, C.H.

1991-09-01

The recommendations contained throughout this NUREG were provided to the Nuclear Regulatory Commission (NRC) as medical screening information that could be used by physicians who are evaluating the parameters of the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The medical recommendations in this NUREG are similar in content to the medical standards contained in 10 CFR Part 1046 which, in part, specifies medical standards for the protective force personnel regulated by the Department of Energy. The guidelines contained in this NUREG are not requirements, and compliance is not required. 3 refs

Medical screening reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

Energy Technology Data Exchange (ETDEWEB)

Arzino, P.A.; Brown, C.H. (California State Univ., Hayward, CA (United States). Foundation)

1991-09-01

The recommendations contained throughout this NUREG were provided to the Nuclear Regulatory Commission (NRC) as medical screening information that could be used by physicians who are evaluating the parameters of the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The medical recommendations in this NUREG are similar in content to the medical standards contained in 10 CFR Part 1046 which, in part, specifies medical standards for the protective force personnel regulated by the Department of Energy. The guidelines contained in this NUREG are not requirements, and compliance is not required. 3 refs.

Training of fire protection personnel in nuclear power plants

International Nuclear Information System (INIS)

Blaser, W.

1980-01-01

Training of fire protection personnel in nuclear power plants is divided up in three categories: training of fire protection commissioners which is mostly carried out externally; training of fire fighting personnel in the form of basic and repeated training usually by the fire protection commissioner; training of other employers with regard to behaviour in case of fire and during work involving a fire hazard. (orig.) [de

Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

Energy Technology Data Exchange (ETDEWEB)

Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

1985-11-01

This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training.

Qualification requirements and training programs for nonreactor nuclear facility personnel in the Operations Division of the Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Preston, E.L.; Culbert, W.H.; Baldwin, M.E.; McCormack, K.E.; Rivera, A.L.; Setaro, J.A.

1985-11-01

This document describes the program for training, retraining, and qualification of nonreactor nuclear operators in the Operations Division of the Oak Ridge National Laboratory. The objective of the program is to provide the Operators and Supervisors of nuclear facilities the knowledge and skills needed to perform assigned duties in a safe and efficient manner and to comply with US Department of Energy Order 5480.1A Chapter V. This order requires DOE nuclear facilities to maintain formal training programs for their operating staff and documentation of that training

The decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Niel, J.Ch.; Rieu, J.; Lareynie, O.; Delrive, L.; Vallet, J.; Girard, A.; Duthe, M.; Lecomte, C.; Rozain, J.P.; Nokhamzon, J.G.; Davoust, M.; Eyraud, J.L.; Bernet, Ph.; Velon, M.; Gay, A.; Charles, Th.; Leschaeva, M.; Dutzer, M.; Maocec, Ch.; Gillet, G.; Brut, F.; Dieulot, M.; Thuillier, D.; Tournebize, F.; Fontaine, V.; Goursaud, V.; Birot, M.; Le Bourdonnec, Th.; Batandjieva, B.; Theis, St.; Walker, St.; Rosett, M.; Cameron, C.; Boyd, A.; Aguilar, M.; Brownell, H.; Manson, P.; Walthery, R.; Wan Laer, W.; Lewandowski, P.; Dorms, B.; Reusen, N.; Bardelay, J.; Damette, G.; Francois, P.; Eimer, M.; Tadjeddine, A.; Sene, M.; Sene, R.

2008-01-01

This file includes five parts: the first part is devoted to the strategies of the different operators and includes the following files: the decommissioning of nuclear facilities Asn point of view, decommissioning of secret nuclear facilities, decommissioning at the civil Cea strategy and programs, EDF de-construction strategy, Areva strategy for decommissioning of nuclear facilities; the second one concerns the stakes of dismantling and includes the articles as follow: complete cleanup of buildings structures in nuclear facilities, decommissioning of nuclear facilities and safety assessment, decommissioning wastes management issues, securing the financing of long-term decommissioning and waste management costs, organizational and human factors in decommissioning projects, training for the decommissioning professions: the example of the Grenoble University master degree; the third part is devoted to the management of dismantling work sites and includes the different articles as follow: decommissioning progress at S.I.C.N. plant, example of decommissioning work site in Cea Grenoble: Siloette reactor decommissioning, matters related to decommissioning sites, decommissioning of french nuclear installations: the viewpoint of a specialist company, specificities of inspections during decommissioning: the Asn inspector point of view; the fourth part is in relation with the international approach and includes as follow: IAEA role in establishing a global safety regime on decommissioning, towards harmonization of nuclear safety practices in Europe: W.E.N.R.A. and the decommissioning of nuclear facilities, EPA superfund program policy for decontamination and decommissioning, progress with remediation at Sellafield, progress and experiences from the decommissioning of the Eurochemic reprocessing plant in Belgium, activities of I.R.S.N. and its daughter company Risk-audit I.r.s.n./G.r.s. international in the field of decommissioning of nuclear facilities in eastern countries

Nuclear radiation monitoring instruments for personnel in nuclear disaster for defence needs

International Nuclear Information System (INIS)

Bhatnagar, P.K.; Vaijapurkar, S.G.; Yadav, Ashok

2005-01-01

Ever since the tragedy of nuclear device exploding over Japan by USA in 1945 awareness exists amongst the armed forces personnel all over the world that a requirement of implementing radiological protection is imminent. Towards this adoption of radiological safety programme is a criterion. In a nuclear war disaster scenario, one encounters initial nuclear radiation (gamma and neutron radiations), gamma radiations from fallout, heat and blast. At certain distances Tanks/ armoured vehicles will survive and 4 R/s radiation level sensing to actuate relays for closing the ports of vehicles is essential, leading to reduction in inhalation, ingestion of fallout radioactivity and reduction in radiation dose received by occupants of the vehicle. Towards this sturdy radiation monitors to indicate gamma dose rate of the order of 1000 R/h, gamma and neutron dosimeters of the order of 1000 cGy with reading instruments are to be developed. These must work in harsh environment and sustain JSS 55555 conditions of army. Defence Laboratory, Jodhpur over past one decade has been involved in developing personnel, area and field monitoring instruments like dosimeters, survey meters, which are useful, acceptable to army personnel, armoured and personnel carrier vehicles, field structures/shelters. Technology transfer after satisfaction of armed forces, product ionisation and supply, maintenance, training has been the endeavor of the DRDO. Herein it is proposed to highlight the techno electronics nuclear radiation monitoring sensors and associated electronics systems developed first time in the country and productionised in bulk for Services for implementing personnel protection. The sensors developed and described are - Radiophotoluminescent Glass (RPLG) for gamma radiation dosimetry , neutron sensitive PIN diode for fast neutron dosimetry, gamma radiation sensitive PIN diode, superheated liquid neutron and gamma sensors. The dosimeter, dose rate meter and field/area instruments are

Studies in training nuclear plant personnel

International Nuclear Information System (INIS)

Hamlin, K.W.

1987-01-01

One of the lessons learned from the Three Mile Island (TMI) accident was that the nuclear industry was ineffective in learning from previous events at other plants. As training programs and methods have improved since TMI, the nuclear industry has searched for effective methods to teach the lessons learned from industry events. The case study method has great potential as a solution. By reviewing actual plant events in detail, trainees can be challenged with solving actual problems. When used in a seminar or discussion format, these case studies also help trainees compare their decision-making processes with other trainees, the instructor, and the personnel involved in the actual case study event

Higher operational safety of nuclear power plants by evaluating the behaviour of operating personnel

International Nuclear Information System (INIS)

Mertins, M.; Glasner, P.

1990-01-01

In the GDR power reactors have been operated since 1966. Since that time operational experiences of 73 cumulative reactor years have been collected. The behaviour of operating personnel is an essential factor to guarantee the safety of operation of the nuclear power plant. Therefore a continuous analysis of the behaviour of operating personnel has been introduced at the GDR nuclear power plants. In the paper the overall system of the selection, preparation and control of the behaviour of nuclear power plant operating personnel is presented. The methods concerned are based on recording all errors of operating personnel and on analyzing them in order to find out the reasons. The aim of the analysis of reasons is to reduce the number of errors. By a feedback of experiences the nuclear safety of the nuclear power plant can be increased. All data necessary for the evaluation of errors are recorded and evaluated by a computer program. This method is explained thoroughly in the paper. Selected results of error analysis are presented. It is explained how the activities of the personnel are made safer by means of this analysis. Comparisons with other methods are made. (author). 3 refs, 4 figs

Current personnel dosimetry practices at DOE facilities

International Nuclear Information System (INIS)

Fix, J.J.

1981-05-01

Only three parameters were included in the personnel occupational exposure records by all facilities. These are employee name, social security number, and whole body dose. Approximate percentages of some other parameters included in the record systems are sex (50%), birthdate (90%), occupation (26%), previous employer radiation exposure (74%), etc. Statistical analysis of the data for such parameters as sex versus dose distribution, age versus dose distribution, cumulative lifetime dose, etc. was apparently seldom done. Less than 50% of the facilities reported having formal documentation for either the dosimeter, records system, or reader. Slightly greater than 50% of facilities reported having routine procedures in place. These are considered maximum percentages because some respondents considered computer codes as formal documentation. The repository receives data from DOE facilities regarding the (a) distribution of annual whole body doses, (b) significant internal depositions, and (c) individual doses upon termination. It is expected that numerous differences exist in the dose data submitted by the different facilities. Areas of significant differences would likely include the determination of non-measurable doses, the methods used to determine previous employer radiation dose, the methods of determining cumulative radiation dose, and assessment of internal doses. Undoubtedly, the accuracy of the different dosimetry systems, especially at low doses, is very important to the credibility of data summaries (e.g., man-rem) provided by the repository

Characterization of Iraq's remote nuclear facilities for decommissioning and waste management - 59167

International Nuclear Information System (INIS)

Al-Musawi, Fouad; Jarjies, Adnan; Miller, Ross A.

2012-01-01

The Government of Iraq (GOI) has undertaken efforts to decommission and dismantle former nuclear facilities. The GOI has only preliminary information on some of the former nuclear facilities. This paper will highlight the challenges involved in conducting inspections of the outlying former nuclear facilities in Iraq and present a brief summary of the results of those inspections. The facilities discussed in this paper are located at various sites throughout Iraq, from locations close to Baghdad to those in the north and far western desert areas. Some of the facilities, such as those at the Al Tuwaitha Nuclear Research Center have been visited and characterized. Other facilities, including the following, have not been visited or thoroughly characterized. - Al Jesira, Uranium feed stock production facility; - Adaya, Burial location for contaminated equipment; - Djerf al Naddah, Spent fuel storage facility; - Rashdiya, Centrifuge development center; - Al Qa'im, Uranium (yellowcake) production facility. The visits were conducted to develop an inventory of the buildings/structures that need to be included in decommissioning/dismantlement efforts. The number of buildings, type of construction, size and general condition of the buildings were noted. In addition, attempts were made to determine contamination levels on surfaces, equipment, rubble, etc. This information will be used to support the Iraqi decommissioning and dismantlement project. Because the facilities are scattered throughout the country of Iraq, significant planning and coordination was required to ensure personnel security. Teams consisting of individuals from the Iraqi Ministry of Science and Technology (MoST) and Americans were under military escort when traveling to and visiting the sites. Because of the security issues, time on the ground at each site was limited. This paper will highlight the challenges involved in conducting the inspections of the outlying former nuclear facilities In Iraq and

Relation of management, supervision, and personnel practices to nuclear power plant safety

International Nuclear Information System (INIS)

Layton, W.L.; Turnage, J.J.

1980-01-01

The knowledge base of industrial/organization psychology suggests three major areas of research with important implications for nuclear power plant safety. These areas are: Management and Supervision: Personnel Selection, Training and Placement; and Organizational Climate. Evidence drawn from several Three Mile Island investigations confirms that organizational structure of plants and supervisory practices, the selection and training of personnel, and organizational climate are important factors. Difficulties in decision making and coordination of personnel are pinpointed. Deficiencies in training are highlighted and the climate of working atmosphere is discussed. These matters are related to nuclear power plant safety. Future research directions are presented

Childhood leukemia around nuclear facilities

International Nuclear Information System (INIS)

1991-01-01

This Information Bulletin highlights the conclusion made from an Atomic Energy Control Board of Canada (AECB) study on the incidence of childhood leukemia near nuclear facilities. All of the locations with the nuclear facilities are located in Ontario, the nuclear generating stations at Pickering and Bruce; the uranium mines and mills in Elliot Lake; the uranium refining facility in Port Hope; and nuclear research facilities located at Chalk River plus the small nuclear power plant in Rolphton. Two conclusions are drawn from the study: 1) while the rate of childhood leukemias made be higher or lower than the provincial average, there is no statistical evidence that the difference is due to anything but the natural variation in the occurrence of the disease; and 2) the rate of occurrence of childhood leukemia around the Pickering nuclear power station was slightly greater than the Ontario average both before and after the plant opened, but this, too , could be due to the natural variation

Steel structures for nuclear facilities

International Nuclear Information System (INIS)

1993-01-01

In the guide the requirements concerning design and fabrication of steel structures for nuclear facilities and documents to be submitted to the Finnish Centre for Radiation and Nuclear Safety (STUK) are presented. Furthermore, regulations concerning inspection of steel structures during construction of nuclear facilities and during their operation are set forth

Decommissioning engineering systems for nuclear facilities and knowledge inheritance for decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Tachibana, Mitsuo

2016-01-01

Information on construction, operation and maintenance of a nuclear facility is essential in order to plan and implement the decommissioning of the nuclear facility. A decommissioning engineering system collects these information efficiently, retrieves necessary information rapidly, and support to plan the reasonable decommissioning as well as the systematic implementation of dismantling activities. Then, knowledge of workers involved facility operation and dismantling activities is important because decommissioning of nuclear facility will be carried out for a long period. Knowledge inheritance for decommissioning has been carried out in various organizations. This report describes an outline of and experiences in applying decommissioning engineering systems in JAEA and activities related to knowledge inheritance for decommissioning in some organizations. (author)

Individual radiological monitoring for exposed personnel of Nuclear Fuel Plant at Pitesti

International Nuclear Information System (INIS)

Ivana, T.; Epure, Gh.

2010-01-01

In the activity of nuclear fuel fabrication of CANDU type, based on natural and depleted uranium, individual radiological monitoring of the personnel exposed to ionizing radiation is very carefully approached. For Nuclear Fuel Plant (NFP) facility, where uranium appears in bulk and itemized form, measures for individual radiological monitoring are established by Radiological Safety Manual (MSR) in accordance with national and international legislation. All NFP employees are classified in either category A or category B of exposure to ionizing radiation. The classification is a function of type of activity and magnitude of exposure. All the exposed personnel are monitored for external doses (from gamma radiation) by measuring the equivalent dose H p (10) with monthly frequency. The system used for external individual dosimetric monitoring is based on the thermoluminescent dosimeter (TLD) of PANASONIC type UD813AS14. The NFP incorporates an in-house dosimetric laboratory notified by Romanian regulatory body CNCAN (National Commission for Control of Nuclear Activities). The workers handling nuclear materials are exposed to internal intake of uranium, mainly by inhalation. For internal doses monitoring is included part of exposed employees working directly with radioactive open sources (pulverulent or liquid nuclear materials), UO 2 sinterable powder, green pellets, sintered pellets, scrap and radioactive effluents. The estimation of internal exposure is made quarterly using the results from radioactive airborne monitors operating in the working places. The internal dose of each person exposed to open sources is calculated taking into account the rate of breathing, the time spent at the work place and the dose-activity coefficient (variable function of uranium absorption rate). The total effective individual dose is obtained by summing the external dose and internal dose (E=E ext +E int ). For conformity, the total effective individual dose (E) is compared with dose

DOE fundamentals handbook: Nuclear physics and reactor theory

International Nuclear Information System (INIS)

1993-01-01

The Nuclear Physics and Reactor Theory Handbook was developed to assist nuclear facility operating contractors in providing operators, maintenance personnel, and the technical staff with the necessary fundamentals training to ensure a basic understanding of nuclear physics and reactor theory. The handbook includes information on atomic and nuclear physics; neutron characteristics; reactor theory and nuclear parameters; and the theory of reactor operation. This information will provide personnel with a foundation for understanding the scientific principles that are associated with various DOE nuclear facility operations and maintenance

Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities

International Nuclear Information System (INIS)

Salmeron V, J. A.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Sanchez J, J.

2013-10-01

In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

AGING FACILITY WORKER DOSE ASSESSMENT

International Nuclear Information System (INIS)

R.L. Thacker

2005-01-01

The purpose of this calculation is to estimate radiation doses received by personnel working in the Aging Facility performing operations to transfer aging casks to the aging pads for thermal and logistical management, stage empty aging casks, and retrieve aging casks from the aging pads for further processing in other site facilities. Doses received by workers due to aging cask surveillance and maintenance operations are also included. The specific scope of work contained in this calculation covers both collective doses and individual worker group doses on an annual basis, and includes the contributions due to external and internal radiation from normal operation. There are no Category 1 event sequences associated with the Aging Facility (BSC 2004 [DIRS 167268], Section 7.2.1). The results of this calculation will be used to support the design of the Aging Facility and to provide occupational dose estimates for the License Application. The calculations contained in this document were developed by Environmental and Nuclear Engineering of the Design and Engineering Organization and are intended solely for the use of the Design and Engineering Organization in its work regarding facility operation. Yucca Mountain Project personnel from the Environmental and Nuclear Engineering should be consulted before use of the calculations for purposes other than those stated herein or use by individuals other than authorized personnel in Environmental and Nuclear Engineering

Use of COTS systems in I and C at nuclear facilities: implementation guide - TAFICS/IG/4

International Nuclear Information System (INIS)

2017-05-01

This TAFICS document contains guidance to Instrumentation and Control (I and C) designers and Operating and maintenance (O and M) personnel of nuclear facilities on how to securely plan, procure and use commercial off-the shelf (COTS) systems in nuclear facilities I and C. It describes the cyber security risks involved in use of COTS systems during aIl the life cycle phases and provides recommendations to mitigate these risks. The life cycle phases covered are: I and C architectural design, procurement including acceptance - installation and commissioning, O and M and disposal. This document also provides guidance on various sanitisation methods that can be used for COTS systems or components relevant to I and C. (author)

Nuclear facilities

International Nuclear Information System (INIS)

Anon.

2000-01-01

Here is given the decree (2000-1065) of the 25. of October 2000 reporting the publication of the convention between the Government of the French Republic and the CERN concerning the safety of the LHC (Large Hadron Collider) and the SPS (Proton Supersynchrotron) facilities, signed in Geneva on July 11, 2000. By this convention, the CERN undertakes to ensure the safety of the LHC and SPS facilities and those of the operations of the LEP decommissioning. The French legislation and regulations on basic nuclear facilities (concerning more particularly the protection against ionizing radiations, the protection of the environment and the safety of facilities) and those which could be decided later on apply to the LHC, SPS and auxiliary facilities. (O.M.)

Safety assessment and surveillance of decommissioning operations at DOE's nuclear facilities

International Nuclear Information System (INIS)

Cowgill, M.G.; Prochnow, D.; Worthington, P.R.

1995-01-01

A description is provided of a systematic approach currently being developed and deployed at the Department of Energy to obtain assurance that post-operational activities at nuclear facilities will be conducted in a safe manner. Using this approach, personnel will have available a formalized set of safety principles and associated question sets to assist them in the conducting of safety assessments and surveillance. Information gathered through this means will also be analyzed to determine if there are any generic complex-wide strengths or deficiencies associated with decommissioning activities and to which attention should be drawn

Role of the State Office for Nuclear Safety in testing special professional competence of selected personnel of nuclear facilities and selected personnel handling ionizing radiation sources

International Nuclear Information System (INIS)

Kovar, P.

2003-01-01

The laws and regulations governing the title topic are identified. The following terms are defined and their context highlighted: professional competence; special professional competence; selected personnel; requirements for selected personnel; requirements for selected personnel training; examination boards; and licensing procedure. (P.A.)

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.

Licensing requirements regarding the qualification of operating personnel in nuclear power plants

International Nuclear Information System (INIS)

Fechner, J.B.

1981-01-01

The legal requirements regarding the qualifications of operating personnel in nuclear power plants in the Federal Republic of Germany are outlined as in article 7 of the Atomic Energy Act. For the responsible operating personnel the requisite competence and reliability are legally required; for subordinate personnel the law requires only the necessary knowledge. The requisite competence and the necessary knowledge have been further specified in a set of guidelines by the authorities; work on specification of reliability requirements is under way. Essential elements of the requisite competence of responsible operating personnel are their professional qualification, their safety-related knowledge, their abilities, their practical experience, and - for the responsible shift personnel - their nuclear, plant-related training as well as a written and oral examination. Requalification is indispensible for keeping the requisite competence on a level in accordance with the current state of science and technology. Facts concerning the personal reliability of the responsible operating personnel are assessed by the competent authorities on the basis of information available at other state institutions. For the responsible shift personnel, physical and psychological fitness are important factors contributing to their reliability. The necessary knowledge subordinate operating personnel must possess with respect to plant safety and safety of the personnel is assured via instruction on safety and via special briefings at the working place. Lack of safety-related knowledge has to be compensated for by assigning an experienced permanent supervisor for each activity in question. Current work on qualification of operating personnel concentrates on training, including simulator training, of responsible shift personnel. (author)

Educational systems - educational qualification of nuclear power plant personnel

International Nuclear Information System (INIS)

Boeger, H.

1986-01-01

In this lecture the following common features of education and training systems are described: - description of general school education, vocational training and engineering study programs, - allocation of categories of activities to normal school training backgrounds, - recommendations for educational and training programs required for various positions in nuclear power plants (formal and on-the-job training), - examinations and licences for the personnel at nuclear power plants. (orig./GL)

Special feature article-very urgent nuclear energy personnel training

International Nuclear Information System (INIS)

Saito, Shinzo; Tsujikura, Yonezo; Kawahara, Akira

2007-01-01

Securing human resources is important for the sustainable development of research, development and utilization of nuclear energy. However, concerns have been raised over the maintenance of human resources due to the decline of public and private investment in research and development of nuclear energy in recent years. To that end, it is essential for the workplace in the field of nuclear energy to be engaging. This special feature article introduced the Government's fund program supporting universities and vocational colleges to develop human resources in the area of nuclear energy. Electric utilities, nuclear industries, nuclear safety regulators and related academia presented respective present status and issues of nuclear energy personnel training with some expectations to the program to secure human resources with professional qualifications. (T. Tanaka)

Base isolation for nuclear power and nuclear material facilities

International Nuclear Information System (INIS)

Eidinger, J.M.; Kircher, C.A.; Vaidya, N.; Constantinou, M.; Kelly, J.M.; Seidensticker, R.; Tajirian, F.F.; Ovadia, D.

1989-01-01

This report serves to document the status of the practice for the use of base isolation systems in the design and construction of nuclear power and nuclear material facilities. The report first describes past and current (1989) applications of base isolation in nuclear facilities. The report then provides a brief discussion of non-nuclear applications. Finally, the report summarizes the status of known base-isolation codes and standards

Radiation Monitoring in a Newly Established Nuclear Medicine Facility

International Nuclear Information System (INIS)

Afroj, Kamila; Anwar-Ul-Azim, Md.; Nath, Khokon Kumar; Khan, Md. Rezaul Karim

2010-05-01

A study of area monitoring in a nuclear medicine department's new physical facility was performed for 3 months to ascertain the level of radiation protection of the staff working in nuclear medicine and that of the patients and patient's attendants. Exposure to nuclear medicine personnel is considered as occupational exposure, while exposure to patients is considered medical exposure and exposure to patients' attendants is considered public exposure. The areas for the sources of radiation considered were the hot laboratory, where unsealed isotopes, radionuclides, generators are stored and dosages are prepared, the patients' waiting room, where the radioactive nuclides are administered orally and intravenously for diagnosis and treatment and the SPECT rooms, where the patients' acquisition are taken. The monitoring process was performed using the TLD supplied and measured by the Health Physics Division of Bangladesh Atomic Energy Commission. The result shows no over-exposure of radiation from any of the working areas. The environment of the department is safe for work and free from unnecessary radiation exposure risk. (author)

Environmental assessment report: Nuclear Test Technology Complex. [Construction and operation of proposed facility

Energy Technology Data Exchange (ETDEWEB)

Tonnessen, K.; Tewes, H.A.

1982-08-01

The US Department of Energy (USDOE) is planning to construct and operate a structure, designated the Nuclear Test Technology Complex (NTTC), on a site located west of and adjacent to the Lawrence Livermore National Laboratory. The NTTC is designed to house 350 nuclear test program personnel, and will accommodate the needs of the entire staff of the continuing Nuclear Test Program (NTP). The project has three phases: land acquisition, facility construction and facility operation. The purpose of this environmental assessment report is to describe the activities associated with the three phases of the NTTC project and to evaluate potential environmental disruptions. The project site is located in a rural area of southeastern Alameda County, California, where the primary land use is agriculture; however, the County has zoned the area for industrial development. The environmental impacts of the project include surface disturbance, high noise levels, possible increases in site erosion, and decreased air quality. These impacts will occur primarily during the construction phase of the NTTC project and can be mitigated in part by measures proposed in this report.

H.R. 3521: Nuclear Facilities Occupational Safety Improvement Act of 1989. Introduced in the House of Representatives, One Hundredth First Congress, First Session, October 25, 1989

International Nuclear Information System (INIS)

Anon.

1989-01-01

Bill H.R.3521 was introduced in the House of Representatives of the United States on October 25, 1989. The purpose of this Act and the amendments made by this Act are to improve and enforce standards for employee health and safety at Department of Energy nuclear facilities. Congress finds that worker health and safety at Department of Energy nuclear facilities could be made substantially safer by applying standards developed by experts in the field of occupational health and safety. A section-by-section analysis makes up most of the report with emphasis on the following: application of OSHA to DOE nuclear facilities; cooperation with inspections and investigations; transfer and allocation of appropriations and personnel; worker training requirements; performance of NIOSH functions at DOE nuclear facilities; medical examinations of employees; and labor-management health and safety committees at DOE nuclear facilities

Development of methods for nuclear power plant personnel qualifications and training

International Nuclear Information System (INIS)

Jorgensen, C.C.; Carter, R.J.

1985-01-01

The Nuclear Regulatory Commission (NRC) has proposed that additions and revisions should be made to Title 10 of the ''Code of Federal Regulations,'' Parts 50 and 55, and to Regulatory Guides 1.8 and 1.149. Oak Ridge National Laboratory (ORNL) is developing methods and some aspects of the technical basis for the implementation and assessment of training programs, personnel qualifications, and simulation facilities to be designed in accordance with the proposed rule changes. The paper describes the three methodologies which were developed during the FY-1984 research. The three methodologies are: (1) a task sort procedure (TSORT); (2) a simulation facility evaluation methodology; and (3) a task analysis profiling system (TAPS). TAPS is covered in detail in this paper. The task analysis profiling system has been designed to support training research. It draws on artificial intelligence concepts of pattern matching to provide an automated task analysis of normal English descriptions of job behaviors. TAPS development consisted of creating a precise method for the definition of skills, knowledge, abilities, and attitudes (SKAA), and generating SKAA taxonomic elements. It systematically outputs skills, knowledge, attitudes, and abilities, and information associated with them

Nuclear criticality safety basics for personnel working with nuclear fissionable materials. Phase I

International Nuclear Information System (INIS)

Vausher, A.L.

1984-10-01

DOE order 5480.1A, Chapter V, ''Safety of Nuclear Facilities,'' establishes safety procedures and requirements for DOE nuclear facilities. The ''Nuclear Criticality Safety Basic Program - Phase I'' is documented in this report. The revised program has been developed to clearly illustrate the concept of nuclear safety and to help the individual employee incorporate safe behavior in his daily work performance. Because of this, the subject of safety has been approached through its three fundamentals: scientific basis, engineering criteria, and administrative controls. Only basics of these three elements were presented. 5 refs

Decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Lunning, W.H.

1977-01-01

Collaborative studies are in progress in the U.K. between the U.K.A.E.A., the Generating Boards and other outside bodies, to identify the development issues and practical aspects of decommissioning redundant nuclear facilities. The various types of U.K.A.E.A. experimental reactors (D.F.R., W.A.G.R , S.G.H.W.R.) in support of the nuclear power development programme, together with the currently operating commercial 26 Magnox reactors in 11 stations, totalling some 5 GW will be retired before the end of the century and attention is focussed on these. The actual timing of withdrawal from service will be dictated by development programme requirements in the case of experimental reactors and by commercial and technical considerations in the case of electricity production reactors. Decommissioning studies have so far been confined to technical appraisals including the sequence logic of achieving specific objectives and are based on the generally accepted three stage progression. Stage 1, which is essentially a defuelling and coolant removal operation, is an interim phase. Stage 2 is a storage situation, the duration of which will be influenced by environmental pressures or economic factors including the re-use of existing sites. Stage 3, which implies removal of all active and non-active waste material and returning the site to general use, must be the ultimate objective. The engineering features and the radioactive inventory of the system must be assessed in detail to avoid personnel or environmental hazards during Stage 2. These factors will also influence decisions on the degree of Stage 2 decommissioning and its duration, bearing in mind that for Stage 3 activation may govern the waste disposal route and the associated radiation man-rem exposure during dismantling. Ideally, planning for decommissioning should be considered at the design stage of the facility. An objective of present studies is to identify features which would assist decommissioning of future systems

Requirement profile for nuclear power station personnel

International Nuclear Information System (INIS)

Roeglin, H.C.

1984-01-01

The starting point in deriving the requirement profile for the shift personnel in the control rooms of nuclear power stations is information of a technical, organisational and ergonomic kind. The technique used, the distribution of work to different work areas and the configuration of the workplace is determined by the tasks and the environmental conditions in which they have to be done. (orig./DG) [de

41 CFR 101-39.102-1 - Records, facilities, personnel, and appropriations.

Science.gov (United States)

2010-07-01

..., TRANSPORTATION, AND MOTOR VEHICLES 39-INTERAGENCY FLEET MANAGEMENT SYSTEMS 39.1-Establishment, Modification, and Discontinuance of Interagency Fleet Management Systems § 101-39.102-1 Records, facilities, personnel, and appropriations. (a) If GSA decides to establish a fleet management system, GSA, with the assistance of the...

Nuclear Regulatory Authority Personnel Educating and Training within the National Nuclear Program Development

International Nuclear Information System (INIS)

Potapov, V.; Goryaeva, T.; Moiseenko, A.; Kapralov, E.; Museridze, A.

2014-01-01

International Cooperation for Nuclear Education and Knowledge: Aims: •Creation of system of continuous personnel training for EvrAzES states in the field of nuclear power applications based on the international standards; •Development of educational service export as following of export of Russian nuclear technology; • Development of educational and scientific contacts to IAEA, WNU, ENEN, ANENT, biggest scientific centers and universities of USA, EU and Asia. Directions of activities: • Education. Transfer of knowledge to new generation, to new developing countries and cooperation with the nuclear education of leading powers; • Scientific enlightening activity – students, specialists, decision makers; • Informational and analytical work

Experience in the use of systematic approach to training (SAT) for nuclear power plant personnel

International Nuclear Information System (INIS)

1998-12-01

One of the essential requirements for safe and reliable nuclear power plant operation and maintenance is the availability of competent personnel, and thus systematic approach to training (SAT) is recognized world-wide. Many countries have applied and implemented the use of SAT in their training systems as demonstrated by the results of the IAEA World Survey on Nuclear Power Plant Personnel Training. This report complements two IAEA publications, the Guidebook on Nuclear Power Plant Personnel and its Evaluation (Technical Reports Series No. 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training (IAEA-TECDOC-1063). It provides a detailed overview and analysis of the experience gained worldwide on the introduction and application of SAT, including the reasons why SAT was introduced and lessons learned. The technical document will be of use for nuclear power plant managers and supervisors and all those responsible for training of personnel. The report was initiated by the International Working Group at a Technical Committee Meeting. Experiences gained from the application of SAT in the following Member States are included: Armenia, Bulgaria, Canada, China, Czech Republic, Finland, France, Germany, Hungary, India, Kazakhstan, Lithuania, Mexico, Romania, Russian Federation, Slovenia, Slovakia, Spain, Sweden, Ukraine, United Kingdom and United States of America

Experience in the use of systematic approach to training (SAT) for nuclear power plant personnel

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

One of the essential requirements for safe and reliable nuclear power plant operation and maintenance is the availability of competent personnel, and thus systematic approach to training (SAT) is recognized world-wide. Many countries have applied and implemented the use of SAT in their training systems as demonstrated by the results of the IAEA World Survey on Nuclear Power Plant Personnel Training. This report complements two IAEA publications, the Guidebook on Nuclear Power Plant Personnel and its Evaluation (Technical Reports Series No. 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training (IAEA-TECDOC-1063). It provides a detailed overview and analysis of the experience gained worldwide on the introduction and application of SAT, including the reasons why SAT was introduced and lessons learned. The technical document will be of use for nuclear power plant managers and supervisors and all those responsible for training of personnel. The report was initiated by the International Working Group at a Technical Committee Meeting. Experiences gained from the application of SAT in the following Member States are included: Armenia, Bulgaria, Canada, China, Czech Republic, Finland, France, Germany, Hungary, India, Kazakhstan, Lithuania, Mexico, Romania, Russian Federation, Slovenia, Slovakia, Spain, Sweden, Ukraine, United Kingdom and United States of America. Refs, figs, tabs

Analysis phase of systematic approach to training (SAT) for nuclear plant personnel

International Nuclear Information System (INIS)

2000-08-01

The IAEA and many Member States have recognized the benefits of a systematic approach when training nuclear power plant personnel. The Systematic Approach to Training (SAT) fully described in the IAEA publications, is recommended as the best practice for attaining and maintaining the competence and qualification of NPP personnel. Typically, SAT is organised into distinct phases of Analysis, Design, Development, Implementation, and Evaluation, and relies on Feedback as a process for continuous improvement This document is addressed to nuclear power operating organisations facing the challenge of developing training programs for their own personnel. The intention was to provide Member States with examples of the Analysis phase to form foundation of SAT-based training programs. This document is also available in CD form

Radiological controls and worker and public health and safety: An independent safety assessment of Department of Energy nuclear reactor facilities

International Nuclear Information System (INIS)

Tew, J.L.; Miles, M.E.; Knuth, D.; Boyd, R.

1981-02-01

DOE has formed a Nuclear Facilities Personnel Qualification and Training (NFPQT) Committee to assess the implications of the Report of the President's Commission on the Accident at Three Mile Island that are applicable to DOE's nuclear reactor operations. Thirteen DOE nuclear reactors were reviewed by the Committee. This report was prepared to provide a measure of how the radiological control and environmental practices at the 13 individual DOE reactor facilities measure up to (1) the recommendations contained in the Report of the President's Commission on the Accident at Three Mile Island, (2) the requirements and guidelines contained, and (3) the requirements of the applicable Title and Part of the Code of Federal Regulations

Pumps for nuclear facilities

International Nuclear Information System (INIS)

1999-01-01

The guide describes how the Finnish Radiation and Nuclear Safety Authority (STUK) controls pumps and their motors at nuclear power plants and other nuclear facilities. The scope of the control is determined by the Safety Class of the pump in question. The various phases of the control are: (1) review of construction plan, (2) control of manufacturing, and construction inspection, (3) commissioning inspection, and (4) control during operation. STUK controls Safety Class 1, 2 and 3 pumps at nuclear facilities as described in this guide. STUK inspects Class EYT (non-nuclear) pumps separately or in connection with the commissioning inspections of the systems. This guide gives the control procedure and related requirements primarily for centrifugal pumps. However, it is also applied to the control of piston pumps and other pump types not mentioned in this guide

Means of evaluating and improving the effectiveness of training of nuclear power plant personnel

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

, weaknesses can be identified and improvements made. These improvements should support an overall improvement in plant performance. Strengths can also be identified to further strengthen the positive aspects of the organization. This report provides information on methods and practices used to evaluate and improve the effectiveness of training. This should result in: plant performance improvement, improved human performance, meeting goals and objectives of the business (quality, safety, productivity), and improving training programmes. This publication is available in two formats, as a conventional printed publication and as a CD-ROM which also contains original contributions in the original language by Member States. The purpose of this report is to provide information on methods and practices to evaluate and improve the effectiveness of training and assistance for nuclear facility managers to establish and maintain effective training programmes for NPP personnel. In this context, the term training effectiveness means that training provides significant added value to NPP operations by improved safety, quality and production. This publication also contains several examples to identify and improve the effectiveness of NPP training programmes. In their respective NPPs, these examples demonstrate that effective training programmes are reflected in improved personnel performance, improved plant performance, and therefore, the achievement of NPP goals and objectives.

Means of evaluating and improving the effectiveness of training of nuclear power plant personnel

International Nuclear Information System (INIS)

2003-07-01

, weaknesses can be identified and improvements made. These improvements should support an overall improvement in plant performance. Strengths can also be identified to further strengthen the positive aspects of the organization. This report provides information on methods and practices used to evaluate and improve the effectiveness of training. This should result in: plant performance improvement, improved human performance, meeting goals and objectives of the business (quality, safety, productivity), and improving training programmes. This publication is available in two formats, as a conventional printed publication and as a CD-ROM which also contains original contributions in the original language by Member States. The purpose of this report is to provide information on methods and practices to evaluate and improve the effectiveness of training and assistance for nuclear facility managers to establish and maintain effective training programmes for NPP personnel. In this context, the term training effectiveness means that training provides significant added value to NPP operations by improved safety, quality and production. This publication also contains several examples to identify and improve the effectiveness of NPP training programmes. In their respective NPPs, these examples demonstrate that effective training programmes are reflected in improved personnel performance, improved plant performance, and therefore, the achievement of NPP goals and objectives

Facilities and procedures used for the performance testing of DOE personnel dosimetry systems

Energy Technology Data Exchange (ETDEWEB)

Roberson, P.L.; Fox, R.A.; Hogan, R.T.; Holbrook, K.L.; Hooker, C.D.; Yoder, R.C.

1983-04-01

Radiological calibration facilities for personnel dosimeter testing were developed at the Pacific Northwest Laboratory (PNL) for the Department of Energy (DOE) to provide a capability for evaluating the performance of DOE personnel dosimetry systems. This report includes the testing methodology used. The informational presented here meets requirements specified in draft ANSI N13.11 for the testing laboratory. The capabilities of these facilities include sealed source irradiations for /sup 137/Cs, several beta-particle emitters, /sup 252/Cf, and machine-generated x-ray beams. The x-ray beam capabilities include filtered techniques maintained by the National Bureau of Standards (NBS) and K-fluorescent techniques. The calibration techniques, dosimeter irradiation procedures, and dose-equivalent calculation methods follow techniques specified by draft ANSI N13.11 where appropriate.

Facilities and procedures used for the performance testing of DOE personnel-dosimetry systems

International Nuclear Information System (INIS)

Roberson, P.L.; Fox, R.A.; Hogan, R.T.; Holbrook, K.L.; Hooker, C.D.; Yoder, R.C.

1983-04-01

Radiological calibration facilities for personnel dosimeter testing were developed at the Pacific Northwest Laboratory (PNL) for the Department of Energy (DOE) to provide a capability for evaluating the performance of DOE personnel dosimetry systems. This report includes the testing methodology used. The informational presented here meets requirements specified in draft ANSI N13.11 for the testing laboratory. The capabilities of these facilities include sealed source irradiations for 137 Cs, several beta-particle emitters, 252 Cf, and machine-generated x-ray beams. The x-ray beam capabilities include filtered techniques maintained by the National Bureau of Standards (NBS) and K-fluorescent techniques. The calibration techniques, dosimeter irradiation procedures, and dose-equivalent calculation methods follow techniques specified by draft ANSI N13.11 where appropriate

Staffing of nuclear power plants and the recruitment, training and authorization of operating personnel

International Nuclear Information System (INIS)

1979-01-01

The Guide is a part of the International Atomic Energy Agency's programme, referred to as the NUSS (Nuclear Safety Standards) programme, for establishing Codes of Practice and Safety Guides relating to nuclear power plants. It outlines the various factors to be considered in order to ensure that the Operating Organization has a sufficient number of qualified site personnel who are clearly aware of their duties and responsibilities. The Guide covers the organization for a nuclear power plant, the educational qualifications and experience of the persons who are recruited for plant operation, the recruitment and training schedule, the training of operating personnel, the authorizations for persons whose duties have an immediate bearing on safety, and re-training of personnel. The provisional list of NUSS programme titles is attached

Organization and management for decommissioning of large nuclear facilities

International Nuclear Information System (INIS)

2000-01-01

For nuclear facilities, decommissioning is the final phase in the life-cycle after siting, design, construction, commissioning and operation. It is a complex process involving operations such as detailed surveys, decontamination and dismantling of plant equipment and facilities, demolition of buildings and structures, and management of resulting waste and other materials, whilst taking into account aspects of health and safety of the operating personnel and the general public, and protection of the environment. Careful planning and management is essential to ensure that decommissioning is accomplished in a safe and cost effective manner. Guidance on organizational aspects may lead to better decision making, reductions in time and resources, lower doses to the workers and reduced impact on public health and the environment. The objective of this report is to provide information and guidance on the organization and management aspects for the decommissioning of large nuclear facilities which will be useful for licensees responsible for discharging these responsibilities. The information contained in the report may also be useful to policy makers, regulatory bodies and other organizations interested in the planning and management of decommissioning. In this report, the term 'decommissioning' refers to those actions that are taken at the end of the useful life of a nuclear facility in withdrawing it from service with adequate regard for the health and safety of workers and members of the public and for the protection of the environment. The term 'large nuclear facilities' involves nuclear power plants, large nuclear research reactors and other fuel cycle facilities such as reprocessing plants, fuel conversion, fabrication and enrichment plants, as well as spent fuel storage and waste management plants. Information on the planning and management for decommissioning of smaller research reactors or other small nuclear facilities can be found elsewhere. The report covers

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-08-01

Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-06-01

Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers [es

The Physical Protection of Nuclear Material and Nuclear Facilities

International Nuclear Information System (INIS)

1999-06-01

Physical protection against the theft or unauthorized diversion of nuclear materials and against the sabotage of nuclear facilities by individuals or groups has long been a matter of national and international concern. Although responsibility for establishing and operating a comprehensive physical protection system for nuclear materials and facilities within a State rests entirely with the Government of that State, it is not a matter of indifference to other States whether and to what extent that responsibility is fulfilled. Physical protection has therefore become a matter of international concern and co-operation. The need for international co-operation becomes evident in situations where the effectiveness of physical protection in one State depends on the taking by other States also of adequate measures to deter or defeat hostile actions against nuclear facilities and nuclear materials, particularly when such materials are transported across national frontiers

10 CFR 50.120 - Training and qualification of nuclear power plant personnel.

Science.gov (United States)

2010-01-01

... 10 Energy 1 2010-01-01 2010-01-01 false Training and qualification of nuclear power plant... Training and qualification of nuclear power plant personnel. (a) Applicability. The requirements of this... each holder of a combined license issued under part 52 of this chapter for a nuclear power plant of the...

Nuclear physics accelerator facilities of the world

International Nuclear Information System (INIS)

1991-12-01

this report is intended to provide a convenient summary of the world's major nuclear physics accelerator facility with emphasis on those facilities supported by the US Department of Energy (DOE). Previous editions of this report have contained only DOE facilities. However, as the extent of global collaborations in nuclear physics grows, gathering summary information on the world's nuclear physics accelerator facilities in one place is useful. Therefore, the present report adds facilities operated by the National Science Foundation (NSF) as well as the leading foreign facilities, with emphasis on foreign facilities that have significant outside user programs. The principal motivation for building and operating these facilities is, of course, basic research in nuclear physics. The scientific objectives for this research were recently reviewed by the DOE/NSF Nuclear Science Advisory Committee, who developed a long range plan, Nuclei, Nucleons, and Quarks -- Nuclear Science in the 1990's. Their report begins as follows: The central thrust of nuclear science is the study of strongly interacting matter and of the forces that govern its structure and dynamics; this agenda ranges from large- scale collective nuclear behavior through the motions of individual nucleons and mesons, atomic nuclei, to the underlying distribution of quarks and gluons. It extends to conditions at the extremes of temperature and density which are of significance to astrophysics and cosmology and are conducive to the creation of new forms of strongly interacting matter; and another important focus is on the study of the electroweak force, which plays an important role in nuclear stability, and on precision tests of fundamental interactions. The present report provides brief descriptions of the accelerator facilities available for carrying out this agenda and their research programs

Model of tritium transfer into environment by the personnel of nuclear enterprises

International Nuclear Information System (INIS)

Batalin, J.; Krechetova, A.

2004-01-01

One of the ways of radionuclide transfer from a nuclear enterprise into an environment is analysed. This way of transfer is the transport of radionuclides by the personnel of a nuclear enterprise. During an active work in a nuclear enterprise the personnel accumulate radionuclides from the air of industrial premises. Accumulated radionuclides are released from the organism into an environment according to the effective period of half-draw. The main part of radionuclides is transferred from the organism of professional workers into an environment: first of all into the air and on furniture of their dwellings and later - into the organisms of their family members. In this way contamination of workers' dwellings and irradiation of their family members exceed the contamination through air and water. The model is confirmed as an example of tritium transfer from nuclear enterprises. (author)

Nuclear facilities in the Federal Republic of Germany

International Nuclear Information System (INIS)

1991-01-01

The information brochure is a survey of installed nuclear facilities in Germany, presenting on one page each a picture of a nuclear power plant together with the main relevant data, or of other type of nuclear facilities belonging to the nuclear fuel cycle (such as fuel production plant, fuel production plant, fuel element storage facilities, and facilities for spent fuel and waste management). (UA) [de

Nonreactor nuclear facilities: standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Junker, L.; Karol, R.C.; Lobner, P.R.; Goldman, L.A.

1981-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE Order 5480.1, Chapter V, Safety of Nuclear Facilities. The guidance and criteria provided are directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. These general guidelines may have limited applicability to subsurface facilities such as waste repositories. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines

Personnel supply and demand issues in the nuclear power industry. Final report of the Nuclear Manpower Study Committee

International Nuclear Information System (INIS)

1981-01-01

The anticipated personnel needs of the nuclear power industry have varied widely in recent years, in response to both increasing regulatory requirements and declining orders for new plants. Recent employment patterns in the nuclear energy field, with their fluctuations, resemble those of defense industries more than those traditionally associated with electric utilities. Reactions to the accident at Three Mile Island Unit 2 by industry and regulators have increased the demand for trained and experienced personnel, causing salaries to rise. Industry, for example, has established several advisory organizations like the Institute for Nuclear Power Operations (INPO). At the same time, the US Nuclear Regulatory Commission (NRC) has imposed many new construction and operating requirements in an effort to take advantage of lessons learned from the Three Mile Island incident and to respond to the perceived public interest in better regulation of nuclear power. Thus, at present, utilities, architect-engineer firms, reactor vendors, and organizations in the nuclear development community have heavy workloads

Nuclear and radioactivity

International Nuclear Information System (INIS)

2000-01-01

Among the industrial risks of nuclear facilities, the nuclear risk is often associated to the Chernobyl accident. This paper presents the nuclear major risk in a french PWR type power plant, with consequences on the personnel, the surrounding population and the environment. (A.L.B.)

H.R. 2098: This Act may be cited as the Nuclear Facilities Occupational Safety Improvement Act of 1991, introduced in the US House of Representatives, One Hundred Second Congress, First Session, April 25, 1991

International Nuclear Information System (INIS)

Anon.

1991-01-01

Worker health and safety at Department of Energy nuclear facilities could be made substantially safer by applying standards developed by experts in the field of occupational health and safety. This bill was introduced into the US House of Representatives on April 25, 1991 to amend the Occupational Safety and Health Act of 1970 to improve and enforce standards for employee health and safety at Department of Energy nuclear facilities. Individual sections address the following: application of OSHA to DOE nuclear facilities; cooperation with inspections and investigations; transfer and allocation of appropriations and personnel; worker training requirements; performance of NIOSH functions at DOE nuclear facilities; medical examinations of employees at DOE nuclear facilities; and labor-management health and safety committees at Doe nuclear facilities

Technical Cybersecurity Controls for Nuclear Facilities

International Nuclear Information System (INIS)

Oh, Jinseok; Ryou, Jaecheol; Kim, Youngmi; Jeong, Choonghei

2014-01-01

To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility

Technical Cybersecurity Controls for Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Oh, Jinseok; Ryou, Jaecheol [Chungnam National Univ., Daejeon (Korea, Republic of); Kim, Youngmi; Jeong, Choonghei [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2014-05-15

To strengthen cybersecurity for nuclear facilities, many countries take a regulatory approach. For example, US Government issued several regulations . Title 10, of the Code of Federal Regulations, Section 73.54, 'Protection of Digital Computer and Communication Systems and Networks (10 CFR 73.54) for cybersecurity requirements and Regulatory Guide 5.71 (RG. 5.71) for cybersecurity guidance and so on. In the case of Korea, Korean Government issued '8.22 Cybersecurity of I and C systems (KINS/RG-NO8.22). In particular, Reg. 5.71 provides a list of security controls to address the potential cyber risks to a nuclear facilities. Implementing and adopting security controls, we can improve the level of cybersecurity for nuclear facilities. RG 5.71 follows the recommendation of NIST SP 800-53. NIST standard provides security controls for IT systems. And NRC staff tailored the controls in NIST standards to unique environments of nuclear facilities. In this paper, we are going to analysis and compare NRC RG 5.71 and NIST SP800-53, in particular, for technical security controls. If RG 5.71 omits the specific security control that is included in SP800-53, we would review that omitting is adequate or not. If RG 5.71 includes the specific security control that is not included in SP800-53, we would also review the rationale. And we are going to some security controls to strengthen cybersecurity of nuclear facilities. In this paper, we compared and analyzed of two regulation in technical security controls. RG 5.71 that is based on NIST standard provides well-understood security controls for nuclear facility. But some omitting from NIST standard can threaten security state of nuclear facility.

Earthquake engineering for nuclear facilities

CERN Document Server

Kuno, Michiya

2017-01-01

This book is a comprehensive compilation of earthquake- and tsunami-related technologies and knowledge for the design and construction of nuclear facilities. As such, it covers a wide range of fields including civil engineering, architecture, geotechnical engineering, mechanical engineering, and nuclear engineering, for the development of new technologies providing greater resistance against earthquakes and tsunamis. It is crucial both for students of nuclear energy courses and for young engineers in nuclear power generation industries to understand the basics and principles of earthquake- and tsunami-resistant design of nuclear facilities. In Part I, "Seismic Design of Nuclear Power Plants", the design of nuclear power plants to withstand earthquakes and tsunamis is explained, focusing on buildings, equipment's, and civil engineering structures. In Part II, "Basics of Earthquake Engineering", fundamental knowledge of earthquakes and tsunamis as well as the dynamic response of structures and foundation ground...

Presentation of the process External communications on the nuclear facilities operation of the Adjunct Head Office of Nuclear Safety of Comision Nacional de Seguridad Nuclear y Salvaguardias; Presentacion del proceso Comunicaciones externas sobre el funcionamiento de instalaciones nucleares de la Direccion General Adjunta de Seguridad Nuclear de la Comision Nacional de Seguridad Nuclear y Salvaguardias

Energy Technology Data Exchange (ETDEWEB)

Espinosa V, J. M., E-mail: jmespinosa@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2012-10-15

The Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) in use of their attributions granted by the Regulation Law of the constitutional Art. 27 in nuclear matter began the development of the called process External communications on the nuclear facilities operation, with the purpose of negotiating the evaluation of the concerns related with the safety of the nuclear facilities received these of external people to the CNSNS. The process External communications on the nuclear facilities operation will allow to the public's members and the workers that carry out activities inside the mark regulator imposed by the CNSNS that report to this Commission their concerns related with safety for several means (for example, directly to the personnel of the assigned Office, official and public statements, phone communication, electronic mail, etc.) The present article presents the legal mark confers the CNSNS the attributions to develop the mentioned process and exposes the most important elements that compose it. The term External communication on the nuclear facilities operation is defined and also is described how these communications are received, evaluated and closed by the assigned Office. Of equal way the objectives that intents to reach this process are indicated. The intention of the mentioned process is to strengthen the actions that the CNSNS carries out in the execution of its functions to maintain the safety standards in the operation of the nuclear facilities in Mexico. (Author)

Nuclear fuel treatment facility for 'Mutsu'

International Nuclear Information System (INIS)

Kanazawa, Toshio; Fujimura, Kazuo; Horiguchi, Eiji; Kobayashi, Tetsuji; Tamekiyo, Yoshizou

1989-01-01

A new fixed mooring harbor in Sekinehama and surrounding land facilities to accommodate a test voyage for the nuclear-powered ship 'Mutsu' in 1990 were constructed by the Japan Atomic Energy Research Institute. Kobe Steel took part in the construction of the nuclear fuel treatment process in various facilities, beginning in October, 1988. This report describes the outline of the facility. (author)

Study on HVAC system in nuclear facility

International Nuclear Information System (INIS)

Baeg, S. Y.; Song, W. S.; Oh, Y. O.; Ju, Y. S.; Hong, K. P.

2003-01-01

Heating, Ventilation and Air Conditioning (HVAC) system in nuclear facility should be equipped and constructed more stable and allowable than that in common facility. The purpose of HVAC system is the maintenance of optimum working environment, the protection of worker against a contaminated air and the prevention of atmospheric contamination due to an outward ventilation, etc.. The basic scheme of a safety operation of nuclear facility is to prevent the atmospheric contamination even in low level. The adaptability of HVAC system which is in operation. In this study, the design requirements of HVAC system in nuclear facility and the HVAC systems in foreign countries are reviewed, and the results can be utilized in the design of HVAC system in nuclear facility

Methicillin-resistant Staphylococcus aureus isolates from surfaces and personnel at a hospital laundry facility.

Science.gov (United States)

Michael, K E; No, D; Roberts, M C

2016-09-01

Examine a clinical laundry facility for the presence of methicillin-resistant Staphylococcus aureus (MRSA) on environmental surfaces and among personnel. Nasal and face samples along with surface samples were collected four times in 2015. MRSA isolates were confirmed using standardized biochemical assays and molecular characterization. MRSA was identified in 33/120 (28%) samples from the dirty and 3/120 (3%) samples from the clean environmental areas. MRSA isolates included: (dirty) ST5 SCCmec type II, ST8 SCCmec type IV, ST231 SCCmec type II, ST239 SCCmec type III, ST239 SCCmec type IV, ST256 SCCmec type IV and (clean) ST5 SCCmec type II and ST8 SCCmec type IV. Five different employees were MRSA positive, 4/8 (50%) from the dirty: and 1/15 (6·7%) from the clean, but there was a 10-fold higher MRSA carriage 6/22 (27%) dirty vs 1/38 (2·6%) clean when all 50 human samples were combined. MRSA prevalence was significantly higher (28 vs 3%) in dirty vs clean areas within the laundry facility suggesting a greater risk for personnel on the dirty side. This is the first report of isolation and characterization of MRSA from surfaces and personnel from a clinical laundry facility. © 2016 The Society for Applied Microbiology.

International conference on knowledge management in nuclear facilities. Book of extended synopses

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-06-15

In recent years new issues have emerged in Member States, including ageing facilities and personnel, nuclear phase-out policies, the expectation of nuclear growth in some regions and the objective to further improve the economic competitiveness of nuclear energy while maintaining a high level of safety. Awareness of the importance of nuclear knowledge management in addressing the challenges the industry is facing has grown significantly, both in the industry and in regulatory authorities, and a large number of projects are under way. Knowledge management is becoming an important element of the organizational behaviour of the nuclear industry. In 2002, the IAEA General Conference adopted a new resolution on Nuclear Knowledge, emphasizing the importance of nuclear knowledge management. The resolution was reiterated in subsequent years. This conference is organized in response to those resolutions, also following the first conference on Nuclear Knowledge Management - Strategies, Information Management and Human Resource Development, organized by the IAEA in 2004 in France. The objectives of the conference are to: - Take stock of the recent developments in nuclear knowledge management; - Demonstrate and discuss the benefits of nuclear knowledge management in promoting excellence in operation and safety of nuclear facilities; - Promote the use of nuclear knowledge management in the nuclear industry; - Provide insights and recommendations to the nuclear community. The conference will address decision makers and professionals in the nuclear industry, including in particular all nuclear facilities in all phases of their life cycle, and from regulatory organizations, governments, academia, vendors and other bodies concerned with the topic. The conference will start with a policy forum: Policy Forum: Status, Strategic Perspectives and Key Issues Leaders from nuclear industry, governmental organizations, regulators, research institutes and international organizations will

Socket welds in nuclear facilities

International Nuclear Information System (INIS)

Anderson, P.A.; Torres, L.L.

1995-01-01

Socket welds are easier and faster to make than are butt welds. However, they are often not used in nuclear facilities because the crevices between the pipes and the socket sleeves may be subject to crevice corrosion. If socket welds can be qualified for wider use in facilities that process nuclear materials, the radiation exposures to welders can be significantly reduced. The current tests at the Idaho Chemical Processing Plant (ICPP) are designed to determine if socket welds can be qualified for use in the waste processing system at a nuclear fuel processing plant

Operational status of nuclear facilities in Japan. 2008 edition

International Nuclear Information System (INIS)

2008-01-01

This document is a summary of the outline of the safety regulation administration of nuclear facilities as well as various data on the commercial nuclear power reactor facilities, research and development nuclear power reactor facilities, fabrication facilities, reprocessing facilities, and disposal facilities in fiscal year 2007 (from April 2007 to March 2008). I sincerely hope this document is used widely by many people engaged in work related to ensuring nuclear safety. (J.P.N.)

Operational status of nuclear facilities in Japan. 2010 edition

International Nuclear Information System (INIS)

2010-01-01

This document is a summary of the outline of the safety regulation administration of nuclear facilities as well as various data on the commercial nuclear power reactor facilities, research and development nuclear power reactor facilities, fabrication facilities, reprocessing facilities, and disposal facilities in fiscal year 2009 (from April 2009 to March 2010). We sincerely hope this document is used widely by many people engaged in work related to ensuring nuclear safety. (author)

Nuclear materials facility safety initiative

International Nuclear Information System (INIS)

Peddicord, K.L.; Nelson, P.; Roundhill, M.; Jardine, L.J.; Lazarev, L.; Moshkov, M.; Khromov, V.V.; Kruchkov, E.; Bolyatko, V.; Kazanskij, Yu.; Vorobeva, I.; Lash, T.R.; Newton, D.; Harris, B.

2000-01-01

Safety in any facility in the nuclear fuel cycle is a fundamental goal. However, it is recognized that, for example, should an accident occur in either the U.S. or Russia, the results could seriously delay joint activities to store and disposition weapons fissile materials in both countries. To address this, plans are underway jointly to develop a nuclear materials facility safety initiative. The focus of the initiative would be to share expertise which would lead in improvements in safety and safe practices in the nuclear fuel cycle.The program has two components. The first is a lab-to-lab initiative. The second involves university-to-university collaboration.The lab-to-lab and university-to-university programs will contribute to increased safety in facilities dealing with nuclear materials and related processes. These programs will support important bilateral initiatives, develop the next generation of scientists and engineers which will deal with these challenges, and foster the development of a safety culture

Nuclear technology. All in good hands

International Nuclear Information System (INIS)

Mueller, Michaela

2011-01-01

Babcock Noell GmbH (BNG) has more than 40 years of practical experience and fundamental know-how in the field of nuclear technology and thus is well equipped to meet future challenges. This applies to building new nuclear power plants, upgrading and decommissioning existing facilities as well as to conditioning and storage of radioactive waste. BNG is a supplier of, among other things, components for machine technology, personnel and materials transfer locks, safety enclosures and pool liners. Outstanding, technically demanding reference projects have demonstrated BNG's capabilities. BNG is a reliable service and assembly partner to the operators of nuclear power plants and nuclear facilities. This sector of activities has as its backbone a separate team of experienced service and assembly personnel. The synergies of engineering and service competence intensively utilized by Babcock Noell GmbH are employed, inter alia, in the development and advanced development, respectively, of nuclear technology products fit for practical use, such as personnel and materials transfer locks. (orig.)

Nonreactor nuclear facilities: Standards and criteria guide

International Nuclear Information System (INIS)

Brynda, W.J.; Scarlett, C.H.; Tanguay, G.E.; Lobner, P.R.

1986-09-01

This guide is a source document that identifies standards, codes, and guides that address the nuclear safety considerations pertinent to nuclear facilities as defined in DOE 5480.1A, Chapter V, ''Safety of Nuclear Facilities.'' The guidance and criteria provided is directed toward areas of safety usually addressed in a Safety Analysis Report. The areas of safety include, but are not limited to, siting, principal design criteria and safety system design guidelines, radiation protection, accident analysis, conduct of operations, and quality assurance. The guide is divided into two sections: general guidelines and appendices. Those guidelines that are broadly applicable to most nuclear facilities are presented in the general guidelines. Guidelines specific to the various types or categories of nuclear facilities are presented in the appendices. These facility-specific appendices provide guidelines and identify standards and criteria that should be considered in addition to, or in lieu of, the general guidelines. 25 figs., 62 tabs

International guidance on the qualifications of nuclear power plant operations personnel

International Nuclear Information System (INIS)

Csik, B.J.

1984-01-01

Nuclear power plant operation and maintenance as well as training of operations personnel are activities where a large amount of experience is available. Though it would seem that the status of a well-established practice, requiring constant attention but no major efforts directed towards improvements, should have been reached, this is not the case. Currently, upgrading of the qualification requirements and training procedures of nuclear power plant operations personnel is a major issue and substantial efforts are being expended to this effect. The availability of international guidance in this field is perceived to be of benefit to all; therefore the Agency has undertaken to develop such guidance. In addition to earlier publications, a guidebook on this subject area is being prepared. Important problems and current issues have been identified and these are commented upon in the present paper. The specific topics referred to include: the role of the operating organization and the regulatory body; organizational aspects; staffing requirements; competence requirements for personnel; establishment and verification of competence; and personnel management. It is recognized that developing international guidance is a difficult and delicate task, especially when it is intended to go beyond stating the obvious and expressing generalities which are certain to meet a general consensus. (author)

Review of maintenance personnel practices at nuclear power plants

International Nuclear Information System (INIS)

Chockie, A.D.; Badalamente, R.V.; Hostick, C.J.; Vickroy, S.C.; Bryant, J.L.; Imhoff, C.H.

1984-05-01

As part of the Nuclear Regulatory Commission (NRC) sponsored Maintenance Qualifications and Staffing Project, the Pacific Northwest Laboratory (PNL) has conducted a preliminary assessment of nuclear power plant (NPP) maintenance practices. As requested by the NRC, the following areas within the maintenance function were examined: personnel qualifications, maintenance training, overtime, shiftwork and staffing levels. The purpose of the assessment was to identify the primary safety-related problems that required further analysis before specific recommendations can be made on the regulations affecting NPP maintenance operations

Storage of radioactive material - accidents - precipitation - personnel monitoring

International Nuclear Information System (INIS)

Matijasic, A.; Gacinovic, O.

1961-12-01

This volume covers the reports on four routine tasks concerned with safe handling of radioactive material and influence of nuclear facilities on the environment. The tasks performed were as follows: Storage of solid and liquid radioactive material; actions in case of accidents; radiation monitoring of the fallout, water and ground; personnel dosimetry

Computer security at ukrainian nuclear facilities: interface between nuclear safety and security

International Nuclear Information System (INIS)

Chumak, D.; Klevtsov, O.

2015-01-01

Active introduction of information technology, computer instrumentation and control systems (I and C systems) in the nuclear field leads to a greater efficiency and management of technological processes at nuclear facilities. However, this trend brings a number of challenges related to cyber-attacks on the above elements, which violates computer security as well as nuclear safety and security of a nuclear facility. This paper considers regulatory support to computer security at the nuclear facilities in Ukraine. The issue of computer and information security considered in the context of physical protection, because it is an integral component. The paper focuses on the computer security of I and C systems important to nuclear safety. These systems are potentially vulnerable to cyber threats and, in case of cyber-attacks, the potential negative impact on the normal operational processes can lead to a breach of the nuclear facility security. While ensuring nuclear security of I and C systems, it interacts with nuclear safety, therefore, the paper considers an example of an integrated approach to the requirements of nuclear safety and security

Physical fitness training reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

International Nuclear Information System (INIS)

Arzino, P.A.; Caplan, C.S.; Goold, R.E.

1991-09-01

The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs

Physical fitness training reference manual for security force personnel at fuel cycle facilities possessing formula quantities of special nuclear materials

Energy Technology Data Exchange (ETDEWEB)

Arzino, P.A.; Caplan, C.S.; Goold, R.E. (California State Univ., Hayward, CA (United States). Foundation)

1991-09-01

The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs.

Experiences in the use of systematic approach to training (SAT) for nuclear power plant personnel training. Working material. Final draft

International Nuclear Information System (INIS)

1997-07-01

This document complements two previous IAEA documents: the Guidebook on Nuclear Power Plant Personnel Training and its Evaluation (IAEA-TRS 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training. It provides a detailed overview and analysis of the experience gained world-wide on the introduction and use of SAT, including the reasons why SAT was introduced and important lessons learned. The Technical Document will be especially useful for nuclear power plant management and supervisors, all those responsible for the training of nuclear power plant personnel, and those in regulatory bodies whose duties relate to nuclear power plant personnel training and qualification. 41 refs, figs, tabs

Experiences in the use of systematic approach to training (SAT) for nuclear power plant personnel training. Working material. Final draft

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-07-01

This document complements two previous IAEA documents: the Guidebook on Nuclear Power Plant Personnel Training and its Evaluation (IAEA-TRS 380) and the IAEA World Survey of Nuclear Power Plant Personnel Training. It provides a detailed overview and analysis of the experience gained world-wide on the introduction and use of SAT, including the reasons why SAT was introduced and important lessons learned. The Technical Document will be especially useful for nuclear power plant management and supervisors, all those responsible for the training of nuclear power plant personnel, and those in regulatory bodies whose duties relate to nuclear power plant personnel training and qualification. 41 refs, figs, tabs.

Visitor centres at nuclear facility sites

International Nuclear Information System (INIS)

1993-01-01

Communications strategies in the nuclear field are often based on the creation of visitor centres at nuclear facility sites. Today, the design, as well as the realization and management of such centres has become a specialized function, and its role is very complementary to the nuclear operator's. It also uses the latest technology in the field of audio-visual, experiment and interactivity. This publication contains the proceedings of an international seminar organized by the OECD Nuclear Energy Agency on the role of visitor centres at nuclear facility sites. It includes the main papers presented at this Seminar

Creation of a new-generation research nuclear facility

International Nuclear Information System (INIS)

Girchenko, A.A.; Matyushin, A.P.; Kudryavtsev, E.M.; Skopin, V.P.; Shchepelev, R.M.

2013-01-01

The SO-2M research nuclear facility operated on the industrial area of the institute. The facility is now removed from service. In view of this circumstance, it is proposed to restore the facility at the new qualitative level, i.e., to create a new-generation research nuclear facility with a very high safety level consisting of a subcritical bench and a proton accelerator (electronuclear facility). Competitive advantages and design features have been discussed and the productive capacity of the research nuclear facility under development has been evaluated [ru

The nuclear industry's impact on health: the case of nuclear power station personnel

International Nuclear Information System (INIS)

Bertin, M.

1984-01-01

The effects of radiation on the health of personnel working in nuclear power stations appear to be non-existant or in any case so slight that they cannot be detected. This paper presents some data, hardly known until now, which corroborates this statement and then he analyses the problems involved in health studies [fr

Impact in the facilities design and the personnel formation of the hybrid equipment s: PET-CT

International Nuclear Information System (INIS)

Hernandez, R.; Soler, K.; Alonso, I.

2014-08-01

The Positron Emission Tomography-Computed Tomography (PET-CT), in the last years has demonstrated to be an image technique very effective for the diagnosis and the treatments continuation in different medical applications, because provides a valuable clinical information for the patient handling. The PET-CT is a technology used in the nuclear medicine for diagnostic, because integrates two different image techniques in an only device and in a single exam or study combine the results of both techniques. Also, is a hybrid tomograph that provides in a single image the biochemical information of a technique and the anatomical information of the other, what means that unifies the spatial resolution of a technique and the contrast resolution of the other, allowing this way to obtain a more precise and detailed diagnostic information, opening new opportunities in diagnostic, Radiotherapy planning and treatments continuation to the patients, being generated new links among the different radiological medical specialties. In nuclear medicine facilities with PET-CT, the radiological protection presents particular characteristics, due to the photons coexistence of 511 keV (generated by the annihilation of the emitted positrons from the different exposure sources) together to the X-rays emitted by the CT, what impacts in a direct way in those design requirements of the areas. On the other hand, this combination of the two image techniques imposes additional requirements to the learning and training of personnel, not considered until the present time. In this article are exposed the general principles that should be considered in the design of a Nuclear Medicine Area with PET-CT, and the existent problems related to the learning and training of personnel to assume this new technology are also approached. (Author)

Training of engineering support personnel at North Carolina State University

International Nuclear Information System (INIS)

Bohannon, J.R. Jr.

1975-01-01

The sources of planning for the development of curricula for engineering support personnel for the nuclear industry in general and nuclear facilities in particular have included the deliberate acquisition of inputs from employers, feedback from past students, and the critique of curricula by the industry, students, and faculty. As a result, three principal courses were developed in the Department of Nuclear Engineering, namely, Reactor Systems which deals in terms of the design engineer's and owner's concerns with regard to functional requirements, design criteria, and objectives of reactor systems; Reactor Operations which applies the student's basic engineering education to the role of an engineer in nuclear facilities, with particular attention to power plant operations; and Quality Assurance which provides the student with the bases, engineering implications and engineer's role in quality assurance during the design, construction, delivery and operation of nuclear and other complex facilities. A summary of the results to date of this trinity of courses is presented, with particular attention to its acceptance by the industry

Activities of the Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear facilities in the Slovak Republic in 1994

International Nuclear Information System (INIS)

1995-01-01

The report summarizes activities of the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1994 and briefly presents results of the national expert supervision over nuclear safety facilities in the SR in 1994. In 1994, the NRA SR have performed a national supervision of following organizations: SE, a.s. - Jaslovske Bohunice Nuclear Power Plant (V-1 Nuclear Power Plant (V-1 NPP), V-2 Nuclear Power Plant (V-2 NPP), A-1 Nuclear Power Plant (A-1 NPP)); Mochovce Nuclear Power Plant; Radioactive waste repository, Mochovce); Organizations providing a specialized training of NPP personnel; Organizations providing specific deliveries and activities for the nuclear power industry; Organizations having an owner of nuclear materials; Organizations providing activities related to import of radioactive sources; Organizations using radioactive sources. Organization structure of the NRA SR is explained. In the presented Chapter 1 - Safety of nuclear power plants in the Slovak Republic - safety aspects of the Slovak NPPs are reported. The next activities are reported: nuclear materials and safeguards; radioactive waste; emergency planning and NRA SR's control and crisis centre; international activities to improve the national surveillance quality; other activities

Perceived nuclear risk, organizational commitment, and appraisals of management: A study of nuclear power plant personnel

International Nuclear Information System (INIS)

Kivimaeki, M.; Kalimo, R.; Salminen, S.

1995-01-01

This study examined to what extent nuclear risk perceptions, organizational commitment (OC), and appraisals of management are associated with each other among nuclear power plant personnel. The sample consisted of 428 nuclear power plant workers who completed a questionnaire at their workplace. Perceived nuclear risk and OC were most closely related to the appraisals of the top management of the organization. As the trust in and satisfaction with the top management increased, perceived nuclear safety and acceptance of the organizational goals and values heightened. This result is discussed in the context of industrial safety management. 29 refs., 2 tabs

Status of safety at Areva group facilities. 2007 annual report

International Nuclear Information System (INIS)

2007-01-01

This report describes the status of nuclear safety and radiation protection in the facilities of the AREVA group and gives information on radiation protection in the service operations, as observed through the inspection programs and analyses carried out by the General Inspectorate in 2007. Having been submitted to the group's Supervisory Board, this report is sent to the bodies representing the personnel. Content: 1 - A look back at 2007 by the AREVA General Inspector: Visible progress in 2007, Implementation of the Nuclear Safety Charter, Notable events; 2 - Status of nuclear safety and radiation protection in the nuclear facilities and service operations: Personnel radiation protection, Event tracking, Service operations, Criticality control, Radioactive waste and effluent management; 3 - Performance improvement actions; 4 - Description of the General Inspectorate; 5 - Glossary

Methodology and technology of decommissioning nuclear facilities

International Nuclear Information System (INIS)

1986-01-01

The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older nuclear facilities which are or soon will be retired from service. In response to increased international interest in decommissioning and to the needs of Member States, the IAEA's activities in this area have increased during the past few years and will be enhanced considerably in the future. A long range programme using an integrated systems approach covering all the technical, regulatory and safety steps associated with the decommissioning of nuclear facilities is being developed. The database resulting from this work is required so that Member States can decommission their nuclear facilities in a safe time and cost effective manner and the IAEA can effectively respond to requests for assistance. The report is a review of the current state of the art of the methodology and technology of decommissioning nuclear facilities including remote systems technology. This is the first report in the IAEA's expanded programme and was of benefit in outlining future activities. Certain aspects of the work reviewed in this report, such as the recycling of radioactive materials from decommissioning, will be examined in depth in future reports. The information presented should be useful to those responsible for or interested in planning or implementing the decommissioning of nuclear facilities

Personnel exposure estimates associated with nuclear fuel reprocessing waste

International Nuclear Information System (INIS)

Boone, F.W.; Rogers, B.W.

1983-08-01

The operation design of the Barnwell Nuclear Fuel Plant (BNFP) calls for shipment of its wastes to either a low-level waste disposal site or to a Federal repository. This study analyzes the probable radiation dose accrued to the personnel involved in handling waste packages from all identified waste streams of the BNFP from generation to reception at destination and including transportation. The shielding characteristics of the transport packages were derived by assuming packaging in existing or prototyped casks. Possible combinations of waste forms and packages for which the projected dose exceeded DOT or NRC regulations for transport of radioactive materials were rejected. Legal weight truck and legal weight rail transport modes were assumed. Potential ways for reducing overall personnel exposure are considered, concentrating on the particular streams with the largest dose contributions. The personnel exposure estimates were determined using a computer program specifically designed for this purpose. This program is described in Appendix A. 9 references, 3 figures, 19 tables

Improving human performance in maintenance personnel

International Nuclear Information System (INIS)

Gonzalez Anez, Francisco; Agueero Agueero, Jorge

2010-01-01

The continuous evolution and improvement of safety-related processes has included the analysis, design and development of training plans for the qualification of maintenance nuclear power plant personnel. In this respect, the international references in this area recommend the establishment of systematic qualification programmes for personnel performing functions or carrying out safety related tasks. Maintenance personnel qualification processes have improved significantly, and training plans have been designed and developed based on Systematic Approach to Training methodology to each job position. These improvements have been clearly reflected in recent training programmes with new training material and training facilities focused not only on developing technical knowledge and skills but also on improving attitudes and safety culture. The objectives of maintenance training facilities such as laboratories, mock-ups real an virtual, hydraulic loops, field simulators and other training material to be used in the maintenance training centre are to cover training necessities for initial and continuous qualification. Evidently, all these improvements made in the qualification of plant personnel should be extended to include supplemental personnel (external or contracted) performing safety-related tasks. The supplemental personnel constitute a very spread group, covering the performance of multiple activities entailing different levels of responsibility. Some of these activities are performed permanently at the plant, while others are occasional or sporadic. In order to establish qualification requirements for these supplemental workers, it is recommended to establish a rigorous analysis of job positions and tasks. The objective will be to identify the qualification requirements to assure competence and safety. (authors)

Remote handling technology for nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Sakai, Akira; Maekawa, Hiromichi; Ohmura, Yutaka

1997-01-01

Design and R and D on nuclear fuel cycle facilities has intended development of remote handling and maintenance technology since 1977. IHI has completed the design and construction of several facilities with remote handling systems for Power Reactor and Nuclear Fuel Development Corporation (PNC), Japan Atomic Energy Research Institute (JAERI), and Japan Nuclear Fuel Ltd. (JNFL). Based on the above experiences, IHI is now undertaking integration of specific technology and remote handling technology for application to new fields such as fusion reactor facilities, decommissioning of nuclear reactors, accelerator testing facilities, and robot simulator-aided remote operation systems in the future. (author)

Procedure for estimating facility decommissioning costs for non-fuel-cycle nuclear facilities

International Nuclear Information System (INIS)

Short, S.M.

1988-01-01

The Nuclear Regulatory Commission (NRC) staff has been reappraising its regulatory position relative to the decommissioning of nuclear facilities over the last several years. Approximately 30 reports covering the technology, safety, and costs of decommissioning reference nuclear facilities have been published during this period in support of this effort. One of these reports, Technology, Safety, and Costs of Decommissioning Reference Non-Fuel-Cycle Nuclear Facilities (NUREG/CR-1754), was published in 1981 and was felt by the NRC staff to be outdated. The Pacific Northwest Laboratory (PNL) was asked by the NRC staff to revise the information provided in this report to reflect the latest information on decommissioning technology and costs and publish the results as an addendum to the previous report. During the course of this study, the NRC staff also asked that PNL provide a simplified procedure for estimating decommissioning costs of non-fuel-cycle nuclear facilities. The purpose being to provide NRC staff with the means to easily generate their own estimate of decommissioning costs for a given facility for comparison against a licensee's submittal. This report presents the procedure developed for use by NRC staff

The physical protection of nuclear material and nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-06-01

The latest review (1993) of this document was of limited scope and resulted in changes to the text of INFCIRC/225/Rev.2 designed to make the categorization table in that document consistent with the categorization table contained in the Convention on Physical Protection of Nuclear Materials. Consequently, a comprehensive review of INFCIRC/225 has not been conducted since 1989. Consequently, a meeting of national experts was convened from 2-5 June 1998 and from 27-29 October 1998 for a thorough review of INFCIRC/225/Rev.3. The revised document reflects the recommendations of the national experts to improve the structure and clarity of the document and to take account of improved technology and current international and national practices. In particular, a chapter has been added which provides specific recommendations related to sabotage of nuclear facilities and nuclear material. As a result of this addition, the title has been changed to 'The Physical Protection of Nuclear Material and Nuclear Facilities'. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States.

The physical protection of nuclear material and nuclear facilities

International Nuclear Information System (INIS)

1999-06-01

The latest review (1993) of this document was of limited scope and resulted in changes to the text of INFCIRC/225/Rev.2 designed to make the categorization table in that document consistent with the categorization table contained in the Convention on Physical Protection of Nuclear Materials. Consequently, a comprehensive review of INFCIRC/225 has not been conducted since 1989. Consequently, a meeting of national experts was convened from 2-5 June 1998 and from 27-29 October 1998 for a thorough review of INFCIRC/225/Rev.3. The revised document reflects the recommendations of the national experts to improve the structure and clarity of the document and to take account of improved technology and current international and national practices. In particular, a chapter has been added which provides specific recommendations related to sabotage of nuclear facilities and nuclear material. As a result of this addition, the title has been changed to 'The Physical Protection of Nuclear Material and Nuclear Facilities'. The recommendations presented in this IAEA document reflect a broad consensus among Member States on the requirements which should be met by systems for the physical protection of nuclear materials and facilities. It is hoped that they will provide helpful guidance for Member States

International nuclear fuel cycle fact book

International Nuclear Information System (INIS)

1992-09-01

The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R ampersand D programs and key personnel on 23 countries, including the US, four multi-national agencies, and 21 nuclear societies. The Fact Book is organized as follows: National summaries-a section for each country which summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies-a section for each of the international agencies which has significant fuel cycle involvement and a listing of nuclear societies. Glossary-a list of abbreviations/acronyms of organizations, facilities, technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter presented from the perspective of the Fact Book user in the United States

Attitudes to risks in nuclear energy production; The personnel's view

Energy Technology Data Exchange (ETDEWEB)

Kivimaeki, M.; Kalimo, R. (Inst. of Occupational Health, Helsinki (Finland). Dept. of Psychology)

1993-01-01

The survey which is overviewed in the article investigated risk perception among nuclear power plant personnel. The study group, 428 employees from a nuclear power plant in Finland, completed a questionnaire which contained the same questions as those in previous surveys on the risk perception of lay persons and industrial workers. The main emphasis of the study was on perceived risk at work and subjective estimations of a serious nuclear accident.

New nuclear facilities and their analytical applications in China

International Nuclear Information System (INIS)

Zhang, Z.Y.; He, X.; Ma, Y.H.; Ding, Y.Y.; Chai, Z.F.

2014-01-01

Nuclear analytical techniques are a family of modern analytical methods that are based on nuclear reactions, nuclear effects, nuclear radiations, nuclear spectroscopy, nuclear parameters, and nuclear facilities. Because of their combined characteristics of sensitivity and selectivity, they are widely used in projects ranging from life sciences to deep-space exploration. In this review article, new nuclear facilities and their analytical applications in China are selectively reviewed, covering the following aspects: large scientific facilities, national demands, and key scientific issues with the emphasis on the new achievements. (orig.)

The state of improvement of security management setup in the Japan Atomic Power Company and improvement of facilities in its Tsuruga Nuclear Power Station

International Nuclear Information System (INIS)

1982-01-01

In connection with the series of accidents in the Tsuruga Nuclear Power Station of the Japan Atomic Power Company, the state of security management in JAPC and the safety of facilities in the Tsuruga Nuclear Power Station, which have resulted from improvement efforts, are described on the following items: security management setup - communication and reporting in emergency, the management of inspection and maintenance records, work control and supervision in repair, improvement, etc., functional authority and responsibility in maintenance management, operation management, radiation control, personnel education; improvement of facilities - feed water heaters, laundry waste-water filter room, radioactive waste treatment facility, general drainage, concentrated waste liquid storage tanks in newly-built waste treatment building, etc. (Mori, K.)

Research Facilities for the Future of Nuclear Energy

International Nuclear Information System (INIS)

Ait Abderrahim, H.

1996-01-01

The proceedings of the ENS Class 1 Topical Meeting on Research facilities for the Future of Nuclear Energy include contributions on large research facilities, designed for tests in the field of nuclear energy production. In particular, issues related to facilities supporting research and development programmes in connection to the operation of nuclear power plants as well as the development of new concepts in material testing, nuclear data measurement, code validation, fuel cycle, reprocessing, and waste disposal are discussed. The proceedings contain 63 papers

Nuclear Security Recommendations on Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225/Revision 5): Recommendations

International Nuclear Information System (INIS)

2011-01-01

This publication, Revision 5 of Physical Protection of Nuclear Material and Nuclear Facilities (INFCIRC/225), is intended to provide guidance to States and their competent authorities on how to develop or enhance, implement and maintain a physical protection regime for nuclear material and nuclear facilities, through the establishment or improvement of their capabilities to implement legislative and regulatory programmes. The recommendations presented in this publication reflect a broad consensus among IAEA Member States on the requirements which should be met for the physical protection of nuclear materials and nuclear facilities.

A Swedish nuclear fuel facility and public acceptance

Energy Technology Data Exchange (ETDEWEB)

Andersson, Bengt A [ABB Atom (Sweden)

1989-07-01

For more than ten years the ABB Atom Nuclear Fuel Facility has gained a lot of public attention in Sweden. When the nuclear power debate was coming up in the middle of the seventies, the Nuclear Fuel Facility very soon became a spectacular object. It provided a possibility to bring factual information about nuclear power to the public. Today that public interest still exists. For ABB Atom the Facility works as a tool of information activities in several ways, as a solid base for ABB Atom company presentations. but also as a very practical demonstration of the nuclear power technology to the public. This is valid especially to satisfy the local school demand for a real life object complementary to the theoretical nuclear technology education. Beyond the fact that the Nuclear Fuel Facility is a very effective fuel production plant, it is not too wrong to see it as an important resource for education as well as a tool for improved public relations.

A Swedish nuclear fuel facility and public acceptance

International Nuclear Information System (INIS)

Andersson, Bengt A.

1989-01-01

For more than ten years the ABB Atom Nuclear Fuel Facility has gained a lot of public attention in Sweden. When the nuclear power debate was coming up in the middle of the seventies, the Nuclear Fuel Facility very soon became a spectacular object. It provided a possibility to bring factual information about nuclear power to the public. Today that public interest still exists. For ABB Atom the Facility works as a tool of information activities in several ways, as a solid base for ABB Atom company presentations. but also as a very practical demonstration of the nuclear power technology to the public. This is valid especially to satisfy the local school demand for a real life object complementary to the theoretical nuclear technology education. Beyond the fact that the Nuclear Fuel Facility is a very effective fuel production plant, it is not too wrong to see it as an important resource for education as well as a tool for improved public relations

Facilities for the treatment of radioactively contaminated water in nuclear power plants

International Nuclear Information System (INIS)

1978-01-01

The regulation is to be applied to design, construction and operation of facilities for the treatment of contaminated water in stationary nuclear power plants with LWR and HTR. The facilities are to be designed, constructed and operated in such manner that (a) imcontrolled discharge of contaminated water is avoided (Paragraph 46 section 1, no. 1 Radiation Protection Regulation) (b) the activity discharged with water is as low as possible ( paragraph 46, section 2, no. 2 Radiation Protection Regulation) (c)contaminated water will not get into the ground, unless this is permitted by a license (paragraph 46 section 6 Radiation Protection Regulation) (d) the radiation exposure resulting from direct radiation, contamination and inhalation of the personnel working with the facility is as low as possible and, at the most, corresponds to the values fixed in the regulation (paragraph 28 section 1 Radiation Protection Regulation) or the values given in the discharge permit. The regulation is not to be applied to installations for reactor coolant or fuel pit clean-up. (orig./HP) [de

Nuclear safety and radiation protection report of the nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the Tricastin operational hot base facility (INB no. 157, Bollene, Vaucluse (FR)), a nuclear workshop for storage and maintenance and qualification operations on some EdF equipments. Then, the nuclear safety and radiation protection measures taken regarding the facility are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, if some, are reported as well as the effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facility is presented and sorted by type of waste, quantities and type of conditioning. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Quality management in nuclear facilities decommissioning

International Nuclear Information System (INIS)

Garonis, Omar H.

2002-01-01

Internationally, the decommissioning organizations of nuclear facilities carry out the decommissioning according to the safety requirements established for the regulatory bodies. Some of them perform their activities in compliance with a quality assurance system. This work establishes standardization through a Specifications Requirement Document, for the management system of the nuclear facilities decommissioning organizations. It integrates with aspects of the quality, environmental, occupational safety and health management systems, and also makes these aspects compatible with all the requirements of the nuclear industry recommended for the International Atomic Energy Agency (IAEA). (author)

Trend of development of robots for nuclear facilities

International Nuclear Information System (INIS)

Maki, Hideo; Sasaki, Masayoshi

1984-01-01

Robot technology becomes more and more important in the field of atomic energy industries. Hitachi Ltd. has energetically engaged in the development of the robot technology for nuclear facilities, recognizing these situations. The course of the development of robot technology and the robots for nuclear facilities is described. As the practical examples of the robots for nuclear facilities, there have been automatic fuel exchangers, the remotely operated automatic exchangers for control rod driving mechanism, automatic and semi-automatic ultrasonic flaw detectors and so on. As the robots for nuclear facilities under development, control rod driving mechanism disassembling and cleaning system, the volume reduction device for spent fuel channel boxes and control rods and others are reported. (Kako, I.)

Childhood leukaemia around Canadian nuclear facilities. Phase 2

International Nuclear Information System (INIS)

Clarke, E.A.; McLaughlin, J.; Anderson, T.W.

1991-06-01

Prompted by findings of increased occurrence of childhood leukaemia in the vicinity of some nuclear facilities in the United Kingdom, this study aimed to investigate whether the frequency of leukaemia among children born to mothers living near nuclear facilities in Ontario differed from the provincial average. The Ontario Cancer Registry was used to identify 1894 children aged 0 to 14 years who died from leukaemia between 1950 and 1987, and 1814 children who were diagnosed with leukaemia between 1964 and 1986. Residence at birth and death was obtained from birth and death certificates. Analyses were performed separately for nuclear research and development facilities; uranium mining, milling and refining facilities; and, nuclear generating stations; and for areas within the same county as the facility and 'nearby' - within a 25-km radius of the facility. Risk estimates were calculated as the ratio of the observed (O) number of events over the expected (E) number. In the vicinity of nuclear research and development facilities the rate of leukaemia was less than expected and within the bound of chance variation. In the areas around the uranium mining, milling and refining facilities and nuclear power plants leukaemia occurred slightly more frequently than expected, but due to small frequencies these differences may have arisen due to chance. Large differences between observed and expected rates were not detected around any of the Ontario facilities. This study was large enough to detect excess risks of the magnitude reported in the United Kingdom, but it was not large enough to discriminate between the observed relative risks and a chance finding. Levels of leukaemia detected near nuclear generating stations indicate the need for further investigation. (20 tabs., 15 figs., 32 refs.)

Realities of proximity facility siting

International Nuclear Information System (INIS)

DeMott, D.L.

1981-01-01

Numerous commercial nuclear power plant sites have 2 to 3 reactors located together, and a group of Facilities with capabilities for fuel fabrication, a nuclear reactor, a storage area for spent fuel, and a maintenance area for contaminated equipment and radioactive waste storage are being designed and constructed in the US. The proximity of these facilities to each other provides that the ordinary flow of materials remain within a limited area. Interactions between the various facilities include shared resources such as communication, fire protection, security, medical services, transportation, water, electrical, personnel, emergency planning, transport of hazardous material between facilities, and common safety and radiological requirements between facilities. This paper will explore the advantages and disadvantages of multiple facilities at one site. Problem areas are identified, and recommendations for planning and coordination are discussed

Experience with quality of training of personnel in start-up, operation and maintenance of nuclear power plants

International Nuclear Information System (INIS)

Ziman, V.; Alaxin, E.

1983-01-01

The theoretical education of personnel takes place in the branch training centre in Jaslovske Bohunice and in the concern training centre of the Slovak Power Plants. Practical training takes place in the Bohunice V-1 power plant. Selected specialists are trained in the training centre of the Novo Voronezh nuclear power plant, at the Paks nuclear plant and in the training centre of the Tusimice power plant. The recruitment, selection, schooling, practical training and placement of personnel and their assignment to posts is done in such a manner as to make sure that the complexly trained personnel is available 6 months to 3 years prior to the physical start-up of the nuclear power plant. The training of university graduates for the post of reactor operator takes 18 months or more. Trained personnel attend in-service training courses in form of complementary courses whose content includes such problems as the elimination of typified possible accidents, on the basis of the analysis of all failures which occurred in the previous period. The rising quality of personnel training at the Bohunice V-1 nuclear power plant is reflected in the decreasing number of failures caused by the human factor and in the increased availability of the power units. (M.D.)

Qualification tests for shift personnel in nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Fechner, J B [Bundesministerium des Innern, Bonn (Germany, F.R.)

1978-02-01

The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors.

Qualification tests for shift personnel in nuclear power plants

International Nuclear Information System (INIS)

Fechner, J.B.

1978-01-01

The selection of personnel for training as shift supervisors or reactor operators so far used to be made by a plant operator mainly on the basis of such criteria as examinations, diplomas and other documents verifying the educational background, the type of activity exercised, and professional success. In addition, there are the opininons of trainers and supervisors based on personal observation of future shift personnel on training for specific plants at a training center, at the manufacturer's, the operator's or in activities in the construction and commissioning of the respective nuclear power plant. In the course of this phase, which normally takes several years, supervisors asses not only the professional capabilities of a trainee, but also bis psychic and physical performance and aptitude, e.g., with respect to decision making, leadership qualifications or behavior unter stress. The advisability of introducing psychological aptitude tests was also studied. However, a decision was recently taken to defer such psychological tests for the time being. Yet, nuclear power plant operators are required to submit a statement to their responsible authorities about industrial medical checkups and qualification assessments by supervisors. (orig.) [de

Securing personnel in nuclear fuel cycle research and development in Japan

International Nuclear Information System (INIS)

Sekino, H.

1993-01-01

The PNC, a japanese governmental research and development organization, is concerned with research and development into building and operating advanced power reactors and R and D into the whole cycle of the nuclear fuel. PNC promotes international cooperation with the USA and European countries as well as technical cooperation with the private sectors in uranium enrichment, reprocessing and advanced reactor development. This report discusses the current situation and problems in securing PNC personnel, in securing 'loan' staff for PNC, and in personnel exchanges for technical transfer and international cooperation. 5 figs

Dismantling of nuclear facilities

International Nuclear Information System (INIS)

Tallec, M.; Kus, J.P.

2009-01-01

Nuclear facilities have a long estimable lifetime but necessarily limited in time. At the end of their operation period, basic nuclear installations are the object of cleansing operations and transformations that will lead to their definitive decommissioning and then to their dismantling. Because each facility is somewhere unique, cleansing and dismantling require specific techniques. The dismantlement consists in the disassembly and disposing off of big equipments, in the elimination of radioactivity in all rooms of the facility, in the demolition of buildings and eventually in the reconversion of all or part of the facility. This article describes these different steps: 1 - dismantling strategy: main de-construction guidelines, expected final state; 2 - industries and sites: cleansing and dismantling at the CEA, EDF's sites under de-construction; 3 - de-construction: main steps, definitive shutdown, preparation of dismantling, electromechanical dismantling, cleansing/decommissioning, demolition, dismantling taken into account at the design stage, management of polluted soils; 4 - waste management: dismantlement wastes, national policy of radioactive waste management, management of dismantlement wastes; 5 - mastery of risks: risk analysis, conformability of risk management with reference documents, main risks encountered at de-construction works; 6 - regulatory procedures; 7 - international overview; 8 - conclusion. (J.S.)

Methodology for analyzing risk at nuclear facilities

International Nuclear Information System (INIS)

Yoo, Hosik; Lee, Nayoung; Ham, Taekyu; Seo, Janghoon

2015-01-01

Highlights: • A new methodology for evaluating the risk at nuclear facilities was developed. • Five measures reflecting all factors that should be concerned to assess risk were developed. • The attributes on NMAC and nuclear security culture are included as attributes for analyzing. • The newly developed methodology can be used to evaluate risk of both existing facility and future nuclear system. - Abstract: A methodology for evaluating risks at nuclear facilities is developed in this work. A series of measures is drawn from the analysis of factors that determine risks. Five measures are created to evaluate risks at nuclear facilities. These include the legal and institutional framework, material control, physical protection system effectiveness, human resources, and consequences. Evaluation attributes are developed for each measure and specific values are given in order to calculate the risk value quantitatively. Questionnaires are drawn up on whether or not a state has properly established a legal and regulatory framework (based on international standards). These questionnaires can be a useful measure for comparing the status of the physical protection regime between two countries. Analyzing an insider threat is not an easy task and no methodology has been developed for this purpose. In this study, attributes that could quantitatively evaluate an insider threat, in the case of an unauthorized removal of nuclear materials, are developed by adopting the Nuclear Material Accounting & Control (NMAC) system. The effectiveness of a physical protection system, P(E), could be analyzed by calculating the probability of interruption, P(I), and the probability of neutralization, P(N). In this study, the Tool for Evaluating Security System (TESS) code developed by KINAC is used to calculate P(I) and P(N). Consequence is an important measure used to analyze risks at nuclear facilities. This measure comprises radiological, economic, and social damage. Social and

Safety study of fire protection for nuclear fuel cycle facility

International Nuclear Information System (INIS)

2013-01-01

Insufficiencies in the fire protection system of the nuclear reactor facilities were pointed out when the fire occurred due to the Niigata prefecture-Chuetsu-oki Earthquake in July, 2007. This prompted the revision of the fire protection safety examination guideline for nuclear reactors as well as commercial guidelines. The commercial guidelines have been endorsed by the regulatory body. Now commercial fire protection standards for nuclear facilities such as the design guideline and the management guideline for protecting fire in the Light Water Reactors (LWRs) are available, however, those to apply to the nuclear fuel cycle facilities such as mixed oxide fuel fabrication facility (MFFF) have not been established. For the improvement of fire protection system of the nuclear fuel cycle facilities, the development of a standard for the fire protection, corresponding to the commercial standard for LWRs were required. Thus, Japan Nuclear Energy Safety Organization (JNES) formulated a fire protection guidelines for nuclear fuel cycle facilities as a standard relevant to the fire protection of the nuclear fuel cycle facilities considering functions specific to the nuclear fuel cycle facilities. In formulating the guidelines, investigation has been conduced on the commercial guidelines for nuclear reactors in Japan and the standards relevant to the fire protection of nuclear facilities in USA and other countries as well as non-nuclear industrial fire protection standards. The guideline consists of two parts; Equipments and Management, as the commercial guidances of the nuclear reactor. In addition, the acquisition of fire evaluation data for a components (an electric cabinet, cable, oil etc.) targeted for spread of fire and the evaluation model of fire source were continued for the fire hazard analysis (FHA). (author)

Facilities inventory protection for nuclear facilities

International Nuclear Information System (INIS)

Schmitt, F.J.

1989-01-01

The fact that shut-down applications have been filed for nuclear power plants, suggests to have a scrutinizing look at the scopes of assessment and decision available to administrations and courts for the protection of facilities inventories relative to legal and constitutional requirements. The paper outlines the legal bases which need to be observed if purposeful calculation is to be ensured. Based on the different actual conditions and legal consequences, the author distinguishes between 1) the legal situation of facilities licenced already and 2) the legal situation of facilities under planning during the licencing stage. As indicated by the contents and restrictions of the pertinent provisions of the Atomic Energy Act and by the corresponding compensatory regulation, the object of the protection of facilities inventor in the legal position of the facility owner within the purview of the Atomic Energy Act, and the licensing proper. Art. 17 of the Atomic Energy Act indicates the legislators intent that, once issued, the licence will be the pivotal point for regulations aiming at protection and intervention. (orig./HSCH) [de

Personnel involved in nuclear standards development: 1980 directory

International Nuclear Information System (INIS)

Carr, S.J.

1980-03-01

The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development

Personnel involved in nuclear standards development: 1980 directory

Energy Technology Data Exchange (ETDEWEB)

Carr, S.J. (ed.)

1980-03-01

The development of nuclear standards is an active and necessary endeavor that is concerned with the safe, orderly, and economic development of nuclear potential. There are almost 4100 people from the teachnical community who are presently involved either in writing nuclear standards, including codes, or in the management and processing roles necessary for their approval and promulgation. This document identifies the current participation of each individual as member, chairman, cochairman (vice-chairman), or secretary of about 700 standards development committees and groups. The standards committees and groups are identified with the organizations that are responsible for the preparation, review, and maintenance of the standards and that provide support through supervisory committees and headquarters staff. This directory includes four major sections: personnel, employers, committees, and a Key-Word-in-Context (KWIC) Index of committee titles. It can also be used to identify the participation of employers as well as to recognize the contributions of individuals to the often interdisciplinary activity of standards development.

Childhood leukaemia around Canadian nuclear facilities. Phase 1

International Nuclear Information System (INIS)

Clarke, E.A.; McLaughlin, J.; Anderson, T.W.

1989-05-01

A ninefold excess risk of leukaemia, as observed in vicinity of the Sellafield facility, was not observed amongst children born to mothers residing in the areas around nuclear research facilities and uranium mining, milling and refining facilities in Ontario. In the vicinity of nuclear research facilities, the rate of leukaemia was, in fact, less than expected. In the areas around the uranium mining, milling and refining facilities; leukaemia occurred slightly more frequently than expected; however, due to small frequencies these results may have risen by chance. A slightly greater than expected occurrence of leukaemia was also detected, which may well have been due to chance, in an exploratory study of the areas around nuclear power generating stations in Ontario

Considerations about the licensing process of special nuclear industrial facilities

Energy Technology Data Exchange (ETDEWEB)

Talarico, M.A., E-mail: talaricomarco@hotmail.com [Marinha do Brasil, Rio de Janeiro, RJ (Brazil). Coordenacao do Porgrama de Submarino com Propulsao Nuclear; Melo, P.F. Frutuoso e [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear

2015-07-01

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

Considerations about the licensing process of special nuclear industrial facilities

International Nuclear Information System (INIS)

Talarico, M.A.; Melo, P.F. Frutuoso e

2015-01-01

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

International nuclear waste management fact book

International Nuclear Information System (INIS)

Abrahms, C.W.; Patridge, M.D.; Widrig, J.E.

1995-11-01

The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US

International nuclear waste management fact book

Energy Technology Data Exchange (ETDEWEB)

Abrahms, C W; Patridge, M D; Widrig, J E

1995-11-01

The International Nuclear Waste Management Fact Book has been compiled to provide current data on fuel cycle and waste management facilities, R and D programs, and key personnel in 24 countries, including the US; four multinational agencies; and 20 nuclear societies. This document, which is in its second year of publication supersedes the previously issued International Nuclear Fuel Cycle Fact Book (PNL-3594), which appeared annually for 12 years. The content has been updated to reflect current information. The Fact Book is organized as follows: National summaries--a section for each country that summarizes nuclear policy, describes organizational relationships, and provides addresses and names of key personnel and information on facilities. International agencies--a section for each of the international agencies that has significant fuel cycle involvement and a list of nuclear societies. Glossary--a list of abbreviations/acronyms of organizations, facilities, and technical and other terms. The national summaries, in addition to the data described above, feature a small map for each country and some general information that is presented from the perspective of the Fact Book user in the US.

On exposure of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1988

International Nuclear Information System (INIS)

1989-01-01

The Law for Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1988 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the exposure of workers was below the permissible exposure dose in 1988 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of Japan Atomic Energy Research Institute and Power Reactor and Nuclear Fuel Development Corporation. (N.K.)

Decommissioning nuclear facilities

International Nuclear Information System (INIS)

Harmon, K.M.; Jenkins, C.E.; Waite, D.A.; Brooksbank, R.E.; Lunis, B.C.; Nemec, J.F.

1976-01-01

This paper describes the currently accepted alternatives for decommissioning retired light water reactor fuel cycle facilities and the current state of decommissioning technology. Three alternatives are recognized: Protective Storage; Entombment; and Dismantling. Application of these alternatives to the following types of facilities is briefly described: light water reactors; fuel reprocessing plants, and mixed oxide fuel fabrication plants. Brief descriptions are given of decommissioning operations and results at a number of sites, and recent studies of the future decommissioning of prototype fuel cycle facilities are reviewed. An overview is provided of the types of operations performed and tools used in common decontamination and decommissioning techniques and needs for improved technology are suggested. Planning for decommissioning a nuclear facility is dependent upon the maximum permitted levels of residual radioactive contamination. Proposed guides and recently developed methodology for development of site release criteria are reviewed. 21 fig, 32 references

Human factor in the process of nuclear power development

International Nuclear Information System (INIS)

Enenkl, V.

The building up of nuclear power requires the training not only of personnel but of the whole population as well. Professional workers in nuclear power facilities production and personnel operating the equipment of nuclear power plants must be on a high technical and managerial level. The important quality of such personnel is their reliability and responsibility. The human factor influences the level, quality and thereby also the service-life of the machines and equipment and their operation. The improvement of the quality of work in nuclear power production depends on upgrading the scientific and technical level of workers and personnel, their training, in-service education and the raising of the social standing. (B.H.)

Some technical aspects of the nuclear material accounting and control at nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Miller, O.A.; Babaev, N.S.; Gryazev, V.M.; Gadzhiev, G.I.; Gabeskiriya, V.Ya.

1977-01-01

The possibilities of nuclear material accounting and control are discussed at nuclear facilities of fuel cycle (WWER-type reactor, fuel fabrication plant, reprocessing plant and uranium enrichment facility) and zero energy fast reactor facility. It is shown that for nuclear material control the main method is the accounting with the application isotopic correlations at the reprocessing plant and enrichment facility. Possibilities and limitations of the application of destructive and non-destructive methods are discussed for nuclear material determinations at fuel facilities and their role in the accounting and safeguards systems as well as possibilities of the application of neutron method at a zero energy fast reactor facility [ru

Criteria, standards and policies regarding decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Detilleux, E.; Lennemann, W.L.

1977-01-01

At the end of this century, there will probably be around 2500 operating nuclear power reactors, along with all the other nuclear fuel cycle facilities supporting their operation. Eventually these facilities, one by one, will be shut down and it will be necessary to dispose of them as with any redundant industrial facility or plant. Some parts of a nuclear fuel cycle facility can be dismantled by conventional methods, but those parts which have become contaminated with radioactive nuclear products or induced radioactivity must be subject to rigid controls and restrictions and handled by special dismantling and disposal procedures. In many cases, the resulting quantity of radioactive waste is likely to be relatively large and dismantling quite costly. Decommissioning nuclear facilities is a multifaceted problem involving planners, design engineers, operators, waste managers and regulatory authorities. Preparation for decommissioning should begin as early as site selection and plant design. The corner stone for the preparation of a decommissioning programme is the definition of its extent, meeting the requirements for public and environmental protection during the period that the radioactive material is of concern. The paper discusses the decontamination and decommissioning experience at the Eurochemic fuel reprocessing plant, the implications and the knowledge gained from this experience. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who should jointly make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities

Storage facilities of spent nuclear fuel in dry for Mexican nuclear facilities; Instalaciones de almacenamiento de combustible nuclear gastado en seco para instalaciones nucleares mexicanas

Energy Technology Data Exchange (ETDEWEB)

Salmeron V, J. A.; Camargo C, R.; Nunez C, A.; Mendoza F, J. E.; Sanchez J, J., E-mail: juan.salmeron@cnsns.gob.mx [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

2013-10-15

In this article the relevant aspects of the spent fuel storage and the questions that should be taken in consideration for the possible future facilities of this type in the country are approached. A brief description is proposed about the characteristics of the storage systems in dry, the incorporate regulations to the present Nuclear Regulator Standard, the planning process of an installation, besides the approaches considered once resolved the use of these systems; as the modifications to the system, the authorization periods for the storage, the type of materials to store and the consequent environmental impact to their installation. At the present time the Comision Nacional de Seguridad Nuclear y Salvaguardias (CNSNS) considers the possible generation of two authorization types for these facilities: Specific, directed to establish a new nuclear installation with the authorization of receiving, to transfer and to possess spent fuel and other materials for their storage; and General, focused to those holders that have an operation license of a reactor that allows them the storage of the nuclear fuel and other materials that they possess. Both authorizations should be valued according to the necessities that are presented. In general, this installation type represents a viable solution for the administration of the spent fuel and other materials that require of a temporary solution previous to its final disposal. Its use in the nuclear industry has been increased in the last years demonstrating to be appropriate and feasible without having a significant impact to the health, public safety and the environment. Mexico has two main nuclear facilities, the nuclear power plant of Laguna Verde of the Comision Federal de Electricidad (CFE) and the facilities of the TRIGA Reactor of the Instituto Nacional de Investigaciones Nucleares (ININ) that will require in a future to use this type of disposition installation of the spent fuel and generated wastes. (Author)

Integrated engineering system for nuclear facilities building

International Nuclear Information System (INIS)

Tomura, H.; Miyamoto, A.; Futami, F.; Yasuda, S.; Ohtomo, T.

1995-01-01

In the construction of buildings for nuclear facilities in Japan, construction companies are generally in charge of the building engineering work, coordinating with plant engineering. An integrated system for buildings (PROMOTE: PROductive MOdeling system for Total nuclear Engineering) described here is a building engineering system including the entire life cycle of buildings for nuclear facilities. A Three-dimensional (3D) building model (PRO-model) is to be in the core of the system (PROMOTE). Data sharing in the PROMOTE is also done with plant engineering systems. By providing these basic technical foundations, PROMOTE is oriented toward offering rational, highquality engineering for the projects. The aim of the system is to provide a technical foundation in building engineering. This paper discusses the characteristics of buildings for nuclear facilities and the outline of the PROMOTE. (author)

Significant incidents in nuclear fuel cycle facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-03-01

In contrast to nuclear power plants, events in nuclear fuel cycle facilities are not well documented. The INES database covers all the nuclear fuel cycle facilities; however, it was developed in the early 1990s and does not contain information on events prior to that. The purpose of the present report is to collect significant events and analyze them in order to give a safety related overview of nuclear fuel cycle facilities. Significant incidents were selected using the following criteria: release of radioactive material or exposure to radiation; degradation of items important to safety; and deficiencies in design, quality assurance, etc. which include criticality incidents, fire, explosion, radioactive release and contamination. This report includes an explanation, where possible, of root causes, lessons learned and action taken. 4 refs, 4 tabs.

Significant incidents in nuclear fuel cycle facilities

International Nuclear Information System (INIS)

1996-03-01

In contrast to nuclear power plants, events in nuclear fuel cycle facilities are not well documented. The INES database covers all the nuclear fuel cycle facilities; however, it was developed in the early 1990s and does not contain information on events prior to that. The purpose of the present report is to collect significant events and analyze them in order to give a safety related overview of nuclear fuel cycle facilities. Significant incidents were selected using the following criteria: release of radioactive material or exposure to radiation; degradation of items important to safety; and deficiencies in design, quality assurance, etc. which include criticality incidents, fire, explosion, radioactive release and contamination. This report includes an explanation, where possible, of root causes, lessons learned and action taken. 4 refs, 4 tabs

Nuclear material inventory estimation in a nuclear fuel reprocessing facility

International Nuclear Information System (INIS)

Bennett, J.E.; Beyerlein, A.L.

1981-01-01

A new approach in the application of modern system identification and estimation techniques is proposed to help nuclear reprocessing facilities meet the nuclear accountability requirement proposed by the International Atomic Energy Agency. The proposed identification and estimation method considers the material inventory in a portion of the chemical separations area of a reprocessing facility. The method addresses the nonlinear aspects of the problem, the time delay through the separation facility, and the lack of measurement access. The method utilizes only input-output measured data and knowledge of the uncertainties associated with the process and measured data. 14 refs

The development of mobile robot for security application and nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Kim, B. S.; Lee, Y. B.; Choi, Y. S.; Seo, Y. C.; Park, Y. M

1999-12-01

The use of a mobile robot system in nuclear radioactive environments has the advantage of watching and inspecting the NPP safety-related equipment systematically and repairing damaged parts efficiently, thereby enhancing the safe operations of NPPs as well as reducing significantly personnel's dose rate to radioactive environment. Key technology achieved through the development of such robotic system can be used for security application and can offer new approaches to many of the tasks faced to the industry as well. The mobile robot system was composed of a mobile subsystem, a manipulator subsystem, a control subsystem, and a sensor subsystem to use in security application and nuclear radioactive environments. The mobile subsystem was adopted to synchro-drive method to improve the mobility of it. And the manipulator subsystem was developed to minimize the weight and easy to control at remote site. Finally, we developed the USB-based robot control system considering the expandability and modularity. The developed mobile robot for inspection and security was experimented for the collision avoidance and autonomous algorithm, and then it was confirmed that the mobile robot was very effective to the security application and inspection of nuclear facilities. (author)

The development of mobile robot for security application and nuclear facilities

International Nuclear Information System (INIS)

Kim, B. S.; Lee, Y. B.; Choi, Y. S.; Seo, Y. C.; Park, Y. M.

1999-12-01

The use of a mobile robot system in nuclear radioactive environments has the advantage of watching and inspecting the NPP safety-related equipment systematically and repairing damaged parts efficiently, thereby enhancing the safe operations of NPPs as well as reducing significantly personnel's dose rate to radioactive environment. Key technology achieved through the development of such robotic system can be used for security application and can offer new approaches to many of the tasks faced to the industry as well. The mobile robot system was composed of a mobile subsystem, a manipulator subsystem, a control subsystem, and a sensor subsystem to use in security application and nuclear radioactive environments. The mobile subsystem was adopted to synchro-drive method to improve the mobility of it. And the manipulator subsystem was developed to minimize the weight and easy to control at remote site. Finally, we developed the USB-based robot control system considering the expandability and modularity. The developed mobile robot for inspection and security was experimented for the collision avoidance and autonomous algorithm, and then it was confirmed that the mobile robot was very effective to the security application and inspection of nuclear facilities. (author)

Introduction to nuclear facilities engineering

International Nuclear Information System (INIS)

Sapy, Georges

2012-06-01

Engineering, or 'engineer's art', aims at transforming simple principle schemes into operational facilities often complex especially when they concern the nuclear industry. This transformation requires various knowledge and skills: in nuclear sciences and technologies (nuclear physics, neutronics, thermal-hydraulics, material properties, radiation protection..), as well as in non-nuclear sciences and technologies (civil engineering, mechanics, electricity, computer sciences, instrumentation and control..), and in the regulatory, legal, contractual and financial domains. This book explains how this huge body of knowledge and skills must be organized and coordinated to create a reliable, exploitable, available, profitable and long-lasting facility, together with respecting extremely high safety, quality, and environmental impact requirements. Each aspect of the problem is approached through the commented presentation of nuclear engineering macro-processes: legal procedures and administrative authorizations, nuclear safety/radiation protection/security approach, design and detailed studies, purchase of equipments, on-site construction, bringing into operation, financing, legal, contractual and logistic aspects, all under the global control of a project management. The 'hyper-complexness' of such an approach leads to hard points and unexpected events. The author identifies the most common ones and proposes some possible solutions to avoid, mitigate or deal with them. In a more general way, he proposes some thoughts about the performance factors of a nuclear engineering process

Hematite nuclear fuel cycle facility decommissioning

International Nuclear Information System (INIS)

Hayes, K.

2004-01-01

Westinghouse Electric Company LLC ('Westinghouse') acquired a nuclear fuel processing plant at Hematite, Missouri ('Hematite', the 'Facility', or the 'Plant') in April 2000. The plant has subsequently been closed, and its operations have been relocated to a newer, larger facility. Westinghouse has announced plans to complete its clean-up, decommissioning, and license retirement in a safe, socially responsible, and environmentally sound manner as required by internal policies, as well as those of its parent company, British Nuclear Fuels plc. ('BNFL'). Preliminary investigations have revealed the presence of environmental contamination in various areas of the facility and grounds, including both radioactive contamination and various other substances related to the nuclear fuel processing operations. The disparity in regulatory requirements for radiological and nonradiological contaminants, the variety of historic and recent operations, and the number of previous owners working under various contractual arrangements for both governmental and private concerns has resulted in a complex project. This paper discusses Westinghouse's efforts to develop and implement a comprehensive decontamination and decommissioning (D and D) strategy for the facility and grounds. (author)

Policy on the decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1988-08-01

This Regulatory Policy Statement describes the policy of the Atomic Energy Control Board (AECB) on the decommissioning of those facilities defined as nuclear facilities in the Atomic Energy Control (AEC) Regulations. It is intended as a formal statement, primarily for the information of licensees, or potential licensees, of the regulatory process and requirements generally applicable to the decommissioning of nuclear facilities licensed and regulated by the AECB pursuant to the authority of the AEC Act and Regulations

The State Surveillance over Nuclear Safety of Nuclear Facilities Act No. 28/1984

International Nuclear Information System (INIS)

1995-01-01

The Act lays down responsibilities of the Czechoslovak Atomic Energy Commission in the field of state surveillance over nuclear safety of nuclear facilities; determines the responsibilities of nuclear safety inspectors in their inspection activities; specifies duties of bodies and corporations responsible for nuclear safety of nuclear facilities; stipulates the obligation to set up emergency plans; and specifies penalties imposed on corporations and individuals for noncompliance with nuclear safety provisions. The Act entered into force on 4 April 1984. (J.B.)

Decommissioning of nuclear facilities: Feasibility, needs and costs

International Nuclear Information System (INIS)

DeLaney, E.G.; Mickelson, J.R.

1985-01-01

The Nuclear Energy Agency's Working Group on Decommissioning is preparing a study entitled ''Decommissioning of Nuclear Facilities: Feasibility, Needs and Costs.'' The study addresses the economics, technical feasibility and waste management aspects of decommissioning larger commercial reactors and nuclear support facilities. Experience on decommissioning small reactors and fuel cycle facilities shows that current technology is generally adequate. Several major projects that are either underway or planned will demonstrate decommissioning of the larger and more complex facilities. This experience will provide a framework for planning and engineering the decommissioning of the larger commercial reactors and fuel cycle facilities. Several areas of technology development are desired for worker productivity improvement, occupational exposure reduction, and waste volume reduction. In order to assess and plan for the decommissioning of large commercial nuclear facilities, projections have been made of the capacity of these facilities that may be decommissioned in the future and the radioactive waste that would be produced from the decommissioning of these facilities. These projections through the year 2025 are based on current data and the OECD reactor capacity forecast through the year 2000. A 25-year operating lifetime for electrical power generation was assumed. The possibilities of plant lifetime extension and the deferral of plant dismantlement make this projection very conservative

The regulations concerning refining business of nuclear source material and nuclear fuel materials

International Nuclear Information System (INIS)

1987-01-01

Regulations specified here cover application for designation of undertakings of refining (spallation and eaching filtration facilities, thickening facilities, refining facilities, nuclear material substances or nuclear fuel substances storage facilities, waste disposal facilities, etc.), application for permission for alteration (business management plan, procurement plan, fund raising plan, etc.), application for approval of merger (procedure, conditions, reason and date of merger, etc.), submission of report on alteration (location, structure, arrangements processes and construction plan for refining facilities, etc.), revocation of designation, rules for records, rules for safety (personnel, organization, safety training for employees, handling of important apparatus and tools, monitoring and removal of comtaminants, management of radioactivity measuring devices, inspection and testing, acceptance, transport and storage of nuclear material and fuel, etc.), measures for emergency, submission of report on abolition of an undertaking, submission of report on disorganization, measures required in the wake of revocation of designation, submission of information report (exposure to radioactive rays, stolen or missing nuclear material or nuclear fuel, unusual leak of nuclear fuel or material contaminated with nuclear fuel), etc. (Nogami, K.)

Decommissioning of nuclear fuel cycle facilities. Safety guide

International Nuclear Information System (INIS)

2001-01-01

The objective of this Safety Guide is to provide guidance to regulatory bodies and operating organizations on planning and provision for the safe management of the decommissioning of non-reactor nuclear fuel cycle facilities. While the basic safety considerations for the decommissioning of nuclear fuel cycle facilities are similar to those for nuclear power plants, there are important differences, notably in the design and operating parameters for the facilities, the type of radioactive material and the support systems available. It is the objective of this Safety Guide to provide guidance for the shutdown and eventual decommissioning of such facilities, their individual characteristics being taken into account

Childhood leukemia around five nuclear facilities in Canada

International Nuclear Information System (INIS)

Elaguppillai, V.

1992-05-01

As a result of public concern over the incidence of leukemia around the Sellafield nuclear fuel reprocessing plant, the Canadian Atomic Energy Control Board commissioned a study to test for similar clustering around licensed nuclear facilities in Ontario. In this study the incidence and mortality of leukemia among children up to the age of 14 years born within a radius of about 25 km from five different types of facilities were compared to the provincial average. The facilities considered were the Pickering Nuclear Generating Station, the Bruce Nuclear Power Development, the uranium conversion facility at Port Hope, the uranium mine and mill facilities in Elliot Lake, and the Chalk River Laboratories. The ratio of observed to expected childhood leukemias was around unity at the 95 percent confidence level, indicating that the occurrence of the disease is not significantly different from the provincial average. The sample size is not large enough to distinguish between a change occurrence and a true excess or deficit. (table)

Training in radiation protection for personnels in nuclear power plants

International Nuclear Information System (INIS)

Constancis, J.; Gauthier, A.

1980-01-01

For more than 10 years, in order to meet the wishes of their members, the A.P.A.V.E. associations have organised training courses in personnel radiation protection, as a consequence of their activities in the inspection of ionizing radiation sources in industrial or medical environments. Because of their experience, the A.P.A.V.E. associations were asked to provide for the training of the film personnel likely to work in nuclear power stations, in the field of occupational radiation protection. For the last 3 years, nearly 5,000 people have attended these training sessions. The present report describes the approach, draws the first conclusions and state some considerations on this subject [fr

Standard Specification for Nuclear Facility Transient Worker Records

CERN Document Server

American Society for Testing and Materials. Philadelphia

1995-01-01

1.1 This specification covers the required content and provides retention requirements for records needed for in-processing of nuclear facility transient workers. 1.2 This specification applies to records to be used for in-processing only. 1.3 This specification is not intended to cover specific skills records (such as equipment operating licenses, ASME inspection qualifications, or welding certifications). 1.4 This specification does not reduce any regulatory requirement for records retention at a licensed nuclear facility. Note 1—Nuclear facilities operated by the U.S. Department of Energy (DOE) are not licensed by the U.S. Nuclear Regulatory Commission (NRC), nor are other nuclear facilities that may come under the control of the U.S. Department of Defense (DOD) or individual agreement states. The references in this specification to licensee, the U.S. NRC Regulatory Guides, and Title 10 of the U.S. Code of Federal Regulations are to imply appropriate alternative nomenclature with respect to DOE, DOD...

Space Nuclear Thermal Propulsion (SNTP) Air Force facility

Science.gov (United States)

Beck, David F.

The Space Nuclear Thermal Propulsion (SNTP) Program is an initiative within the US Air Force to acquire and validate advanced technologies that could be used to sustain superior capabilities in the area or space nuclear propulsion. The SNTP Program has a specific objective of demonstrating the feasibility of the particle bed reactor (PBR) concept. The term PIPET refers to a project within the SNTP Program responsible for the design, development, construction, and operation of a test reactor facility, including all support systems, that is intended to resolve program technology issues and test goals. A nuclear test facility has been designed that meets SNTP Facility requirements. The design approach taken to meet SNTP requirements has resulted in a nuclear test facility that should encompass a wide range of nuclear thermal propulsion (NTP) test requirements that may be generated within other programs. The SNTP PIPET project is actively working with DOE and NASA to assess this possibility.

Gas separation techniques in nuclear facilities

International Nuclear Information System (INIS)

Hioki, Hideaki; Morisue, Tetsuo; Ohno, Masayoshi

1983-01-01

The literatures concerning the gas separation techniques which are applied to the waste gases generated from nuclear power plants and nuclear fuel reprocessing plants, uranium enrichment and the instrumentation of nuclear facilities are reviewed. The gas permeability and gas separation performance of membranes are discussed in terms of rare gas separation. The investigation into the change of the gas permeability and mechanical properties of membranes with exposure to radiation is reported. The theoretical investigation of the separating cells used for the separation of rare gas and the development of various separating cells are described, and the theoretical and experimental investigations concerning rare gas separation using cascades are described. The application of membrane method to nuclear facilities is explained showing the examples of uranium enrichment, the treatment of waste gases from nuclear reactor buildings and nuclear fuel reprocessing plants, the monitoring of low level β-emitters in stacks, the detection of failed fuels and the detection of water leak in fast breeder reactors. (Yoshitake, I.)

Development of neutron personnel monitoring system based on CR-39 solid state nuclear track detector

International Nuclear Information System (INIS)

Massand, O.P.; Kundu, H.K.; Marathe, P.K.; Supe, S.J.

1990-01-01

Personnel neutron monitoring aims at providing a method to evaluate the magnitude of the detrimental effects on the personnel exposed to neutrons. Neutron monitoring is done for a small though growing number of personnel working with neutrons in a wide range of situations. Over the years, many solid state nuclear track detectors (SSNTD) have been tried for neutron personnel monitoring. CR-39 SSNTD is a proton sensitive polymer and offers a lot of promise for neutron personnel monitoring due to its high sensitivity and lower energy threshold for neutron detection. This report presents the mechanism of track formation in this polymer, the development of this neutron personnel monitoring system in our laboratory, its various characteristics and its promise as a routine personnel neutron monitor. (author). 1 tab., 7 figs

Summary of personnel doses and discharge of radioactivity at Swedish nuclear power plants 1971-1975

International Nuclear Information System (INIS)

Malmqvist, L.; Persson, Aa.

1977-01-01

The report is a summary of personnel doses and activity discharges from Swedish nuclear power plants during the first five years of electric power production by nuclear plants. The personnel doses for the Sweedish plants are lower than the corresponding values for American plants. The highest Swedish value is o,13 manrem per MWE and year. The discharge of radioactivity to the atmosphere from the Swedish plants has been for below the maximum permissible limits. The discharge of radioactivity to the water recipients was less than 1 % of what is permissible

Studying on the problem of quality, ability and adult education of the management personnel of nuclear power library and information

International Nuclear Information System (INIS)

Ma Hua

2012-01-01

Studying on how to improve the quality and ability of the nuclear power library and information management personnel has an important role in the promotion of nuclear power industry and the development of nuclear power library and information. By the view of the perspective of the development of nuclear power industry and the improvement of quality and level of nuclear power library and information. The library and information management personnel of nuclear power in the new period should have seven types of basic quality and ability. Vigorously developing adult education is an effective way to comprehensively improve the quality and ability of the nuclear power library and information management personnel. Doing well in adult education must grasp some key issues: put ideological and moral education first, regard pertinence and effectiveness and innovate ways and methods of education. (author)

Estimating Fire Risks at Industrial Nuclear Facilities

International Nuclear Information System (INIS)

Coutts, D.A.

1999-01-01

The Savannah River Site (SRS) has a wide variety of nuclear production facilities that include chemical processing facilities, machine shops, production reactors, and laboratories. Current safety documentation must be maintained for the nuclear facilities at SRS. Fire Risk Analyses (FRAs) are used to support the safety documentation basis. These FRAs present the frequency that specified radiological and chemical consequences will be exceeded. The consequence values are based on mechanistic models assuming specific fire protection features fail to function as designed

Westinghouse Savannah River Company (WSRC) approach to nuclear facility maintenance

International Nuclear Information System (INIS)

Harrison, D.W.

1991-01-01

The Savannah River Site (SRS) in South Carolina is a 300+ square mile facility owned by the US Department of Energy (DOE) and operated by Westinghouse Savannah River Company (WSRC), the prime contractor; Bechtel Savannah River, Incorporated (BSRI) is a major subcontractor. The site has used all of the five nuclear reactors and it has the necessary nuclear materials processing facilities, as well as waste management and research facilities. The site has produced materials for the US nuclear arsenal and various isotopes for use in space research and nuclear medicine for more than 30 years. In 1989, WSRC took over as prime contractor, replacing E.I. du Pont de Nemours and Company. At this time, a concentrated effort began to more closely align the operating standards of this site with those accepted by the commercial nuclear industry of the United States. Generally, this meant acceptance of standards of the Institute of Nuclear Power Operations (INPO) for nuclear-related facilities at the site. The subject of this paper is maintenance of nuclear facilities and, therefore, excludes discussion of the maintenance of non-nuclear facilities and equipment

On exposure management of workers in nuclear reactor facilities for test and in nuclear reactor facilities in research and development stage in fiscal 1993

International Nuclear Information System (INIS)

1994-01-01

The Law of Regulation on Nuclear Reactor requires the operators of nuclear reactors that the exposure dose of workers engaged in work for nuclear reactors should not exceed the limits specified in official notices that are issued based on the Law. The present article summarizes the contents of the Report on Radiation Management in 1993 submitted by the operators of nuclear reactor facilities for test and those of nuclear reactor facilities in research and development stage based on the Law, and the Report on Management of Exposure Dose of Workers submitted by them based on administrative notices. The reports demonstrate that the the exposure of workers was below the permissible exposure dose in 1993 in all nuclear reactor facilities. The article presents data on the distribution of exposure dose among workers in all facilities with a nuclear reactor for test, and data on personal exposure of employees and non-employees and overall exposure of all workers in the facilities of JAERI and PNC. (J.P.N.)

Importance of tests in nuclear facilities

International Nuclear Information System (INIS)

Guillemard, B.

1985-10-01

In nuclear facilities, safety related systems and equipments are subject, along their whole service-life, to numerous tests. This paper analyses the role of tests in the successive stages of design, construction, exploitation of a nuclear facility. It examines several aspects of test quality control: definition of needs, test planning, intrinsic quality of each test, control of interfaces (test are both the end and the starting point of many actions concerned by quality) and the application [fr

The law for the regulations of nuclear source materials, nuclear fuel materials and reactors

International Nuclear Information System (INIS)

1987-01-01

General provisions specify the purpose of the Law and definitions of terms used in it. Provisions relating to control of business management for refining cover designation of business operation, requirements for designation, permission and report of alteration, report of commencement of business operation, revocation of designation, recording, and measures for wastes. Provisions relating to control of business management for processing cover permission of operation, requirements for permission, approval of design and construction plan, inspection of facilities, report of commencement of business management, measures for maintenance, suspension of use of facilities, responsible personnel for handling nuclear fuel, and permit, obligations, etc. of responsible personnel for handing nuclear fuel. Provisions relating to control of construction and operation of nuclear reactor cover permission of construction, permission concerning nuclear reactor mounted on foreign nuclear powered ships, requirements for permission, etc. Other articles stipulate provisions relating to control of business management for reprocessing, use of nuclear fuel substances, use of materials and substances covered by international regulations, designation of inspection organizations, and other rules. (Nogami, K.)

Waste management considerations in nuclear facility decommissioning

International Nuclear Information System (INIS)

Elder, H.K.; Murphy, E.S.

1981-01-01

Decommissioning of nuclear facilities involves the management of significant quantities of radioactive waste. This paper summarizes information on volumes of waste requiring disposal and waste management costs developed in a series of decommissioning studies performed for the U.S. Nuclear Regulatory Commission by the Pacific Northwest Laboratory. These studies indicate that waste management is an important cost factor in the decommissioning of nuclear facilities. Alternatives for managing decommissioning wastes are defined and recommendations are made for improvements in waste management practices

Evaluation of the secondary radiation impact on personnel during the dismantling of contaminated nuclear equipment

Directory of Open Access Journals (Sweden)

Stankunas Gediminas

2013-01-01

Full Text Available The article contains a numerical analysis of the secondary radiation contribution to the total radiation affecting the operational personnel during the dismantling activities of the contaminated equipment at a nuclear power plant. This study considers a widely applicable Monte Carlo particle transport code MCNPX and real Ignalina nuclear power plant records. A simplified albedo method is investigated in order to analyze the selected geometrical design cases. Additionally, the impact of the secondary radiation on the personnel dose was analyzed. The numerical MCNPX simulation allowed ascertaining the optimal distance between the source and the wall for the working personnel in closed rooms with contaminated equipment. The developed dose rate maps of the secondary radiation showed cross-sectional distribution of the dose rate inside the enclosed area.

Design aspects of radiological safety in nuclear facilities

International Nuclear Information System (INIS)

Patkulkar, D.S.; Purohit, R.G.; Tripathi, R.M.

2014-01-01

In order to keep operational performance of a nuclear facility high and to keep occupational and public exposure ALARA, radiological safety provisions must be reviewed at the time of facility design. Deficiency in design culminates in deteriorated system performance and non adherence to safety standards and could sometimes result in radiological incident. Important radiological aspects relevant to safety were compiled based on operating experiences, design deficiencies brought out from past nuclear incidents, experience gained during maintenance, participation in design review of upcoming nuclear facilities and radiological emergency preparedness

Sample registration software for process automation in the Neutron Activation Analysis (NAA) Facility in Malaysia nuclear agency

Energy Technology Data Exchange (ETDEWEB)

Rahman, Nur Aira Abd, E-mail: nur-aira@nuclearmalaysia.gov.my; Yussup, Nolida; Ibrahim, Maslina Bt. Mohd; Mokhtar, Mukhlis B.; Soh Shaari, Syirrazie Bin Che; Azman, Azraf B. [Technical Support Division, Malaysian Nuclear Agency, 43000, Kajang, Selangor (Malaysia); Salim, Nazaratul Ashifa Bt. Abdullah [Division of Waste and Environmental Technology, Malaysian Nuclear Agency, 43000, Kajang, Selangor (Malaysia); Ismail, Nadiah Binti [Fakulti Kejuruteraan Elektrik, UiTM Pulau Pinang, 13500 Permatang Pauh, Pulau Pinang (Malaysia)

2015-04-29

Neutron Activation Analysis (NAA) had been established in Nuclear Malaysia since 1980s. Most of the procedures established were done manually including sample registration. The samples were recorded manually in a logbook and given ID number. Then all samples, standards, SRM and blank were recorded on the irradiation vial and several forms prior to irradiation. These manual procedures carried out by the NAA laboratory personnel were time consuming and not efficient. Sample registration software is developed as part of IAEA/CRP project on ‘Development of Process Automation in the Neutron Activation Analysis (NAA) Facility in Malaysia Nuclear Agency (RC17399)’. The objective of the project is to create a pc-based data entry software during sample preparation stage. This is an effective method to replace redundant manual data entries that needs to be completed by laboratory personnel. The software developed will automatically generate sample code for each sample in one batch, create printable registration forms for administration purpose, and store selected parameters that will be passed to sample analysis program. The software is developed by using National Instruments Labview 8.6.

Sample registration software for process automation in the Neutron Activation Analysis (NAA) Facility in Malaysia nuclear agency

Science.gov (United States)

Rahman, Nur Aira Abd; Yussup, Nolida; Salim, Nazaratul Ashifa Bt. Abdullah; Ibrahim, Maslina Bt. Mohd; Mokhtar, Mukhlis B.; Soh@Shaari, Syirrazie Bin Che; Azman, Azraf B.; Ismail, Nadiah Binti

2015-04-01

Neutron Activation Analysis (NAA) had been established in Nuclear Malaysia since 1980s. Most of the procedures established were done manually including sample registration. The samples were recorded manually in a logbook and given ID number. Then all samples, standards, SRM and blank were recorded on the irradiation vial and several forms prior to irradiation. These manual procedures carried out by the NAA laboratory personnel were time consuming and not efficient. Sample registration software is developed as part of IAEA/CRP project on `Development of Process Automation in the Neutron Activation Analysis (NAA) Facility in Malaysia Nuclear Agency (RC17399)'. The objective of the project is to create a pc-based data entry software during sample preparation stage. This is an effective method to replace redundant manual data entries that needs to be completed by laboratory personnel. The software developed will automatically generate sample code for each sample in one batch, create printable registration forms for administration purpose, and store selected parameters that will be passed to sample analysis program. The software is developed by using National Instruments Labview 8.6.

Establishing management information system to solve the information management problem of nuclear safety related personnel's qualification management

International Nuclear Information System (INIS)

Sun Haipeng; Liu Zhijun; Li Tianshu

2013-01-01

With the rapid progress of nuclear energy and nuclear technology utilization, nuclear safety related personnel play an increasingly important role in ensuring nuclear safety. NNSA personnel qualification management information system conducts a multi-faceted, effective, real-time monitoring and information collection for nuclear safety staff practice unit management, knowledge management, license application, appraisal management or supervision, training management or supervision and certified staff management, and also is a milestone for NNSA to build the state department with 'five-feature' (learning-oriented, service-oriented, economical, innovative, clean-type). (authors)

Radiation protection in nuclear facilities

International Nuclear Information System (INIS)

Piechowski, J.; Lochard, J.; Lefaure, Ch.; Schieber, C.; Schneider, Th; Lecomte, J.F.; Delmont, D.; Boitel, S.; Le Fauconnier, J.P.; Sugier, A; Zerbib, J.C.; Barbey, P.

1998-01-01

Close ties exist between nuclear safety and radiation protection. Nuclear safety is made up of all the arrangements taken to prevent accidents occurring in nuclear facilities, these accidents would certainly involved a radiological aspect. Radiation protection is made up of all the arrangements taken to evaluate and reduce the impact of radiation on workers or population in normal situations or in case of accident. In the fifties the management of radiological hazards was based on the quest for minimal or even zero risk. This formulation could lead to call some activities in question whereas the benefits for the whole society were evident. Now a new attitude more aware of the real risks and of no wasting resources prevails. This attitude is based on the ALARA principle whose purpose is to maintain the exposure to radiation as low as reasonably achievable taking into account social and economic concerns. This document regroups articles illustrating different aspects of the radiation protection in nuclear facilities such as a research center, a waste vitrification workshop and a nuclear power plant. The surveillance of radiological impacts of nuclear sites on environment is examined, a point is made about the pending epidemiologic studies concerning La Hague complex. (A.C.)

Research and test facilities required in nuclear science and technology

International Nuclear Information System (INIS)

2009-01-01

Experimental facilities are essential research tools both for the development of nuclear science and technology and for testing systems and materials which are currently being used or will be used in the future. As a result of economic pressures and the closure of older facilities, there are concerns that the ability to undertake the research necessary to maintain and to develop nuclear science and technology may be in jeopardy. An NEA expert group with representation from ten member countries, the International Atomic Energy Agency and the European Commission has reviewed the status of those research and test facilities of interest to the NEA Nuclear Science Committee. They include facilities relating to nuclear data measurement, reactor development, neutron scattering, neutron radiography, accelerator-driven systems, transmutation, nuclear fuel, materials, safety, radiochemistry, partitioning and nuclear process heat for hydrogen production. This report contains the expert group's detailed assessment of the current status of these nuclear research facilities and makes recommendations on how future developments in the field can be secured through the provision of high-quality, modern facilities. It also describes the online database which has been established by the expert group which includes more than 700 facilities. (authors)

Radiological dose assessment from the operation of Daeduk nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Hwang, Won Tae; Kim, Eun Han; Suh, Kyung Suk; Choi, Young Gil [Korea Atomic Energy Research Institute, Taejon (Korea)

2000-02-01

The objective of this project is to assure the public acceptance for nuclear facilities, and the environmental safety from the operation of Daeduk nuclear facilities, such as HANARO research reactor, nuclear fuel processing facilities and others. For identifying the integrity of their facilities, the maximum individual doses at the site boundary and on the areas with high population density were assessed. Also, the collective doses within radius 80 km from the site were assessed. The radiation impacts for residents around the site from the operation of Daeduk nuclear facilities in 1999 were neglectable. 8 refs., 10 figs., 27 tabs. (Author)

STACY and TRACY: nuclear criticality experimental facilities under construction

International Nuclear Information System (INIS)

Kobayashi, I.; Takeshita, I.; Yanagisawa, H.; Tsujino, T.

1992-01-01

Japan Atomic Energy Research Institute is constructing a Nuclear Fuel Cycle Safety Engineering Research Facility, NUCEF, where the following research themes essential for evaluating safety problems relating to back-end technology in nuclear fuel cycle facilities will be studied: nuclear criticality safety research; research on advanced reprocessing processes and partitioning; and research on transuranic waste treatment and disposal. To perform nuclear criticality safety research related to the reprocessing of light water reactor spent fuels, two criticality experimental facilities, STACY and TRACY, are under construction. STACY (Static Criticality Facility) will be used for the study of criticality conditions of solution fuels, uranium, plutonium and their mixtures. TRACY (Transient Criticality Facility) will be used to investigate criticality accident phenomena with uranium solutions. The construction progress and experimental programmes are described in this Paper. (author)

Report on operation of nuclear facilities in 1991

International Nuclear Information System (INIS)

1992-06-01

The Slovenian Nuclear Safety Administration (SNSA) prepared a report on nuclear safety in the republic of Slovenia in 1991 as part of its regular practice of reporting on its work to the Government and the National Assembly of the Republic of Slovenia. The report is divided into three thematic chapters covering the activities of the SNSA, the operation of nuclear facilities in Slovenia, the activity of international missions in Slovenia and the operation of nuclear facilities around the world.

Technical obstacles to nuclear security - Russian perspective

International Nuclear Information System (INIS)

Pshakin, G.

2005-01-01

Full text: Present political, economical and social development the world - wide and in particular countries and regions facilitate number of serious and dangerous challenges for people responsible for security of materials and facilities, which could be used as a threat to the humankind in case of unauthorized approach. A number of factors have impact on the security including political, social, financial and technical nature. The security of nuclear materials and facilities where nuclear materials located and under processing is facing a number of problems such as control of the personnel who is handling the materials, access to the materials and the facilities, accounting and control of the materials storage, transportation, transactions, processing, physical protection of the materials. Each aspect of those problems must be taken into account for establishing most efficient way to keep the nuclear materials out of hands of the terrorists. Technical aspects which require serious and intent relation from political and technical communities in Russia (as example) are the following: legal base for nuclear materials protection, control and accounting and export control; personnel for nuclear materials control and accounting - skill, reliability, responsibility, training and new generation education; personnel for physical protection - skill, reliability, responsibility, training; structure of the system and equipment for materials control, verification, accountability; structure of the system and equipment for physical protection; regulatory supervision of the MPC+A system effectiveness. (author)

Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

International Nuclear Information System (INIS)

Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L.

1996-03-01

The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 5 tabs., 21 ills

Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

Energy Technology Data Exchange (ETDEWEB)

Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L. [eds.

1996-03-01

The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

International nuclear cycle fact book: Revision 9

International Nuclear Information System (INIS)

Leigh, I.W.

1989-01-01

The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. The Fact Book contains: national summaries in which a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; and international agencies in which a section for each of the international agencies which has significant fuel cycle involvement, and a listing of nuclear societies. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter is presented from the perspective of the Fact Book user in the United States

Environmental monitoring around the Swedish Nuclear Facilities

International Nuclear Information System (INIS)

Bondesson, A.; Luening, M.; Wallberg, L.; Wijk, H.

1999-01-01

The environmental monitoring programme for the nuclear facilities has shown that the radioactive discharges increase the concentrations of some radionuclides in the local marine environment around the Swedish nuclear facilities. Samples from the terrestrial environment rarely show increased radionuclide concentrations. From a radiological point of view the most important nuclide in the environmental samples usually is CS-137. However, the largest part of the present concentrations of Cs-137 in the Swedish environment originate from the Chernobyl accident. The concentrations of radionuclides that can be found in biota around the nuclear facilities are much lower than the concentration levels that are known to give acute damage to organisms. The total radiation doses from the discharges of radionuclides are small. (au)

Life Management and Safety of Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Fabbri, S.; Diluch, A.; Vega, G., E-mail: fabbri@cnea.gov.ar [Comisión Nacional de Energía Atómica, Buenos Aires (Argentina)

2014-10-15

The nuclear programme in Argentina includes: nuclear power and related supplies, medical and industrial applications, waste management, research and development and human training. Nuclear facilities require life management programs that allow a safe operation. Safety is the first priority for designers and operators. This can be attained with defence in depth: regular inspections and maintenance procedures to minimize failure risks. CNEA objectives in this area are to possess the necessary capability to give safe and fast technical support. Within this scheme, one of the main activities undertaken by CNEA is to provide technological assistance to the nuclear plants and research reactors. As a consequence of an increasing concern about safety and ageing a Life Management Department for safe operation was created to take care of these subjects. The goal is to elaborate a Safety Evaluation Process for the critical components of nuclear plants and other facilities. The overall objectives of a safety process are to ensure a continuous safe, reliable and effective operation of nuclear facilities and it means the implementation of the defence in deep concept to enhance safety for the protection of the public, the workers and the environment. (author)

Proceeding of the 7. Seminar on Technology and Safety of Nuclear Power Plants and Nuclear Facilities

International Nuclear Information System (INIS)

Hastowo, Hudi; Antariksawan, Anhar R.; Soetrisnanto, Arnold Y; Jujuratisbela, Uju; Aziz, Ferhat; Su'ud, Zaki; Suprawhardana, M. Salman

2002-02-01

The seventh proceedings of seminar safety and technology of nuclear power plant and nuclear facilities, held by National Nuclear Energy Agency. The Aims of seminar is to exchange and disseminate information about safety and nuclear Power Plant Technology and Nuclear Facilities consist of technology; high temperature reactor and application for national development sustain able and high technology. This seminar level all aspects technology, Power Reactor research reactor, high temperature reactor and nuclear facilities. The article is separated by index

Over view of nuclear fuel cycle examination facility at KAERI

Energy Technology Data Exchange (ETDEWEB)

Lee, Key-Soon; Kim, Eun-Ga; Joe, Kih-Soo; Kim, Kil-Jeong; Kim, Ki-Hong; Min, Duk-Ki [Korea Atomic Energy Research Institute, Taejon (Korea)

1999-09-01

Nuclear fuel cycle examination facilities at the Korea Atomic Energy Research Institute (KAERI) consist of two post-irradiation examination facilities (IMEF and PIEF), one chemistry research facility (CRF), one radiowaste treatment facility (RWTF) and one radioactive waste form examination facility (RWEF). This paper presents the outline of the nuclear fuel cycle examination facilities in KAERI. (author)

Engineering and technology in the deconstruction of nuclear materials production facilities

International Nuclear Information System (INIS)

Kingsley, R.S.; Reynolds, W.E.; Heffner, D.C.

1996-01-01

Technology and equipment exist to support nuclear facility deactivation, decontamination, and decommissioning. In reality, this statement is not surprising because the nuclear industry has been decontaminating and decommissioning production plants for decades as new generations of production technology were introduced. Since the 1950s, the Babcock and Wilcox Company (B ampersand W) has operated a number of nuclear materials processing facilities to manufacture nuclear fuel for the commercial power industry and the U.S. Navy. These manufacturing facilities included a mixed oxide (PuO 2 -UO 2 ) nuclear fuel manufacturing plant, low- and high-enriched uranium (HEU/LEU) chemical and fuel plants, and fuel assembly plants. In addition, B ampersand W designed and build a major nuclear research center in Lynchburg, Virginia, to support these nuclear fuel manufacturing activities and to conduct nuclear power research. These nuclear research facilities included two research reactors, a hot-cell complex for nuclear materials research, four critical experiment facilities, and a plutonium fuels research and development facility. This article describes the B ampersand W deactivation, decomtanimation, and decommisioning program

Nuclear orientation facility at Charles University in Prague

International Nuclear Information System (INIS)

Rotter, M.; Trhlik, M.; Hubalovsky, S.; Srnka, A.; Dupak, J.; Ota, J.; Pari, P.

2000-01-01

A low temperature nuclear orientation facility was installed at Charles University in the laboratory of the Department of Low Temperature Physics on the Faculty of Mathematics and Physics in Prague. The solid state as well as nuclear physics research is pursued on this facility. (author)

Accidents in nuclear facilities: classification, incidence and impact

International Nuclear Information System (INIS)

Galicia A, J.; Paredes G, L. C.

2012-10-01

A general analysis of the 146 accidents reported officially in nuclear facilities from 1945 to 2012 is presented, among them some took place in: power or research nuclear reactors, critical and subcritical nuclear assemblies, handling of nuclear materials inside laboratories belonging to institutes or universities, in radiochemistry industrial plants and nuclear fuel factories. In form graph the incidence of these accidents is illustrated classified for; category, decades, geographical localization, country classification before the OECD, failure type, and the immediate or later victims. On the other hand, the main learned lessons of the nuclear accidents of Three Mile Island, Chernobyl and Fukushima are stood out, among those that highlight; the human factors, the necessity of designs more innovative and major technology for the operation, control and surveillance of the nuclear facilities, to increase the criterions of nuclear, radiological and physics safety applied to these facilities, the necessity to carry out probabilistic analysis of safety more detailed for cases of not very probable accidents and their impact, to revalue the selection criterions of the sites for nuclear locations, the methodology of post-accident sites recovery and major instrumentation for parameters evaluation and the radiological monitoring among others. (Author)

Course in fire protection training for nuclear power plant personnel

International Nuclear Information System (INIS)

Walker, K.L.; Bates, E.F.; Randall, J.D.

1979-01-01

Proposed Regulatory Guide 1.120, entitled ''Fire Protection Guidelines for Nuclear Power Plants,'' provides detailed requirements for the overall fire protection programs at nuclear power plant sites in the United States. An essential element in such a program in the training of plant fire brigade personnel is the use of proper firefighting techniques and equipment. The Texas A and M University Nuclear Science Center (NSC) in conjunction with the Fire Protection Training Division of the Texas Engineering Extension Service has developed a one-week course to meet this training need. The program emphasizes hands-on exercises. The course is designed for up to 18 students with all protective clothing provided. Fire instructors are certified by the State of Texas, and registered nuclear engineers and certified health physicists supervise the radiological safety exercises. The first course was conducted during the week of January 8--12, 1979

Fatigue damage of nuclear facilities

International Nuclear Information System (INIS)

2001-01-01

The conference on the fatigue damage of nuclear facilities, organized by the SFEN (french society of nuclear energy), took place at Paris the 23. of november 2000. Eleven papers were presented, showing the state of the art and the research programs in the domain of the sizing rules, safety, installations damage, examination and maintenance. (A.L.B.)

Dismantling of nuclear facilities

International Nuclear Information System (INIS)

Tallec, Michele; Kus, Jean-Pierre; Mogavero, Robert; Genelot, Gabriel

2009-01-01

Although the operational life of nuclear plants is long (around 60 years for French reactors) it is nonetheless limited in time, the stopping of it being essentially due to the obsolescence of materials and processes or to economic or safety considerations. The nuclear power plants are then subjected to cleanup and dismantling operations which have different objectives and require specific techniques. The cleanup and/or dismantling of a nuclear power produces significant quantities of waste which is generally of a different nature to that produced during the operation of the concerned plant. The radioactive waste produced by these operations is destined to be sent to the waste disposal facilities of the French National Agency for the Management of Nuclear Waste. (authors)

Application of robotics in nuclear facilities

International Nuclear Information System (INIS)

Byrd, J.S.; Fisher, J.J.

1986-01-01

Industrial robots and other robotic systems have been successfully applied at the Savannah River nuclear site. These applications, new robotic systems presently under development, general techniques for the employment of robots in nuclear facilities, and future systems are discussed

Criteria, standards and policies regarding decommissioning of nuclear facilities

International Nuclear Information System (INIS)

Detilleux, E.; Lennemann, W.

1977-01-01

The paper discusses the decontamination and decommissioning experiences encountered at the Eurochemic fuel reprocessing plant, their implications and the knowledge gained from these experiences. It includes the results of technical reviews made by the Nuclear Energy Agency of OECD and the International Atomic Energy Agency regarding decommissioning nuclear facilities. The conlusions which are presented should weigh heavily in the considerations of the national authorities involved in regulating nuclear power programmes. The paper notes the special planning that should be arranged between those responsible for the nuclear facility and competent public authorities who jointly should make a realistic determination of the eventual disposition of the nuclear facility, even before it is built. Recommendations cover the responsibilities of nuclear plant entrepreneurs, designers, operators, and public and regulatory authorities [fr

Nuclear safety and radiation protection report of the Bugey nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Bugey nuclear power plant (Ain (FR)): 4 PWR reactors in operation (INB 78 and 89), one partially dismantled graphite-gas reactor (INB 45), an inter-regional fuel storage facility (MIR, INB 102), and a radioactive waste storage and conditioning facility under construction (ICEDA, INB 173). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2013

International Nuclear Information System (INIS)

2014-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2013, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, the radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Penly nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Fessenheim nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Fessenheim nuclear power plant (INB 75, Haut-Rhin, 68 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2012

International Nuclear Information System (INIS)

2013-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2012, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Penly nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Penly nuclear power plant (INB 136 and 140, Seine-Maritime, 76 (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2014

International Nuclear Information System (INIS)

2015-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2014, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions

Nuclear safety and radiation protection report of the Gravelines nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Gravelines nuclear power plant (INB 96, 97 and 122, Nord (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Blayais nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Blayais nuclear power plant (INB 86 and 110, Gironde (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Civaux nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-06-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Civaux nuclear power plant (INB 158 and 159, Vienne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Neutron fluence measurement in nuclear facilities

International Nuclear Information System (INIS)

Camacho L, M.E.

1997-01-01

The objective of present work is to determine the fluence of neutrons in nuclear facilities using two neutron detectors designed and built at Instituto Nacional de Investigaciones Nucleares (ININ), Mexico. The two neutron detectors are of the passive type, based on solid state nuclear tracks detectors (SSNTD). One of the two neutron detectors was used to determine the fluence distribution of the ports at the nuclear research reactor TRIGA Mark III, which belongs to ININ. In these facilities is important to know the neutron fluence distribution characteristic to carried out diverse kind of research activities. The second neutron detector was employed in order to carry out environmental neutron surveillance. The detector has the property to separate the thermal, intermediate and fast components of the neutron fluence. This detector was used to measure the neutron fluence at hundred points around the primary container of the first Mexican Nuclear Power plant 'Laguna Verde'. This last detector was also used to determine the neutron fluence in some points of interest, around and inside a low scattering neutron room at the 'Centro de Metrologia de Radiaciones Ionizantes' of the ININ, to know the background neutron field produced by the neutron sources used there. The design of the two neutron detector and the results obtained for each of the surveying facilities, are described in this work. (Author)

AREVA General Inspectorate Annual Report 2013 - Status of safety in nuclear facilities

International Nuclear Information System (INIS)

Oursel, Luc; Riou, Jean

2014-06-01

discipline. As in the previous year, the quality of relationship with the French nuclear safety regulator (ASN) and the management of the criticality risk were identified as areas for vigilance, as well as safety skills and resources, and sufficient managerial presence in the field. Other highlights of 2013 were the simplification of the group's legal structure, the continued roll-out of the new INB order, and the close attention paid to the conditions for implementing subcontracted work. Content: 1 - Context; 2 - Lessons learned from inspections; 3 - Radiological monitoring of personnel; 4 - Environmental monitoring; 5 - Operating experience from events; 6 - Crosscutting processes: Safety management, Safety of facilities, Operational safety; 7 - Areas for improvement and outlook; 8 - Glossary

Nuclear facility safeguards as specified by the Czechoslovak administrative law

International Nuclear Information System (INIS)

Elias, J.; Svab, J.

1978-01-01

A study is presented of the legal aspects of nuclear safeguards for the operation of nuclear power facilities evaluating the development of the legal arrangement over the past five years, i.e., encoding nuclear safeguards for nuclear facilities in the new building regulations (Act No. 50/1976 Coll. of Laws on Urban Planning and Building Regulations and implementing provisions). It also discusses the juridical position of State surveillance over the nuclear safety of nuclear facilities and its relation to surveillance carried out by specialized bodies of the State work safety inspection and to surveillance carried out by hygiene inspection bodies. (J.S.)

Monitoring around the secret nuclear facilities of naval ports; Surveillance autour des INBS des ports militaires

Energy Technology Data Exchange (ETDEWEB)

Jaskierowicz, D. [Marine Nationale, pharmacien en chef, conseiller scientifique et technique, etat-major de la marine, 83 - Toulon (France); Quere, St. [Marine Nationale, capitaine de corvette, adjoint charge de la prise en compte des installations nucleaires sur l' environnement et le personnel, 83 - Toulon (France)

2010-06-15

Based within large industrial cities (Brest, Toulon, Cherbourg) or more rural areas like Crozon (Ile Longue), French navy exploits nuclear facilities where are built, maintained and decommissioned nuclear power submarines and aircraft-carrier. The safety and the security of these installations as well as the non-impact on people and environment are continuously monitored. The DSND, a governmental regulatory body dedicated to the Defense, applies the same regulations enforced by the ASN for civilian nuclear activities. Concerning environmental monitoring, the navy answers to the DSND or the ASN, depending on the type of survey. In every nuclear site, an automatic nuclear monitoring sensor system (2SNM) runs 24/7, with the supervision of specialized personnel in radioprotection. Each year, more than 7000 samples are collected in the ecosystem and thousands of measurements are carried out in four laboratories (LASEM in Cherbourg, Brest and Toulon) - SPRS ILO) of the navy. These results are sent to the DSND and have been integrated since February 2010 to the brand-new public web site of the national monitoring network of radioactivity in the environment (RMN). (author)

Radiation protection and safety guide no. GRPB-G-1: qualification and certification of radiation protection personnel

International Nuclear Information System (INIS)

Schandorf, C.; Darko, O.; Yeboah, J.; Osei, E.K.; Asiamah, S.D.

1995-01-01

A number of accidents with radiation sources are invariably due to human factors. The achievement and maintenance of proficiency in protection and safety in working with radiation devices is a necessary prerequisite. This guide specifies the national scheme and minimum requirements for qualification and certification of radiation protection personnel. The objective is to ensure adequate level of skilled personnel by continuous upgrading of knowledge and skill of personnel. The following sectors are covered by this guide: medicine, industry, research and training, nuclear facility operations, miscellaneous activities

Experience in the recruitment, organization and training of operations and maintenance personnel for the Malaysian research reactor

International Nuclear Information System (INIS)

Jamal Khair Ibrahim.

1983-01-01

The TRIGA Reactor located at the Tun Ismail Atomic Research Centre (PUSPATI) Complex is owned and operated by the Nuclear Energy Unit of the Prime Minster's Department. The operations and maintenance personnel are part and parcel of the national civil service organization. As such, the requirement and remuneration of these personnel are handled by a central federal government personnel management agency in common with personnel from other federal government agencies. In addition, the reactor is the first and only one in Malaysia, a developing country, which is the process of committing herself towards a nuclear power programme. These factors coupled with the absence of an independent reactor operator licensing agency posed unique problems in the recruitment, organization, training and licensing of operations personnel for the facility. The paper discusses these factors and their bearing on the recruitment, training, licensing and career development prospects of the PUSPATI TRIGA Reactor operators. (author)

Intellectual decision-making system in the context of potentially dangerous nuclear power facilities

Directory of Open Access Journals (Sweden)

Danilov Alexander

2018-01-01

Full Text Available The article deals with intelligent operation decision support system under condition of potentially hazardous nuclear facilities. The proposed system is referred to the class of advising systems and does not make final decisions in case of deviations of parameters to be analyzed, but generates general ways to solve an encountered problem and issues a set of recommendations for the plant personnel. In the article a fuzzy logic tool is used as mathematic tool. Lessons learnt from operation of nuclear facilities demonstrate that existing critical components (parts, areas, welding joints are subject to increased failure under conditions of high operational loads, including beyond design loads and negative environmental impact. Usually in that situation there is probability of equipment integrity failure, when the unit is at power, with severe defect downing. For instance, the coolant leak and potential development of initial penetration defect to critical dimensions. In other words, in fact, the final observable result is always one – formation and development of operational crack which jeopardizes design integrity of the component and, accordingly, seriously compromises the nuclear power unit operation. The proposed situational model is linked with real knowledge data base where generated situational pairs are stored. The expert system is used for knowledge data base formation. Actually the proposed system consists of two independent fuzzy systems. From mathematical tool point of view, the advantage of such systems combination is lack of defuzzification unit in the first system and fuzzification unit in the second one.

Special training of shift personnel

International Nuclear Information System (INIS)

Martin, H.D.

1981-01-01

The first step of on-the-job training is practical observation phase in an operating Nuclear Plant, where the participants are assigned to shift work. The simulator training for operating personnel, for key personnel and, to some extent, also for maintenance personnel and specialists give the practical feeling for Nuclear Power Plant behaviour during normal and abnormal conditions. During the commissioning phase of the own Nuclear Power Plant, which is the most important practical training, the participants are integrated into the commissioning staff and assisted during their process of practical learning by special instructors. The preparation for the licensing exams is vitally important for shift personnel and special courses are provided after the first non-nuclear trial operation of the plant. Personnel training also includes performance of programmes and material for retraining, training of instructors and assistance in building up special training programmes and material as well as training centers. (orig./RW)

Design requirements for new nuclear reactor facilities in Canada

International Nuclear Information System (INIS)

Shim, S.; Ohn, M.; Harwood, C.

2012-01-01

The Canadian Nuclear Safety Commission (CNSC) has been establishing the regulatory framework for the efficient and effective licensing of new nuclear reactor facilities. This regulatory framework includes the documentation of the requirements for the design and safety analysis of new nuclear reactor facilities, regardless of size. For this purpose, the CNSC has published the design and safety analysis requirements in the following two sets of regulatory documents: 1. RD-337, Design of New Nuclear Power Plants and RD-310, Safety Analysis for Nuclear Power Plants; and 2. RD-367, Design of Small Reactor Facilities and RD-308, Deterministic Safety Analysis for Small Reactor Facilities. These regulatory documents have been modernized to document past practices and experience and to be consistent with national and international standards. These regulatory documents provide the requirements for the design and safety analysis at a high level presented in a hierarchical structure. These documents were developed in a technology neutral approach so that they can be applicable for a wide variety of water cooled reactor facilities. This paper highlights two particular aspects of these regulatory documents: The use of a graded approach to make the documents applicable for a wide variety of nuclear reactor facilities including nuclear power plants (NPPs) and small reactor facilities; and, Design requirements that are new and different from past Canadian practices. Finally, this paper presents some of the proposed changes in RD-337 to implement specific details of the recommendations of the CNSC Fukushima Task Force Report. Major changes were not needed as the 2008 version of RD-337 already contained requirements to address most of the lessons learned from the Fukushima event of March 2011. (author)

Supervision of the safety culture in nuclear facilities

International Nuclear Information System (INIS)

2014-11-01

This brochure issued by the Swiss Federal Nuclear Safety Inspectorate ENSI reports on safety culture aspects in nuclear facilities and ENSI’s activities as a supervisory instance. ENSI is the independent supervisory authority for the nuclear sector in Switzerland. A definition of safety culture is presented and the development of the concepts used in its monitoring are discussed. The main attributes of a good safety culture are discussed. Further, the conceptual basics and principles of such monitoring are looked at and the methods used for the supervision of safety culture in nuclear facilities are described

Decommissioning of nuclear facilities: a growing activity in the world

International Nuclear Information System (INIS)

Anasco, Raul

2001-01-01

Nuclear power plants and nuclear facilities are no different from normal buildings and factories. Eventually, they become worn-out or old fashioned, too expensive to maintain or remodel. Decommissioning a nuclear facility is different from retiring other types because of the radioactivity involved. The most important consideration in nuclear decommissioning is to protect workers and the public from exposure to harmful levels of radiation. General criteria and strategies for the decommissioning of nuclear facilities are described as well as the present decommissioning activities of the Argentine CNEA (author)

International nuclear fuel cycle fact book: Revision 9

Energy Technology Data Exchange (ETDEWEB)

Leigh, I.W.

1989-01-01

The International Nuclear Fuel Cycle Fact Book has been compiled in an effort to provide current data concerning fuel cycle and waste management facilities, R and D programs and key personnel. The Fact Book contains: national summaries in which a section for each country which summarizes nuclear policy, describes organizational relationships and provides addresses, names of key personnel, and facilities information; and international agencies in which a section for each of the international agencies which has significant fuel cycle involvement, and a listing of nuclear societies. The national summaries, in addition to the data described above, feature a small map for each country as well as some general information. The latter is presented from the perspective of the Fact Book user in the United States.

Upgrade and development of nuclear data production test facility

Energy Technology Data Exchange (ETDEWEB)

Namkung, Won; Ko, I. S.; Cho, M. H.; Lee, Y. S.; Kang, H. S. [Pohang Univ. of Science and Technology, Pohang (Korea, Republic of); Kim, G. N. [Kyungpook National Univ., Daegu (Korea, Republic of); Koh, S. K. [Univ. of Ulsan, Ulsan (Korea, Republic of); Ro, T. I. [Donga Univ., Busan (Korea, Republic of); Choi, G. U. [Korea Research Institute of Standards and Science, Daejeon (Korea, Republic of)

2005-04-15

It is necessary to improve the Pohang Neutron Facility (PNF) in order to be used as a nuclear data production facility for users in both domestic and abroad. We improved following items: upgrade the electron linac, collimators inside the TOF beam pipe, the development and installation of an automatic sample changer, the extension of the TOF beam line, and the data acquisition system. We would like to establish a utilization system for users to measure the nuclear data at the PNF. To do this, we made manuals for the accelerator operation and the data acquisition system. We also made an application form to apply for users to measure the nuclear data in both domestic and abroad. The main object of the Pohang Neutron Facility is to measure the nuclear data in the neutron energy region from thermal neutron to few hundreds of eV. In addition to neutron beams produced at the PNF, photon and electron beams are produced in this facility. We thus utilize this facility for other fields, such as test facility for detectors, activation experiments, polarized neutron beam source, and so on. In addition to these, we could use this facility for training students.

Investigation on candidates of principal facilities for exposure dose to public for the facilities using nuclear material

International Nuclear Information System (INIS)

Shimazaki, Yosuke; Sawahata, Hiroaki; Takada, Shoji; Fujimoto, Nozomu

2015-01-01

HTTR holds the nuclear fuel material use facilities in its reactor facilities, for the purpose of study on the fracture behavior of fuel and release behavior of fission products, development of high-performance fuel, and measurement of neutron flux. Due to the revision of the 'Act on the regulation of nuclear source material, nuclear fuel material and reactor', the facilities having the 'Important safety-related facilities' among the facilities applicable to the Enforcement Ordinance Article 41 (Article 41 facilities) has come to need to conform to the 'Regulations concerning standards for the location, structure, and equipment of used facilities and others'. In this case, actions such as modification by all possible means are required. The nuclear fuel substance use facilities of HTTR correspond to Article 41 facilities. So, whether it is a candidate for the 'Important safety-related facilities' has been examined. As a result, it is confirmed that the facilities are not correspond to the 'Important safety-related facilities', and it has been concluded that modification measures for the purpose of conforming to this approval standard rule are not necessary as of the present. (A.O.)

LAMPF: a nuclear research facility

International Nuclear Information System (INIS)

Livingston, M.S.

1977-09-01

A description is given of the recently completed Los Alamos Meson Physics Facility (LAMPF) which is now taking its place as one of the major installations in this country for the support of research in nuclear science and its applications. Descriptions are given of the organization of the Laboratory, the Users Group, experimental facilities for research and for applications, and procedures for carrying on research studies

Decommissioning and environmental restoration of nuclear facilities in China

International Nuclear Information System (INIS)

Pan Ziqiang

2000-01-01

In the beginning of the 1980s, the Scientific and Technological Commission (STC) began the study on the environmental impact of the nuclear industry in China. At the end of the 1980s, the STC initiated the study on the decommissioning of nuclear facilities and environmental restoration. In 1989 the STC completed the project entitled ''Radiological and Environmental Quality Assessment of the Nuclear Industry in China Over the Past Thirty Years''. The status of the environmental pollution of various nuclear facility sites was subsequently analysed. In 1994, the decommissioning and environmental restoration of the first research and manufacture complex for nuclear weapons was completed. The complex is now accessible to the public without restriction and the site has become a town. Some nuclear related facilities, such as uranium mines, are currently being decommissioned. Although uranium mining and milling has a more serious impact on the environment, the technology for decommissioning and environmental restoration in mining and milling installations is not much more complicated than that used for reactor and reprocessing facilities: much has been achieved in the area of mining and milling. (author)

Criticality safety and facility design considerations

International Nuclear Information System (INIS)

Waltz, W.R.

1991-06-01

Operations with fissile material introduce the risk of a criticality accident that may be lethal to nearby personnel. In addition, concerns over criticality safety can result in substantial delays and shutdown of facility operations. For these reasons, it is clear that the prevention of a nuclear criticality accident should play a major role in the design of a nuclear facility. The emphasis of this report will be placed on engineering design considerations in the prevention of criticality. The discussion will not include other important aspects, such as the physics of calculating limits nor criticality alarm systems

The Study on Domestic and Foreign Cases for Decommissioning of DPRK Nuclear Facilities

International Nuclear Information System (INIS)

Baek, Ye Ji; Hhu, Joo Youn; Lee, Jung Hyun; Hwang, Yong Soo

2016-01-01

This study was able to analyze domestic and foreign cases, and collect data on the approximate amount of waste and time required time; however, data on applied technology, input manpower, required cost, and waste disposal method was insufficient. DPRK activities such as nuclear weapon development or nuclear testing not only threaten our country's security but also have an adverse effect on nuclear nonproliferation and security in the international society. Therefore, denuclearization of the DPRK is prior task that is essential to peace on the Korean Peninsula. The fundamental purpose of denuclearization of the DPRK is to safely decommission facilities related to developing nuclear weapons and to depose related radioactive waste and nuclear materials. Understanding descriptive references and physical properties of the facility and its purpose important for decommissioning nuclear facilities. Although it was impossible to collect data on DPRK nuclear facilities to perform complete decommissioning, we were able to understand the process used at DPRK nuclear facilities with open source data. This study has been conducted to establish overall measures for decommissioning DPRK nuclear facilities. DPRK nuclear facilities in this study include a IRT- 2000 type nuclear research reactor, a 5 MWe graphite moderated reactor, nuclear fuel fabrication facility, and a nuclear fuel reprocessing facility, which are considered as facilities that produce or manufacture nuclear materials needed for nuclear weapons or related to such activities.

The Study on Domestic and Foreign Cases for Decommissioning of DPRK Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Baek, Ye Ji; Hhu, Joo Youn; Lee, Jung Hyun; Hwang, Yong Soo [Korea Institute of Nuclear Non-proliferation and Control, Daejeon (Korea, Republic of)

2016-05-15

This study was able to analyze domestic and foreign cases, and collect data on the approximate amount of waste and time required time; however, data on applied technology, input manpower, required cost, and waste disposal method was insufficient. DPRK activities such as nuclear weapon development or nuclear testing not only threaten our country's security but also have an adverse effect on nuclear nonproliferation and security in the international society. Therefore, denuclearization of the DPRK is prior task that is essential to peace on the Korean Peninsula. The fundamental purpose of denuclearization of the DPRK is to safely decommission facilities related to developing nuclear weapons and to depose related radioactive waste and nuclear materials. Understanding descriptive references and physical properties of the facility and its purpose important for decommissioning nuclear facilities. Although it was impossible to collect data on DPRK nuclear facilities to perform complete decommissioning, we were able to understand the process used at DPRK nuclear facilities with open source data. This study has been conducted to establish overall measures for decommissioning DPRK nuclear facilities. DPRK nuclear facilities in this study include a IRT- 2000 type nuclear research reactor, a 5 MWe graphite moderated reactor, nuclear fuel fabrication facility, and a nuclear fuel reprocessing facility, which are considered as facilities that produce or manufacture nuclear materials needed for nuclear weapons or related to such activities.

Nuclear facilities

International Nuclear Information System (INIS)

Anon.

2002-01-01

During September and October 2001, 15 events were recorded on the first grade and 1 on the second grade of the INES scale. The second grade event is in fact a re-classification of an incident that occurred on the second april 2001 at Dampierre power plant. This event happened during core refueling, a shift in the operation sequence led to the wrong positioning of 113 assemblies. A preliminary study of this event shows that this wrong positioning could have led, in other circumstances, to the ignition of nuclear reactions. Even in that case, the analysis made by EDF shows that the consequences on the staff would have been limited. Nevertheless a further study has shown that the existing measuring instruments could not have detected the power increase announcing the beginning of the chain reaction. The investigation has shown that there were deficiencies in the control of the successive operations involved in refueling. EDF has proposed a series of corrective measures to be implemented in all nuclear power plants. The other 15 events are described in the article. During this period 121 inspections have been made in nuclear facilities. (A.C.)

Nuclear Reactor Laboratory annual report, fiscal year 1981-1982

International Nuclear Information System (INIS)

Cashwell, R.J.

1982-01-01

Information related to the use of the UWNR reactor is presented concerning instructional use by the Nuclear Engineering Department; reactor sharing program; utility personnel training; sample irradiations and neutron activation analysis services; changes in personnel, facility, and procedures; and results of surveillance tests

Technical qualification requirements and training programs for radiation protection personnel at Oak Ridge National Laboratory

International Nuclear Information System (INIS)

Copenhaver, E.D.; Houser, B.S.; Butler, H.M. Jr.; Bogard, J.S.; Fair, M.F.; Haynes, C.E.; Parzyck, D.C.

1986-04-01

This document deals with the policies and practices of the Environmental and Occupational Safety Division (EOSD) at the Oak Ridge National Laboratory (ORNL) in regard to the selection, training, qualification, and requalification of radiation protection staff assigned to reactor and nonreactor nuclear facilities. Included are personnel at facilities that: (1) operate reactors or particle accelerators; (2) produce, process, or store radioactive liquid or solid waste; (3) conduct separations operations; (4) engage in research with radioactive materials and radiation sources; and (5) conduct irradiated materials inspection, fuel fabrication, deconamination, or recovery operations. The EOSD personnel also have environmental surveillance and operational and industrial safety responsibilities related to the total Laboratory

Study on system integration of robots operated in nuclear fusion facility and nuclear power plant facilities

International Nuclear Information System (INIS)

Oka, Kiyoshi

2004-07-01

A present robot is required to apply to many fields such as amusement, welfare and protection against disasters. The are however only limited numbers of the robots, which can work under the actual conditions as a robot system. It is caused by the following reasons: (1) the robot system cannot be realized by the only collection of the elemental technologies, (2) the performance of the robot is determined by that of the integrated system composed of the complicated elements with many functions, and (3) the respective elements have to be optimized in the integrated robot system with a well balance among them, through their examination, adjustment and improvement. Therefore, the system integration of the robot composed of a large number of elements is the most critical issue to realize the robot system for actual use. In the present paper, I describe the necessary approaches and elemental technologies to solve the issues on the system integration of the typical robot systems for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. These robots work under the intense radiation condition and restricted space in place of human. In particular, I propose a new approach to realize the system integration of the robot for actual use from the viewpoints of not only the environment and working conditions but also the restructure and optimization of the required elemental technologies with a well balance in the robot system. Based on the above approach, I have a contribution to realize the robot systems working under the actual conditions for maintenance in the nuclear fusion facility and rescue in the accident of the nuclear power plant facilities. (author)

Automated approach to nuclear facility safeguards effectiveness evaluation

International Nuclear Information System (INIS)

1977-01-01

Concern over the security of nuclear facilities has generated a need for a reliable, time efficient, and easily applied method of evaluating the effectiveness of safeguards systems. Such an evaluation technique could be used (1) by the Nuclear Regulatory Commission to evaluate a licensee's proposal, (2) to assess the security status of a system, or (3) to design and/or upgrade nuclear facilities. The technique should be capable of starting with basic information, such as the facility layout and performance parameters for physical protection components, and analyzing that information so that a reliable overall facility evaluation is obtained. Responding to this expressed need, an automated approach to facility safeguards effectiveness evaluation has been developed. This procedure consists of a collection of functional modules for facility characterization, critical path generation, and path evaluation combined into a continuous stream of operations. The technique has been implemented on an interactive computer-timesharing system and makes use of computer graphics for the handling and presentation of information. Using this technique a thorough facility evaluation can be made by systematically varying parameters that characterize the physical protection components of a facility according to changes in perceived adversary attributes and strategy, environmental conditions, and site status

Safety at the End of a Nuclear Facility's Life

International Nuclear Information System (INIS)

Geis, John A.; McEahern, Patrice; Evans, Brad

2004-01-01

The objective of this paper is to capture the changes that are caused by the transition from nuclear operation through closure of defense nuclear facilities and convey lessons learned from their deactivation, decontamination and demolition. The specific area of discussion is focused on the planned reduction of safety equipment and consequent shift in hazard controls and safety management programs as the facility moves toward closure. The premise of the paper is that as the dominant hazards transition from nuclear to radiological and/or industrial, the facility control of the hazards and response to the potential upset conditions must transition as well to ensure safe and efficient operations. Using recent experience of the accelerated closure mission for U. S. Department of Energy (DOE) defense nuclear facilities at Rocky Flats Environmental Technology Site, the current culture with respect to developing and implementing hazard controls and response to upset conditions is illustrated. Several events have been documented that provide insight into the challenges facing line managers and safety professionals at the end of a facility's life cycle. Replacing permanent systems with temporary equipment challenges the traditional concept of reliability. Workers disassemble safety systems daily, but must rely on some of these components or redundant systems as work continues. Decisions governing upkeep of systems that await demolition balance the risk of running to failure against the cost benefit of maintenance and repair. This is further complicated as regulators and safety professionals are often unfamiliar with these new conditions and continue to view facility work activities and potential upset conditions from a nuclear operations perspective. The results of this paper evaluate the differences in how regulatory, safety basis, and operational practices must adapt to the dynamic environment of decontamination and decommissioning in contrast to the relatively constant

Operational status of nuclear facilities in Japan. 2012 edition

International Nuclear Information System (INIS)

2012-01-01

This document is a compilation which provides an outline of the administration of nuclear facility safety regulations as well as various data including operational status, the status of periodical and safety inspections, the status of issues, and radiation management on nuclear power reactor facilities, reactor facilities in the research and development stage, and fabrication, reprocessing, disposal, and storage facilities in fiscal year 2011 (from April 2011 to March 2012). (J.P.N.)

Decommissioning of nuclear facilities using current criteria

International Nuclear Information System (INIS)

Shum, E.Y.; Swift, J.J.; Malaro, J.C.

1991-01-01

When a licensed nuclear facility ceases operation, the US Nuclear Regulatory Commission (NRC) is responsible for ensuring that the facility and its site are decontaminated to an acceptable level so that it is safe to release that facility and site for unrestricted public use. Currently, the NRC is developing decommissioning criteria based on reducing public doses from residual contamination in soils and structures at sites released for unrestricted use to as low as is reasonably achievable (ALARA). Plans are to quantify ALARA in terms of an annual total effective dose equivalent (TEDE) to an average member of the most highly exposed population group. The NRC is working on a regulatory guidance document to provide a technical basis for translating residual contamination levels to annual dose levels. Another regulatory guide is being developed to provide guidance to the licensee on how to conduct radiological surveys to demonstration compliance with the NRC decommissioning criteria. The methods and approaches used in these regulatory guides on the decommissioning of a nuclear facility are discussed in the paper

Graphics-based nuclear facility modeling and management

International Nuclear Information System (INIS)

Rod, S.R.

1991-07-01

Nuclear waste management facilities are characterized by their complexity, many unprecedented features, and numerous competing design requirements. This paper describes the development of comprehensive descriptive databases and three-dimensional models of nuclear waste management facilities and applies the database/model to an example facility. The important features of the facility database/model are its abilities to (1) process large volumes of site data, plant data, and nuclear material inventory data in an efficient, integrated manner; (2) produce many different representations of the data to fulfill information needs as they arise; (3) create a complete three-dimensional solid model of the plant with all related information readily accessible; and (4) support complete, consistent inventory control and plant configuration control. While the substantive heart of the system is the database, graphic visualization of the data vastly improves the clarity of the information presented. Graphic representations are a convenient framework for the presentation of plant and inventory data, allowing all types of information to be readily located and presented in a manner that is easily understood. 2 refs., 5 figs., 1 tab

Training for the qualification and competence of nuclear power plant personnel. Working material

International Nuclear Information System (INIS)

1993-01-01

This document contains summaries of the presentations prepared for the IAEA Review Meeting ''Training for the Qualification and Competence of Nuclear Power Plant Personnel''. The individual contributors have been indexed separately for the database. Refs, figs and tabs

Methods for reducing occupational exposures during the decommissioning of nuclear facilities

International Nuclear Information System (INIS)

1987-01-01

The decommissioning and decontamination of nuclear facilities is a topic of great interest to many Member States of the International Atomic Energy Agency (IAEA) because of the large number of older facilities which have been or soon will be retired from service. This report is a review of the current state of knowledge concerning methods for reducing occupational exposures during the decommissioning of nuclear facilities. This report focuses on water cooled nuclear power plants but, in addition, other major nuclear facilities are briefly discussed to determine how they differ from nuclear power plants in this regard. The information presented should be useful to those responsible for or interested in designing or constructing nuclear facilities or in the planning or implementing of the decommissioning of such installations. 59 refs, 1 tab

Nuclear physics at multi-GeV hadron facilities

International Nuclear Information System (INIS)

Geesaman, D.F.

1993-01-01

The important contributions Multi-GeV hadron beam facilities can make to the field of Nuclear Physics have been recognized by the community for a decade. Such a facility has featured prominently in each NSAC planning exercise in this period. As Nuclear Physicists realize they must become more concerned with the quark structure of nuclei and the applications of Quantum Chromodynamics to many body systems, the need for experiments at such facilities has become more urgent. In this talk, I will present a personal view of some of the significant recent Nuclear Physics results with multi-GeV hadron facilities, the most important opportunities which can open up to us in the future, and demonstrate how our field must take advantage of these opportunities to progress. I will also report on the recent discussions in the community to make this possible

Assessment of field training for nuclear operations personnel

International Nuclear Information System (INIS)

White, M.

1995-08-01

Training of station personnel is an important component of the safe operation of the nuclear generating station. On-the-job training (OJT) is an important component of training. The AECB initiated this project to develop a process to assess the effectiveness of OJT for field operators, and perform an initial trial of the developed process. This report describes the recommended process to assess the effectiveness of OJT for field operators, as well as the results of the initial assessment at Pickering Nuclear Generating Station. The assessment's conclusions included: (1) Ontario Hydro policies and procedures are generally consistent with industry guidelines requiring a systematic approach to training; (2) Pickering NGS field operator performance is not always consistent with documented station requirements and standards, nor industry guidelines and practices; and (3) The Pickering NGS field operator on-the-job training is not consistent with a systematic approach to training, a requirement recognized in Ontario Hydro's Policy NGD 113, and does not contribute to a high level of performance in field operator tasks. Recommendations are made regarding the use of the developed process for future assessments of on-the-job training at nuclear power plants. (author). 36 refs., 4 tabs., 3 figs

Nuclear safety and radiation protection report of the Chooz nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Chooz nuclear power plant (Ardennes (FR)): 2 PWR reactors in operation (Chooz B, INB 139 and 144) and one partially dismantled PWR reactor (Chooz A, INB 163). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary followed by the viewpoint of the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2010

International Nuclear Information System (INIS)

2011-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Paluel nuclear power plant (INB no. 103 - Paluel 1, no. 104 - Paluel 2, no. 114 - Paluel 3 and no. 115 - Paluel 4, Cany-Barville - Seine-Maritime (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2010, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document ends with a glossary and no recommendation from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Paluel nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Paluel nuclear power plant (INB no. 103 - Paluel 1, no. 104 - Paluel 2, no. 114 - Paluel 3 and no. 115 - Paluel 4, Cany-Barville - Seine-Maritime (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)

Nuclear safety and radiation protection report of the Golfech nuclear facilities - 2011

International Nuclear Information System (INIS)

2012-01-01

This safety report was established under the article 21 of the French law no. 2006-686 of June 13, 2006 relative to nuclear safety and information transparency. It presents, first, the facilities of the Golfech nuclear power plant (INB 135 and 142, Tarn-et-Garonne (FR)). Then, the nuclear safety and radiation protection measures taken regarding the facilities are reviewed: nuclear safety definition, radiation protection of intervening parties, safety and radiation protection improvement paths, crisis management, external and internal controls, technical situation of facilities, administrative procedures in progress. The incidents and accidents which occurred in 2011, are reported as well as the radioactive and non-radioactive (chemical, thermal) effluents discharge in the environment. Finally, The radioactive materials and wastes generated by the facilities are presented and sorted by type of waste, quantities and type of conditioning. Other environmental impacts (noise, microbial proliferation in cooling towers) are presented with their mitigation measures. Actions in favour of transparency and public information are presented as well. The document concludes with a glossary and a list of recommendations from the Committees for health, safety and working conditions. (J.S.)