Offshore regulators focus on incentives for safety

Energy Technology Data Exchange (ETDEWEB)

Reid, W.

2000-11-27

Strict safety regulations in effect at offshore drilling sites are discussed. The guiding principle in all existing regulation is that while economic or industrial considerations are important, the value and the concern for human life is paramount. Should some tragic event occur at an offshore drilling site that is shown to have been caused by negligence of an operator, there is no question at all that the regulatory authority, in this case the Canada-Newfoundland Offshore Petroleum Board (CNOPB), would take the negligent operator to court. Nevertheless, Canadian authorities remain confident that encouragement of maintaining a safe working environment is likely to be more successful in ensuring workplace safety than threats of punishment. Indeed, Canadian regulators have, in recent times, shown a tendency to move towards performance-based systems, as opposed to the more usual prescriptive or rule-bound regulatory regime. This new approach involves setting targets and giving companies the responsibility to implement measures to reach the targets rather than relying on government instructions. Still, performance-based regulation in Canada is relatively new and some regulations remain prescriptive. Examples are the requirement for two immersion suits and two lifeboat seats for every worker on a drilling unit.

Cooperative development of nuclear safety regulations, guides and standards based on NUSS

International Nuclear Information System (INIS)

Pachner, J.; Boyd, F.C.; Yaremy, E.M.

1984-10-01

In 1983, the Atomic Energy Control Board and Atomic Energy of Canada Limited conducted a study of a possible joint program involving Canada, a nuclear power plant importing Member State and the IAEA for the development of the national nuclear safety regulations and guides based on NUSS documents. During the study, a work plan with manpower estimates for the development of design was prepared as an investigatory exercise. The work plan suggests that a successful NUSS implementation in developing Member States will require availability of significant resources at the start of the program. The study showed that such a joint program could provide an effective mechanism for transfer of nuclear safety know-how to the developing Member States through NUSS implementation

Development of Comprehensive Nuclear Safety Regulation Plan for 2007-2011

International Nuclear Information System (INIS)

Choi, Young Sung; Kim, Woong Sik; Park, Dong Keuk; Kim, Ho Ki

2006-01-01

The Article 8-2 of Atomic Energy Act requires the government to establish Atomic Energy Promotion Plan every five years. It sets out national nuclear energy policies in a systematic and consistent way. The plan presents the goals and basic directions of national nuclear energy policies on the basis of current status and prospects. Both areas of utilization and safety management of nuclear energy are included and various projects and schedules are delineated based on the national policy directions. The safety management area in this plan deals with the overall safety and regulation policy. Its detail projects and schedule should be developed in separate plans by responsible ministries under the mediation of the MOST. As a regulatory authority, MOST is responsible for safety management area and its technical support organization, KINS has developed Comprehensive Nuclear Safety Regulation Plan as an implementation plan of safety area. This paper presents the development process and specific projects contained in the Comprehensive Nuclear Safety Regulation Plan which is under development now

Assessment of policy issues in nuclear safety regulation according to circumstantial changes

Energy Technology Data Exchange (ETDEWEB)

Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Lee, Kwang Gu; Huh, Gyun Young; Hahn, Young Tae [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

2000-03-15

The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. The approach to improve regulatory effectiveness is also reviewed and a transition to 'knowledge-based regulation' is suggested.

Strategy for public understanding and participation in nuclear safety regulation

Energy Technology Data Exchange (ETDEWEB)

Kim, H. J.; Chung, Yun Hyung

2004-02-15

The objective of this study is to help the general public and local residents to better understand and trust nuclear safety regulation. In order to obtain public confidence in nuclear safety regulation, the emotion and demand of public should be first understood and the change in an attitude to meet the present circumstances actively is requisite. Hence it is intended that a genuine communication shall be newly arranged and accomplished on the basis of mutual understanding. To achieve this, a series of public opinion poll have performed periodically and symposium for the public acceptance is held in order to frame a policy based on the understanding of nuclear safety and regulation of the general public and local residents. Besides nuclear safety indicators including safety sentiment indicators are being developed as a means to understand the safety of operating nuclear power plants from the viewpoint of the general public, a plan for the harmonious communication of nuclear safety information is established, and handbooks of nuclear terminologies and report-writing are under development in part. Finally plans for convergence of the public opinions and a wide public involvement in nuclear safety regulation are formulated and their applicability as organization and administration program is now under consideration.

R and D perspectives on the advanced nuclear safety regulation system

International Nuclear Information System (INIS)

Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook; Han, Sang Hoon; Lee, Jung Won

2009-01-01

As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea

R and D perspectives on the advanced nuclear safety regulation system

Energy Technology Data Exchange (ETDEWEB)

Lee, Chang Ju; Ahn, Sang Kyu; Park, Jong Seuk; Chung, Dae Wook [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Han, Sang Hoon; Lee, Jung Won [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2009-04-15

As current licensing process is much desired to be optimized both plant safety and regulatory efficiency, an advanced safety regulation such as risk informed regulation has been come out. Also, there is a need to have a future oriented safety regulation since a lot of new reactors are conceptualized. Keeping pace with these needs, since early 2007, Korean government has launched a new project for preparing an advanced and future oriented nuclear safety regulation system. In order to get practical achievements, the project team sets up such specific research objectives for the development of: implementation program for graded regulation using risk and performance information; multi purpose PSA models for regulatory uses; a technology neutral regulatory framework for future innovative reactors; evaluation procedure of proliferation resistance; and, performance based fire hazard analysis method and evaluation system. This paper introduces major R and D outputs of this project, and provides some perspectives for achieving effectiveness and efficiency of the nuclear regulation system in Korea.

Risk based regulation: a convenient concept for legislation and regulation in the field of technical risks?

International Nuclear Information System (INIS)

Seiler, J.H.

1998-01-01

Legislation and regulation concerning risk activities are traditionally based on deterministic safety measures. This may lead to inefficient results: sometimes the law requires safety measures which are - from an economic viewpoint - not justified because of their poor cost-effectiveness; sometimes it does not require safety measures although they would be very efficient. The risk based regulation approach wants to make the law more efficient and to get more safety at less costs. Legislation and regulation should be based on terms of risk rather than on deterministic rules. Risk should be expressed in quantitative terms and risk regulation should be based on the cost-effectiveness of safety measures. Thus a most efficient (in the sense of the economic analysis of the law) strategy for safety and environmental law could be established. The approach is economically reasonable and theoretically convincing. Its practical implementation however raises a lot of technical and legal questions. The project 'Risk Based Regulation' (1996-1999), sponsored by the Swiss National Fund for Scientific Research, intends to evaluate the practical feasibility of the approach from a technical and a legal view. It contains a general part which describes the risk based regulation approach and its legal and technical questions, case studies which try to practically implement the risk based regulation approach; the case studies are: storage and management of explosives in the army, storage and management of explosives for non-military purposes, safety at work, accident prevention in the non-professional field (mainly road accidents), fire protection, transportation of dangerous goods, waste disposal: traditional waste, waste disposal: radioactive waste, nuclear energy (reactor safety), a synthesis with recommendations for the future legislation and regulation in the field of technical risks. The paper presents the project and its preliminary results. (author)

Bases of updating of nuclear safety regulations for NPP in Romania

International Nuclear Information System (INIS)

Biro, Lucian; Serbanescu, Dan

1999-01-01

The paper presents the basic principles of reviewing and updating process of the regulatory environment pyramid. The main part of this review process refers to Cernavoda NPP Unit 2. However, there is an important impact on Cernavoda NPP Unit 1. The basic principles were defined in 1993/1994 when the licensing process for Unit 1 was resumed in order to be in accordance with the latest developments of Candu 600 worldwide and with the IAEA and NEA latest recommended documents and practices. After the licensing process for the Unit 1 was completed up to operation stage, CNCAN developed new updated regulations on nuclear safety and the regulatory pyramid in the framework of the RAMG PHARE project. CNCAN issued in 1996 the regulatory Policy for Unit 2, self-sustained and independent of future possible revisions of the regulations. The use of the concept of hierarchical systems, systematic review of safety criteria and objectives and margins along with the feedback from international and national experience on this topic ensured issuance of a reference document for future approach of nuclear safety in Romania. (authors)

Discussion about risk-informed regulations on the nuclear safety

International Nuclear Information System (INIS)

Gu Yeyi

2008-01-01

The article introduces the background and status quo of regulations on the nuclear safety in China, and points out the inadequacies existing with the current regulations. The author explains the risk-informed safety management concerning its development, status quo, and achievements made, in an attempt to make out the trend of improving regulations on the nuclear safety through risk-informed methods. Combining the U.S. development program of establishing risk-informed regulations on the nuclear safety, the author narrates principles and features of the new regulations system, and provides suggestions for the promotion of risk-informed safety management and establishment of risk-informed regulations on the nuclear safety. (author)

Framework for applying probabilistic safety analysis in nuclear regulation

International Nuclear Information System (INIS)

Dimitrijevic, V.B.

1997-01-01

The traditional regulatory framework has served well to assure the protection of public health and safety. It has been recognized, however, that in a few circumstances, this deterministic framework has lead to an extensive expenditure on matters hat have little to do with the safe and reliable operation of the plant. Developments of plant-specific PSA have offered a new and powerful analytical tool in the evaluation of the safety of the plant. Using PSA insights as an aid to decision making in the regulatory process is now known as 'risk-based' or 'risk-informed' regulation. Numerous activities in the U.S. nuclear industry are focusing on applying this new approach to modify regulatory requirements. In addition, other approaches to regulations are in the developmental phase and are being evaluated. One is based on the performance monitoring and results and it is known as performance-based regulation. The other, called the blended approach, combines traditional deterministic principles with PSA insights and performance results. (author)

Safety goals and safety culture opening plenary. 2. Safety Regulation Implemented by Gosatomnadzor of Russia

International Nuclear Information System (INIS)

Gutsalov, A.T.; Bukrinsky, A.M.

2001-01-01

more strict than those recommended in the INSAG-3 and INSAG-12 reports, but they correlate with the value of negligible individual risk of 10 -6 , established in 'Radiation Safety Standards' (NRB-99) and consider still a high level of uncertainty in calculation of these probabilities. OPB- 88/97 also defines safety culture and principles of its formation and provision. Gosatomnadzor of Russia is a federal executive authority implementing state safety regulation in nuclear energy use. One of the main activities of Gosatomnadzor of Russia is nuclear and radiation safety regulation in sitting, design, construction, operation, and decommissioning of nuclear facilities. The activities include the following: 1. development and enactment of regulatory documents; 2. licensing of activities at nuclear facilities; 3. state supervision on observing the requirements of federal rules and regulations and license conditions. Gosatomnadzor of Russia strives toward solving the problems of consistent safety improvement of facilities and technologies up to the internationally accepted level, acting within the framework of the existing set of special safety rules and regulations in production and use of nuclear energy. Simultaneously, Gosatomnadzor of Russia develops proposals aimed at the improvement of legislative and regulatory bases of the Russian Federation as well as licensing and inspection procedures and implementing them. The main principles that Gosatomnadzor of Russia follows in its practical activities are openness, publicity, and cooperation with juridical and natural persons, whose activities are regulated with the purpose of achieving safety. This cooperation is accomplished in compliance with the principle of separation of responsibilities. According to this principle, the parties that are involved in activities related to the use of nuclear materials and nuclear energy on one hand, and in the state regulation of nuclear and radiation safety on the other hand, bear

Safety Culture for Regulator Competence Management in Embarking States

International Nuclear Information System (INIS)

Kandil, M.

2016-01-01

Full text: Safety is based on preventive actions where the ability of a regulatory body to fulfill its responsibilities depends largely on the competence of its staff. Building employees’ skills and knowledge is an investment for each employee and in the future of the organization. This building must be the competence of its staff integration with their safety culture, the essential to ensure competent human resources as required in the IAEA safety standards and other documents, in which the need and importance of ensuring regulatory competence is emphasized. As it involves both operational and management issues, safety culture is a sensitive topic for regulators whose role is to ensure compliance with safety requirements and not to intervene in management decisions. A number of embarking States are aspiring to develop nuclear power generation and this means that, among other things, regulatory bodies have to be established and rapidly expanded. This paper reports major considerations on the integration of safety culture with an adequate competence management system for regulators in embarking states. (author

The Competence Promoting by NNSA for Keeping High Level Nuclear Safety: The Corner Stone of the Nuclear Safety Regulation Edifice

International Nuclear Information System (INIS)

Hu, L.

2016-01-01

Facing the fast development of the nuclear power industry and the application of radioactive sources, The MEP(NNSA) is endeavoured to promoting its competency, including: complementing the law system, training and recruiting staff to keep a capable team, constructing the R&D base to keep the basic capability, promoting safety culture both for the industry and the regulator. After the Fukushima nuclear accident, the MEP(NNSA) planned to construct R&D base, in which the Platform Nuclear Safety Monitoring and Emergency Responding, the Platform of Safety Technology of PWR Testing, the Laboratory of Safety Management Technology of Nuclear Waste Verification, the Laboratory of Environmental Radiation Monitoring and the Center of International Cooperation are included. On the other hand, the MEP(NNSA) issued Chinese nuclear safety culture policy declaration in 2014, and carried out a large scale Specialized Action for Nuclear Safety Promotion to promote the nuclear safety culture both for the industry and herself. For the nuclear regulator, It is essential to conduct the competence promoting by both “hardware” and “software”, the former is the material foundation of regulation authority, which will be effectively functioning under the facilitating of the latter. (author)

Assessment of safety regulation using an artificial society

International Nuclear Information System (INIS)

Furuta, Kazuo; Nagase, Masaya

2005-01-01

This study proposes using an artificial society to assess impacts of safety regulation on the society. The artificial society used in this study is a multi-agent system, which consists of many agents representing companies. The agents cannot survive unless they get profits by producing some products. Safety regulation functions as the business environment, which the agents will evolve to fit to. We modeled this process of survival and adaptation by the genetic algorithm. Using the proposed model, case simulations were performed to compare various regulation styles, and some interesting insights were obtained how regulation style influences behavior of the agents and then productivity and safety level of the industry. In conclusion, an effective method for assessment of safety regulation has been developed, and then several insights were shown in this study

49 CFR 176.4 - Port security and safety regulations.

Science.gov (United States)

2010-10-01

... 49 Transportation 2 2010-10-01 2010-10-01 false Port security and safety regulations. 176.4... SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION HAZARDOUS MATERIALS REGULATIONS CARRIAGE BY VESSEL General § 176.4 Port security and safety regulations. (a) Each carrier, master, agent, and charterer of a...

Safety regulation on high-pressure gas and gas business

International Nuclear Information System (INIS)

Kim, Du Yeoung; An, Dae Jun

1978-09-01

This book is divided into two parts. The first part introduces safety regulation on high-pressure gas, enforcement ordinance on safety regulation about high-pressure gas and enforcement regulation on safety regulation about high-pressure gas. The second part indicates regulations on gas business such as general rules, gas business gas supplies, using land, supervision, supple mentary rules and penalty. It has two appendixes on expected questions and questions during last years.

Managing for safety and safety culture within the UK nuclear industry. A regulator's perspective

International Nuclear Information System (INIS)

Tyrer, M.J.

2002-01-01

This paper outlines the basis of the legal system for the regulation of health and safety at work within the United Kingdom (UK), and in particular, the regulation of the nuclear industry. The framework, formulated by the regulator, which has been published as a practical guide for directors, managers, health and safety professionals and employee representatives for the successful management of health and safety is explained. This guidance, however, concentrates, to a large extent, on management systems and only addresses in part the types of issues, such as behaviours, values, attitudes and beliefs which contribute to the safety culture of an organization. The regulator of the UK nuclear industry has considered research, and other work, carried out by several organizations in this area, notably the Advisory Committee on the Safety of Nuclear Installations (ACSNI) and the International Atomic Energy Agency (IAEA), and produced its own framework for managing for safety at nuclear installations. As a regulator, the Health and Safety Executive (HSE), and its inspectorate responsible for regulation of the nuclear industry, HM Nuclear Installations Inspectorate (HMNII), are not the appropriate organization to assess the safety culture of an organization, but positively encourage organizations to both carry out this assessment themselves and to monitor their performance. To this end, HSE has developed, and made available, the Health and Safety Climate Tool which is aimed at providing organizations with information which can be used as part of a continuous improvement process. (author)

NRC safety research in support of regulation, 1988

International Nuclear Information System (INIS)

1989-05-01

This report, the fourth in a series of annual reports, was prepared in response to Congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during 1988. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

Fire safety regulations and licensing

International Nuclear Information System (INIS)

Berg, H.P.

1998-01-01

Experience of the past tow decades of nuclear power plant operation and results obtained from modern analytical techniques confirm that fires may be a real threat to nuclear safety and should receive adequate attention from the design phase throughout the life of the plant. Fire events, in particular influence significantly plant safety due to the fact that fires have the potential to simultaneously damage components of redundant safety-related equipment. Hence, the importance of fire protection for the overall safety of a nuclear power plant has to be reflected by the fire safety regulations and to be checked during the licensing process of a plant as well as during the continuous supervision of the operating plant

Improving the rationality of nuclear safety regulations

International Nuclear Information System (INIS)

Choi, Byung Sun; Choi, Y. G.; Mun, G. H.

2005-03-01

This study focuses on human nature and institutions around the risk management in Korean Nuclear Installations. Nuclear safety regulatory system in Korea has had a tendency to overvalue the technical or engineering areas. But just like other risk management system, the knowledge of social science is also required to design more valid safety regulatory system. As a result of analysis, this study suggest that performance regulation need to be introduced to current nuclear safety regulation system. In this advanced regulatory system, each nuclear generation unit have to be evaluated by performance of its own regulatory implementation and would be treated differently by the performance. Additionally, self-regulation could be very effective was to guarantee nuclear safety. Because KHNP could be judged to have an considerable capabilities to manage its own regulatory procedures. To make self-regulatory system established successfully, it is also important to arrange the appropriate incentive and compensate structures

Regulator Loss Functions and Hierarchical Modeling for Safety Decision Making.

Science.gov (United States)

Hatfield, Laura A; Baugh, Christine M; Azzone, Vanessa; Normand, Sharon-Lise T

2017-07-01

Regulators must act to protect the public when evidence indicates safety problems with medical devices. This requires complex tradeoffs among risks and benefits, which conventional safety surveillance methods do not incorporate. To combine explicit regulator loss functions with statistical evidence on medical device safety signals to improve decision making. In the Hospital Cost and Utilization Project National Inpatient Sample, we select pediatric inpatient admissions and identify adverse medical device events (AMDEs). We fit hierarchical Bayesian models to the annual hospital-level AMDE rates, accounting for patient and hospital characteristics. These models produce expected AMDE rates (a safety target), against which we compare the observed rates in a test year to compute a safety signal. We specify a set of loss functions that quantify the costs and benefits of each action as a function of the safety signal. We integrate the loss functions over the posterior distribution of the safety signal to obtain the posterior (Bayes) risk; the preferred action has the smallest Bayes risk. Using simulation and an analysis of AMDE data, we compare our minimum-risk decisions to a conventional Z score approach for classifying safety signals. The 2 rules produced different actions for nearly half of hospitals (45%). In the simulation, decisions that minimize Bayes risk outperform Z score-based decisions, even when the loss functions or hierarchical models are misspecified. Our method is sensitive to the choice of loss functions; eliciting quantitative inputs to the loss functions from regulators is challenging. A decision-theoretic approach to acting on safety signals is potentially promising but requires careful specification of loss functions in consultation with subject matter experts.

Economic consideration of nuclear safety and cost benefit analysis in nuclear safety regulation

International Nuclear Information System (INIS)

Choi, Y. S.; Choi, K. S.; Choi, K. W.; Song, I. J.; Park, D. K.

2001-01-01

For the optimization of nuclear safety regulation, understanding of economic aspects of it becomes increasingly important together with the technical approach used so far to secure nuclear safety. Relevant economic theories on private and public goods were reviewed to re-illuminate nuclear safety from the economic perspective. The characteristics of nuclear safety as a public good was reviewed and discussed in comparison with the car safety as a private safety good. It was shown that the change of social welfare resulted from the policy change induced can be calculated by the summation of compensating variation(CV) of individuals. It was shown that the value of nuclear safety could be determined in monetary term by this approach. The theoretical background and history of cost benefit analysis of nuclear safety regulation were presented and topics for future study were suggested

Radiation Safety (Qualifications) Regulations 1980

International Nuclear Information System (INIS)

1980-01-01

These Regulations, promulgated pursuant to the provisions of the Radiation Safety Act, 1975-1979, require persons engaged in activities involving radiation to pass a radiation safety examination or to possess an approved qualification in radiation. The National Health and Medical Research Council is authorised to exempt persons from compliance with these requirements or, conversely, to impose such requirements on persons other than those designated. (NEA) [fr

Environmental Regulation and Food Safety: Studies of Protection ...

International Development Research Centre (IDRC) Digital Library (Canada)

Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Book cover Environmental Regulation and Food Safety: Studies of Protection and Protectionism. Directeur(s) : Veena Jha. Maison(s) d'édition : Edward Elgar, IDRC. 1 janvier 2006. ISBN : 184542512X. 250 pages. e-ISBN : 155250185X.

48 CFR 245.7311-2 - Safety, security, and fire regulations.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Safety, security, and fire regulations. 245.7311-2 Section 245.7311-2 Federal Acquisition Regulations System DEFENSE ACQUISITION... Inventory 245.7311-2 Safety, security, and fire regulations. ...

NRC safety research in support of regulation--FY 1989

International Nuclear Information System (INIS)

1990-04-01

This report, the fifth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1989. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

NRC safety research in support of regulation, FY 1991

International Nuclear Information System (INIS)

1992-04-01

This report, the seventh in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1991. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

NRC safety research in support of regulation, FY 1990

International Nuclear Information System (INIS)

1991-04-01

This report, the sixth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1990. The goal of this office is to ensure that safety-related research provides the technical bases for rulemaking and for related decisions in support of NRC licensing and inspection activities. This research is necessary to make certain that the regulations that are imposed on licensees provide an adequate margin of safety so as to protect the health and safety of the public. This report describes both the direct contributions to scientific and technical knowledge with regard to nuclear safety and their regulatory applications

Nuclear safety regulations in the Republic of Croatia

International Nuclear Information System (INIS)

Cizmek, A.; Horvatic, M.; Ilijas, B.; Medakovic, S.

2009-01-01

Based on Nuclear Safety Act (Official Gazette No. 173/03) in 2006 State Office for Nuclear Safety (SONS) adopted beside Ordinance on performing nuclear activities (Official Gazette No. 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (Official Gazette No. 74/06) the new Ordinance on the control of nuclear material and special equipment (Official Gazette No. 15/08) and Ordinance on conditions for nuclear safety and protection with regard to the sitting, design, construction, use and decommissioning of a facility in which a nuclear activity is to be performed (Official Gazette No. 71/08). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a license to perform nuclear activity. The Ordinance also regulates the content of the form for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear conditions, whereas compliance is established by the decision passed by SONS. Ordinance on special conditions (requirements) for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety regulates these mentioned activities Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a licence to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance

Collaborative, cross-national studies on health and safety in seafaring for evidence-based Maritime policy and regulations.

Science.gov (United States)

Jensen, Olaf C

2009-01-01

Until recently, maritime health and safety policies and regulations were sparsely based on health and safety research, and only a small number of countries contributed to new research. To strengthen maritime health and safety research activities by presenting a study example and discussing the possibilities and needs for more national and cross-national research. In a cross-national epidemiological study example, the seafarers from eleven countries completed small, anonymous questionnaires concerning the working conditions on their latest tours at sea while waiting for their health examinations. Significant disparities were pointed out among the nationalities, e.g., the length of the tours at sea, the proportional distribution of officers and non-officers, the mean age structure, the injury incidence rates, and the differences of occupational safety standards. The analysis of all data together increased the statistical strength of the multivariate analyses and allowed for valid comparisons among the nationalities. The questionnaire data was used successfully in the collaborative study example, but other data sources and methods are useful for health and safety research in seafaring as well. More national and cross-national research on maritime health and safety is warranted.

European regulations on nutraceuticals, dietary supplements and functional foods: A framework based on safety

International Nuclear Information System (INIS)

Coppens, Patrick; Fernandes da Silva, Miguel; Pettman, Simon

2006-01-01

This article describes the legislation that is relevant in the marketing of functional foods in the European Union (EU), how this legislation was developed as well as some practical consequences for manufacturers, marketers and consumers. It also addresses some concrete examples of how the EU's safety requirements for food products have impacted a range of product categories. In the late nineties, research into functional ingredients was showing promising prospects for the use of such ingredients in foodstuffs. Due mainly to safety concerns, these new scientific developments were accompanied by an urgent call for legislation. The European Commission 2000 White Paper on Food Safety announced some 80 proposals for new and improved legislation in this field. Among others, it foresaw the establishment of a General Food Law Regulation, laying down the principles of food law and the creation of an independent Food Authority endowed with the task of giving scientific advice on issues based upon scientific risk assessment with clearly separated responsibilities for risk assessment, risk management and risk communication. Since then, more than 90% of the White Paper proposals have been implemented. However, there is not, as such, a regulatory framework for 'functional foods' or 'nutraceuticals' in EU Food Law. The rules to be applied are numerous and depend on the nature of the foodstuff. The rules of the general food law Regulation are applicable to all foods. In addition, legislation on dietetic foods, on food supplements or on novel foods may also be applicable to functional foods depending on the nature of the product and on their use. Finally, the two proposals on nutrition and health claims and on the addition of vitamins and minerals and other substances to foods, which are currently in the legislative process, will also be an important factor in the future marketing of 'nutraceuticals' in Europe. The cornerstone of EU legislation on food products, including

The politics of nuclear safety regulation

International Nuclear Information System (INIS)

Adam, G.

2002-01-01

The paper discusses political aspects of decision making about the safety of nuclear power plants especially in Eastern Europe and in connection with the enlargement of the European Union. The problem of the Kozloduy NPP safety is also discussed. Recommendations on the policy and tasks for nuclear regulators are given

Regulation of Aging Power Plants: Ensuring Safety in a Changing Environment

International Nuclear Information System (INIS)

Jackson, S.A.

1999-01-01

In her keynote address to the Plim and Plex 1997 Conference, Dr. Jackson, President of the US Nuclear Regulatory Commission, dealt with four problem areas: (i) the development and application of safety margins; (ii) aging mechanisms and the use of inspection and testing methods; (iii) the U. S. licence renewal process; and (iv) risk-informed, performance-based regulation. Aging effects can further complicate existing interactions between 'explicit' and 'implicit' safety margins. Attempting to satisfy these combined margins can have a significant technical and financial impact on the plant operator. Aging degradation affects a broad range of plant systems, structures and components. Inspection and testing methods are improved continually, but development of methods for direct measuring of material properties on a more microscopic level together with elaboration of more precise predictive models of aging is still needed. In the U. S., the decision on whether to seek licence renewal rests with the licensee. The NRC task is to establish a reasonable process and clear safety standards. License renewal (extension of a NPP 40-years operating licence for additional 20 years) is explicitly allowed in NRS regulations in 10 CFR Part 54. In the U. S. nuclear power industry, there is considerable interest in licence renewal. A 'risk informed' approach to regulation means that, in the decision-making, the risk information is considered along with other factors. Performance-based regulation is, by definition, results focused; its essential component is the feedback of operating experience into subsequent evaluation. When the results focus is linked to risk analysis and ranking, the result is risk-informed, performance-based regulation. The NRS applies this combined approach in all its activities and, also, in its collaborative programs with the nuclear power industry. At the threshold of the 21st century, the nuclear power industry faces an array of challenges and opportunities

Risk-based regulation: A regulatory perspective

International Nuclear Information System (INIS)

Scarborough, J.C.

1993-01-01

In the early development of regulations for nuclear power plants, risk was implicitly considered through qualitative assessments and engineering reliability principles and practices. Examples included worst case analysis, defense in depth, and the single failure criterion. However, the contributions of various systems, structures, components and operator actions to plant safety were not explicitly assessed since a methodology for this purpose had not been developed. As a consequence of the TMI accident, the use of more quantitative risk methodology and information in regulation such as probabilistic risk analysis (PRA) increased. The use of both qualitative and quantitative consideration of risk in regulation has been a set of regulations and regulatory guides and practices that ensure adequate protection of public health and safety. Presently, the development of PRA techniques has developed to the point that safety goals, expressed in terms of risk, have been established to help guide further regulatory decision making. This paper presents the personal opinions of the author as regards the use of risk today in nuclear power plant regulation, areas of further information needs, and necessary plans for moving toward a more systematic use of risk-based information in regulatory initiatives in the future

JICST Factual DatabaseJICST Chemical Substance Safety Regulation Database

Science.gov (United States)

Abe, Atsushi; Sohma, Tohru

JICST Chemical Substance Safety Regulation Database is based on the Database of Safety Laws for Chemical Compounds constructed by Japan Chemical Industry Ecology-Toxicology & Information Center (JETOC) sponsored by the Sience and Technology Agency in 1987. JICST has modified JETOC database system, added data and started the online service through JOlS-F (JICST Online Information Service-Factual database) in January 1990. JICST database comprises eighty-three laws and fourteen hundred compounds. The authors outline the database, data items, files and search commands. An example of online session is presented.

Regulatory Body Safety Culture in Non-nuclear HROs: Lessons for Nuclear Regulators

International Nuclear Information System (INIS)

Fleming, M.; Bowers, K.

2016-01-01

Regulator safety culture is a relatively new area of investigation, even though deficiencies in regulatory oversight have been identified in a number of public inquiries (e.g., Piper Alpha, Deep Water Horizon). More recently the IAEA report into the Fukushima disaster specifically identified the need for regulatory bodies to have a positive safety culture. While there are clear parallels between duty holder safety culture and regulator safety culture there are also likely to be differences. To date they have been no published studies investigating regulator safety culture. In order to develop a framework to understand regulator safety culture we conducted a literature review and interviewed safety culture subject matter experts from a range of HRO domains (e.g., offshore oil and gas). There was general consensus among participants that regulatory safety culture was an important topic that was worthy of further investigation. That there was general agreement that regulatory safety culture was multi-dimensional and that some of the elements of existing safety culture models applied to regulator culture (e.g., learning and leadership). The participants also identified unique dimensions of regulator safety culture including commitment to high standards and ethics, transparency and perceived role of the regulator. In this paper we will present the results of the interviews and present a model of regulator safety culture. This model will be contrasted with models being used in the nuclear industry. Implications for assessing regulatory safety culture will be discussed. (author)

Development of NPP safety regulation in Russia

International Nuclear Information System (INIS)

Vishnevsky, Y.G.; Gutsalov, A.T.; Bukrinsky, A.M.; Gordon, B.G.

1999-01-01

The presentation describes the organisation scheme of Russian safety regulatory bodies, their tasks and responsibilities. Legislative and regulatory basis of NPP safety regulations rely on the federal laws: Law on the Use of Nuclear Energy and Law on Radiation Safety of the Population. Role of international cooperation and Improvement of regulatory activities in Russia are emphasised

Safety regulations for radioisotopes, etc. (interim report)

International Nuclear Information System (INIS)

1980-01-01

An (interim) report by an ad hoc expert committee to the Nuclear Safety Commission, on the safety regulations for radioisotopes, etc., was presented. For the utilization of radioisotopes, etc., there is the Law Concerning Prevention of Radiation Injury Due to Radioisotopes, etc. with the advances in this field and the improvement in international standards, the regulations by the law have been examined. After explaining the basic ideas of the regulations, the problems and countermeasures in the current regulations are described: legal system, rationalization in permission procedures and others, inspection on RI management, the system of the persons in charge of radiation handling, RI transport, low-level radioactive wastes, consumer goods, definitions of RIs, radiation and sealed sources, regulations by group partitioning, RI facilities, system of personnel exposure registration, entrusting of inspection, etc. to private firms, and reduction in the works for permission among governmental offices. (author)

Safety evaluation and regulation of chemicals. 2. Impact of regulations - improvement of methods

Energy Technology Data Exchange (ETDEWEB)

Homburger, F [ed.

1985-01-01

This volume assesses the impact of new scientific knowledge on the testing and regulation of chemicals, including food additives, drugs, cosmetics, pesticides, and other commercial substances. Apart from describing the newest tests, regulations, and risk assessment strategies, chapters reflect changes forced by both the growing need for cost containment and the mounting pressure to find alternatives to animal testing. Based on an international congress, the book also brings the advantage of diversity in the background and nationality of the authors, thus allowing a view of central problems according to the different interests of academics, industry scientists, government scientists, and regulators. The book opens with coverage of national and international regulations designed to prevent and control damage to human health and the environment. Topics range from basic problems of policy design and enforcement to the specific requirements for chemical regulation in developing countries. The next chapters cover new tests, systems, and assays used in in vivo safety testing. Readers will find a critical assessment of tests used to determine teratogenicity, mutagenicity, carcinogenicity, neurotoxicity and chemical lethality. Other topics include factors operating in the public perception of chemical hazards, guidelines for decision making in the management and regulation of risks, and future trends in the methodology of safety evaluation. The volume concludes with an overview of in vitro methods for testing hepatotoxicity. Several short-term in vitro test models and limited in vivo bioassays are presented and evaluated in terms of their capacity to substitute for long-term animal studies. Expert and thorough in its coverage, the book offers a wealth of technical and practical information for toxicologists, pharmacologists, industrial policy makers, and government regulators. (orig.). With 67 figs., 34 tabs.

Legislation for the countermeasures on special issues of nuclear safety regulations

International Nuclear Information System (INIS)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul

2003-02-01

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea

Legislation for the countermeasures on special issues of nuclear safety regulations

Energy Technology Data Exchange (ETDEWEB)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Hak Man; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

2003-02-15

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea.

Regulation of chemical safety at fuel cycle facilities by the United States Nuclear Regulatory Commission

International Nuclear Information System (INIS)

Ramsey, Kevin M.

2013-01-01

When the U.S. Nuclear Regulatory Commission (NRC) was established in 1975, its regulations were based on radiation dose limits. Chemical hazards rarely influenced NRC regulations. After the Three Mile Island reactor accident in 1979, the NRC staff was directed to address emergency planning at non-reactor facilities. Several fuel cycle facilities were ordered to submit emergency plans consistent with reactor emergency plans because no other guidance was available. NRC published a notice that it was writing regulations to codify the requirements in the Orders and upgrade the emergency plans to address all hazards, including chemical hazards. The legal authority of NRC to regulate chemical safety was questioned. In 1986, an overfilled uranium hexafluoride cylinder ruptured and killed a worker. The NRC staff was directed to address emergency planning for hazardous chemicals in its regulations. The final rule included a requirement for fuel cycle facilities to certify compliance with legislation requiring local authorities to establish emergency plans for hazardous chemicals. As with emergency planning, NRC's authority to regulate chemical safety during routine operations was limited. NRC established memoranda of understanding (MOUs) with other regulatory agencies to encourage exchange of information between the agencies regarding occupational hazards. In 2000, NRC published new, performance-based, regulations for fuel cycle facilities. The new regulations required an integrated safety analysis (ISA) which used quantitative standards to assess chemical exposures. Some unique chemical exposure cases were addressed while implementing the new regulations. In addition, some gaps remain in the regulation of hazardous chemicals at fuel cycle facilities. The status of ongoing efforts to improve regulation of chemical safety at fuel cycle facilities is discussed. (authors)

Alternative development and action plan for the atomic safety regulation instruments

International Nuclear Information System (INIS)

Kim, J. Y.; Ahn, S. K.; Ham, Y. S.

2004-01-01

The goal of this study to provide highly practical model to regulation agency. Since nuclear power safety regulation has different characteristics, compared to general regulation, it is important to have new point of view and approach. But application possibility for regulation that guarantees the 'perfect safety' is very low. Therefore, it is important establish nuclear power safety regulation that is realistic as well as safety securing. In order to establish high quality regulation, evaluation of existing regulation must be done first. Thus in this study, 6 standards to evaluate existing regulation are suggested. They are clearness, efficiency, flexibility, reliability, responsibility and political consideration. Also, strategies to complement the weak points of regulatory governance, regulatory sunset, regulatory map, regulatory negotiation, regulatory benefit cost analysis, etc. These strategies can be applied all in one regulation, and can strategically be selected for application. After analyzing the result if case analysis on nuclear furnace regulation for research study, agreement was made that it is most efficient to consider in the order if clearness reliability, flexibility, confidence, political consideration, administrative efficiency and economic efficiency

78 FR 11092 - Safety and Health Regulations for Construction

Science.gov (United States)

2013-02-15

... LABOR DEPARTMENT Occupational Safety and Health Administration 29 CFR Part 1926 Safety and Health Regulations for Construction CFR Correction In Title 29 of the Code of Federal Regulations, Part 1926, revised as of July 1, 2012, on page 225, in Sec. 1926.152, paragraph (c)(16) is added to read as follows: Sec...

Review of Policy Documents for Nuclear Safety and Regulation

International Nuclear Information System (INIS)

Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki

2006-01-01

The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies

Review of Policy Documents for Nuclear Safety and Regulation

Energy Technology Data Exchange (ETDEWEB)

Kim, Woong Sik; Choi, Kwang Sik; Choi, Young Sung; Kim, Hho Jung; Kim, Ho Ki [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)

2006-07-01

The goal of regulation is to protect public health and safety as well as environment from radiological hazards that may occur as a result of the use of atomic energy. In September 1994, the Korean government issued the Nuclear Safety Policy Statement (NSPS) to establish policy goals of maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It declares the importance of establishing safety culture in nuclear community and also specifies five nuclear regulatory principles (Independence, Openness, Clarity, Efficiency and Reliability) and provides the eleven regulatory policy directions. In 2001, the Nuclear Safety Charter was declared to make the highest goal of safety in driving nuclear business clearer; to encourage atomic energy- related institutions and workers to keep in mind the mission and responsibility for assuring safety; to guarantee public confidence in related organizations. The Ministry of Science and Technology (MOST) also issues Yearly Regulatory Policy Directions at the beginning of every year. Recently, the third Atomic Energy Promotion Plan (2007-2011) has been established. It becomes necessary for the relevant organizations to prepare the detailed plans on such areas as nuclear development, safety management, regulation, etc. This paper introduces a multi-level structure of nuclear safety and regulation policy documents in Korea and presents some improvements necessary for better application of the policies.

Implementation of the new regulation on radiological safety in Peru

International Nuclear Information System (INIS)

Medina Gironzini, E.

1997-01-01

Since its creation in 1975, the Peruvian Institute of Nuclear Energy (IPEN) has enacted three regulations of national importance on the norms of protection against ionizing radiation. The first regulation, which is called regulation of radiological protection (1980) approved by a resolution of IPEN, is the result of the work of a committee constituted by IPEN and the Ministry of Health. Its implementation caused some problems as result of which, in 1989, a new regulation on radiological protection was enacted through a supreme decree. Taking into account the new recommendation of the International Commission on Radiological Protection and the International Basic Safety Standard for Protection against Ionizing Radiation and for the Safety of Radiation Sources, approved in May 1997, the regulation of radiological safety also considers evolving aspects in the Project ARCAL XVII/IAEA. This regulation includes various topics such as exclusions, requirements of protection (medical exposure, occupational exposure, public exposure, chronic exposure), requirements of source safety, interventions and emergencies, control of sources and practices (exemptions, authorizations, inspections) etc. The implementation of this regulation at the national level falls to IPEN, the unique authority commissioned to control nuclear installations, radioactivity and x ray facilities in medicine, industry and research

Education and Training of Safety Regulation for Nuclear Safety Infrastructure: Its Necessity and Unique Features

International Nuclear Information System (INIS)

Choi, Young Sung; Choi, Young Joon; Lee, Jae Cheon

2009-01-01

Faced with global warming and electricity demands, countries over the world recognize the comparative advantages of nuclear energy. It is estimated that about 300 nuclear power plants (NPPs) expect to be constructed until 2030 worldwide. In addition, according to the IAEA, approximately 20 new countries might have their first NPP in operation by 2030 in the high projection compared with bout 5 new countries in the low projection. When introducing nuclear power, the implementation of an appropriate infrastructure to address all of the relevant issues is a central concern of international community. In particular, nuclear power program requires, at an earlier stage than when construction starts, the development of a legal and regulatory framework and training of regulators and safety experts whose combined knowledge adequately covers all areas of nuclear safety and regulation applied at a NPP construction and operation. As an essential component of such human resource development, special attention was paid to the provision of education and training to regulators of which countries plan to introduce NPPs. In term of education theory, safety regulation has some unique features in learning and teaching, which are different from those of nuclear engineering or development. This paper overviews nuclear safety infrastructure, explores the roles of exporting countries, and presents features and components in education of nuclear safety regulation

Legislation for the countermeasures on special issues of nuclear safety regulations

International Nuclear Information System (INIS)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul

2004-02-01

Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation

Legislation for the countermeasures on special issues of nuclear safety regulations

Energy Technology Data Exchange (ETDEWEB)

Cho, Byung Sun; Lee, Mo Sung; Chung, Gum Chun; Kim, Heon Jin; Oh, Ho Chul [Chongju Univ., Cheongju (Korea, Republic of)

2004-02-15

Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation.

Leadership for Safety in Practice: Perspectives from a Nuclear Regulator

International Nuclear Information System (INIS)

Tyobeka, B. M.

2016-01-01

The principal responsibility for a nuclear regulator is to assure compliance with regulations and safety standards by operators. One of these requirements is demonstration of, and adherence to, nuclear safety culture by the operators. At the same time, the regulators themselves are expected to live the talk and practice what they preach, i.e., demonstrate highest levels of nuclear safety culture within their organizations. Consequently, it is recognised that leadership is important in the creation of a culture that supports and promotes a strong nuclear safety performance of an organization. The leaders of a regulatory body are vital in inspiring employees to a higher level of safety and productivity, which means that they must apply good leadership attributes on a daily basis. This paper will attempt to bring forth and share attributes for strong leadership role in promoting a safety culture within a nuclear regulatory body by surveying world-wide practices and examples in developing and advanced nuclear countries. (author)

Improving the regulation of safety at DOE nuclear facilities. Final report

International Nuclear Information System (INIS)

1995-12-01

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by DOE itself. The three major recommendations are: under any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE's nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation

Nuclear safety: risks and regulation

International Nuclear Information System (INIS)

Wood, W.C.

1983-01-01

Taking a fresh look at nuclear safety regulations, this study finds that the mandate and organization of the Nuclear Regulatory Commission (NRC) militate against its making sound decisions. The author criticizes failures to make hard decisions on societal risk, to clarify responsibility, and to implement cost-effective safety measures. Among his recommendations are reorganization of the NRC under a single authoritative administrator, separation of technical issues from social ones, and reform of the Price-Anderson Act. The author concludes that the worst eventuality would be to continue the current state of indecision. 161 references, 6 figures, 4 tables

Domestic Regulation for Periodic Safety Review of Nuclear Power Plants

International Nuclear Information System (INIS)

Kim, Daesik; Ahn, Seunghoon; Auh, Geunsun; Lee, Jonghyeok

2015-01-01

The so-called Periodic Safety Review (PSR) has been carried out such safety assessment throughout its life, on a periodic basis. In January 2001, the Atomic Energy Act and related regulations were amended to adopt the PSR institutional scheme from IAEA Nuclear Safety Guide 50-SG-O12. At that time the safety assessment was made to review the plant safety on 10 safety factors, such as aging management and emergency planning, where the safety factor indicates the important aspects of safety of an operating NPP to be addressed in the PSR. According to this legislation, the domestic utility, the KHNP has conducted the PSR for the operating NPP of 10 years coming up from operating license date, starting since May 2000. Some revisions in the PSR rule were made to include the additional safety factors last year. This paper introduces the current status of the PSR review and regulation, in particular new safety factors and updated technical regulation. Comprehensive safety assessment for Korea Nuclear Power Plants have performed a reflecting design and procedure changes and considering the latest technology every 10 years. This paper also examined the PSR system changes in Korea. As of July 2015, reviews for PSR of 18 units have been completed, with 229 nuclear safety improvement items. And implementation have been completed for 165 of them. PSR system has been confirmed that it has contributed to improvement of plant safety. In addition, this paper examined the PSR system change in Korea

A macromarketing perspective on food safety regulation

DEFF Research Database (Denmark)

Bech-Larsen, Tino; Aschemann-Witzel, Jessica

2012-01-01

of the major stakeholders in the Danish food marketing system. Adding to the literature on diffusion of regulatory initiatives, the analysis shows that the Danish ban on trans-fats had—and still has—an important impact on trans-fat regulation in other European and overseas countries. In the final section......This article discusses the implementation and diffusion of mandatory and voluntary food safety regulations from a marketing systems perspective, and specifically applies this framework to an analysis of the antecedents and implications of the Danish 2003 ban on trans-fatty acids (TFAs......). The analysis is based on reviews of published material and on interviews with food marketers, nutrition experts, and policy makers. It is established that the ban was implemented due to scientific proof of health risks associated with the intake of TFAs but also as a result of aligned interests and efforts...

Radiation Safety of Accelerator Facility with Regard to Regulation

International Nuclear Information System (INIS)

Dedi Sunaryadi; Gloria Doloresa

2003-01-01

The radiation safety of accelerator facility and the status of the facilities according to licensee in Indonesia as well as lesson learned from the accidents are described. The atomic energy Act No. 10 of 1997 enacted by the Government of Indonesia which is implemented in Radiation Safety Government Regulation No. 63 and 64 as well as practice-specific model regulation for licensing request are discussed. (author)

Legal principles of regulatory administration and nuclear safety regulation

Energy Technology Data Exchange (ETDEWEB)

Lee, Kyeong Hui; Cheong, Sang Kee [Hannam Univ., Taejon (Korea, Republic of)

2000-12-15

This research presents a critical analysis and evaluation of principles of administrative laws in order to provide framework of structural reform on the nuclear safety regulation system. The focus of this analysis and evaluation is centered around the area of origin of regulatory administrative laws; authorities of regulation; procedures of regulatory actions; regulatory enforcement; and administrative relief system. In chapter 2 the concept of regulatory administration is analysed. Chapter 3 identifies the origin of regulatory administration and the principles of administration laws. It also examines legal nature of the nuclear safety standard. In relation to regulatory authorities. Chapter 4 identifies role and responsibility of administration authorities and institutions. It also examines fundamental principles of delegation of power. Then the chapter discusses the nuclear safety regulation authorities and their roles and responsibilities. Chapter 5 classifies and examines regulatory administration actions. Chapter 6 evaluates enforcement measure for effectiveness of regulation. Finally, chapter 7 discusses the administrative relief system for reviewing unreasonable regulatory acts.

Research needs for risk-informed, performance-based regulation

International Nuclear Information System (INIS)

Cloninger, T.H.

1997-01-01

This presentation was made by an executive in the utility which operates the South Texas Project reactors, and summarizes their perspective on probabilistic safety analysis, risk-based operation, and risk-based regulation. They view it as a tool to help them better apply their resources to maintain the level of safety necessary to protect the public health and safety. South Texas served as one of the pilot plants for the application of risk-based regulation to the maintenance rule. The author feels that the process presents opportunities as well as challenges. Among the opportunities is the involvement of more people in the process, and the sense of investment they take in the decisions, in addition to the insight they can offer. In the area of challenges there is the need for better understanding of how to apply what already is known on problems, rather than essentially reinventing the wheel to address problems. Research is needed to better understand when some events are not truly of a significant safety concern. The demarcation between deterministic decisions and the appropriate application of risk-based decisions must be better defined, for the sake of the operator as well as the public observing plant operation

Risk-based rules for crane safety systems

Energy Technology Data Exchange (ETDEWEB)

Ruud, Stian [Section for Control Systems, DNV Maritime, 1322 Hovik (Norway)], E-mail: Stian.Ruud@dnv.com; Mikkelsen, Age [Section for Lifting Appliances, DNV Maritime, 1322 Hovik (Norway)], E-mail: Age.Mikkelsen@dnv.com

2008-09-15

The International Maritime Organisation (IMO) has recommended a method called formal safety assessment (FSA) for future development of rules and regulations. The FSA method has been applied in a pilot research project for development of risk-based rules and functional requirements for systems and components for offshore crane systems. This paper reports some developments in the project. A method for estimating target reliability for the risk-control options (safety functions) by means of the cost/benefit decision criterion has been developed in the project and is presented in this paper. Finally, a structure for risk-based rules is proposed and presented.

Risk-based rules for crane safety systems

International Nuclear Information System (INIS)

Ruud, Stian; Mikkelsen, Age

2008-01-01

The International Maritime Organisation (IMO) has recommended a method called formal safety assessment (FSA) for future development of rules and regulations. The FSA method has been applied in a pilot research project for development of risk-based rules and functional requirements for systems and components for offshore crane systems. This paper reports some developments in the project. A method for estimating target reliability for the risk-control options (safety functions) by means of the cost/benefit decision criterion has been developed in the project and is presented in this paper. Finally, a structure for risk-based rules is proposed and presented

Safety culture in nuclear installations - The role of the regulator

International Nuclear Information System (INIS)

Karigi, Alice W.

2002-01-01

Safety culture is an amalgamation of values, standards, morals and norms of acceptable behavior by the licensees, Radiation workers and the Regulator. The role played by a Regulator in establishing safety culture in a nuclear installation is that related to Authorization, review, assessment, inspection and enforcement. The regulator is to follow the development of a facility or activity from initial selection of the site through design, construction, commissioning, radioactive waste management through to decommissioning and closure. He is to ensure safety measures are followed through out the operation of the facility by laying down in the license conditions of controlling construction of nuclear installations and ensuring competence of the operators. (author)

Safety evaluations required in the safety regulations for Monju and the validity confirmation of safety evaluation methods

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to perform the safety evaluations of the fast breeder reactor 'Monju' and to confirm the validity of the safety evaluation methods. In JFY 2012, the following results were obtained. As for the development of safety evaluation methods needed in the safety examination achieved for the reactor establishment permission, development of the analysis codes, such as a core damage analysis code, were carried out according to the plan. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-12-01

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE`s nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation.

Improving the regulation of safety at DOE nuclear facilities. Final report: Appendices

International Nuclear Information System (INIS)

1995-12-01

The report strongly recommends that, with the end of the Cold War, safety and health at DOE facilities should be regulated by outside agencies rather than by any regulatory scheme, DOE must maintain a strong internal safety management system; essentially all aspects of safety at DOE's nuclear facilities should be externally regulated; and existing agencies rather than a new one should be responsible for external regulation

Radiation Safety (General) Regulations 1983 (Western Australia)

International Nuclear Information System (INIS)

1983-01-01

The provisions of the Regulations cover, inter alia, the general precautions and requirements relating to radiation safety of the public and radiation workers and registration of irradiating apparatus or premises on which such apparatus is operated. In addition, the Regulations set forth requirements for the operation of such apparatus and for the premises involved. (NEA) [fr

Impact of Construction Health & Safety Regulations on Project ...

African Journals Online (AJOL)

Impact of Construction Health & Safety Regulations on Project Parameters in Nigeria: Consultants and Contractors View. ... The study recommends that better attention is given to health and safety should as a project parameter and that related practice notes and guidelines should be evolved for all project stakeholders.

International Safety Regulation and Standards for Space Travel and Commerce

Science.gov (United States)

Pelton, J. N.; Jakhu, R.

The evolution of air travel has led to the adoption of the 1944 Chicago Convention that created the International Civil Aviation Organization (ICAO), headquartered in Montreal, Canada, and the propagation of aviation safety standards. Today, ICAO standardizes and harmonizes commercial air safety worldwide. Space travel and space safety are still at an early stage of development, and the adoption of international space safety standards and regulation still remains largely at the national level. This paper explores the international treaties and conventions that govern space travel, applications and exploration today and analyzes current efforts to create space safety standards and regulations at the national, regional and global level. Recent efforts to create a commercial space travel industry and to license commercial space ports are foreseen as means to hasten a space safety regulatory process.

Assessment of policy issues in nuclear safety regulation according to circumstantial changes

Energy Technology Data Exchange (ETDEWEB)

Chang, Soon Heung; Chang, Soon Heung; Lee, Byong Ho; Baek, Won Pil; Roh, Chang Hyun; Lee, Kwang Gu; Kim, Hong Chae; Lee, Yong Ho [Korea Advanced Institute of Science and Technology, Taejon (Korea, Republic of)

1999-03-15

The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. It is concluded that the Periodic Safety Review (PSR) should be implemented in Korea as soon as possible, in harmonization with the regulation for life extension of NPPs. The IAEA guidelines, including 10 year intervals and 11 safety factors, should be used as the basic guidelines. Efforts are also required to cope with other circumstantial changes such as the establishment of International Nuclear Regulators Association (INRA)

Cost-benefit comparison of nuclear and nonnuclear health and safety protective measures and regulations

International Nuclear Information System (INIS)

O'Donnell, E.P.; Mauro, J.J.

1979-01-01

This article compares the costs and benefits of health and safety measures and regulations in the nuclear and nonnuclear fields. A cost-benefit methodology for nuclear safety concerns is presented and applied to existing nuclear plant engineered safety features. Comparisons in terms of investment costs to achieve reductions in mortality rates are then made between nuclear plant safety features and the protective measures and regulations associated with nonnuclear risks, particularly with coal-fired power plants. These comparisons reveal a marked inconsistency in the cost effectiveness of health and safety policy, in which nuclear regulatory policy requires much greater investments to reduce the risk of public mortality than is required in nonnuclear areas where reductions in mortality rates could be achieved at much lower cost. A specific example of regulatory disparity regarding gaseous effluent limits for nuclear and fossil-fuel power plants is presented. It is concluded that a consistent health and safety regulatory policy based on uniform risk and cost-benefit criteria should be adopted and that future proposed Nuclear Regulatory Commission regulatory requirements should be critically evaluated from a cost-benefit viewpoint

Pakistan nuclear safety and radiation protection regulation 1990

International Nuclear Information System (INIS)

1990-01-01

In this act regulations of nuclear safety and radiation protection in Pakistan has been explained. A legal and licensing procedure to handle protection of nuclear materials, processing storage of radioactive products has been described under this regulation. In these regulations full explanation of accidental exposure, delegation of powers and record keeping/waste disposal of radioactive has been given. (A.B.)

Food suppliers' perceptions and practical implementation of food safety regulations in Taiwan

OpenAIRE

Ko, Wen-Hwa

2015-01-01

The relationships between the perceptions and practical implementation of food safety regulations by food suppliers in Taiwan were evaluated. A questionnaire survey was used to identify individuals who were full-time employees of the food supply industry with at least 3 months of experience. Dimensions of perceptions of food safety regulations were classified using the constructs of attitude of employees and corporate concern attitude for food safety regulation. The behavior dimension was cla...

Ethical issues in engineering design processes ; regulative frameworks for safety and sustainability

NARCIS (Netherlands)

Gorp, A. van

2007-01-01

The ways designers deal with ethical issues that arise in their consideration of safety and sustainability in engineering design processes are described. In the case studies, upon which this article is based, a difference can be seen between normal and radical design. Designers refer to regulative

Application of a support vector machine algorithm to the safety precaution technique of medium-low pressure gas regulators

Science.gov (United States)

Hao, Xuejun; An, Xaioran; Wu, Bo; He, Shaoping

2018-02-01

In the gas pipeline system, safe operation of a gas regulator determines the stability of the fuel gas supply, and the medium-low pressure gas regulator of the safety precaution system is not perfect at the present stage in the Beijing Gas Group; therefore, safety precaution technique optimization has important social and economic significance. In this paper, according to the running status of the medium-low pressure gas regulator in the SCADA system, a new method for gas regulator safety precaution based on the support vector machine (SVM) is presented. This method takes the gas regulator outlet pressure data as input variables of the SVM model, the fault categories and degree as output variables, which will effectively enhance the precaution accuracy as well as save significant manpower and material resources.

Nuclear safety: economic analysis of American, French and Japanese regulations

International Nuclear Information System (INIS)

Leveque, Francois

2013-05-01

While discussing and comparing the American, Japanese and French approaches and practices, and identifying the strengths and weaknesses of each of them, the author discusses why self-regulation and civil responsibility cannot guarantee a sufficient nuclear safety level, why the safety regulation authority must be independent from industry and government, whether a figure must be put to the safety objective (for example with a risk threshold), whether it is better to define detailed standards to be applied by manufacturers and operators or to define general performance criteria to be reached

International Nuclear Officials Discuss IAEA Peer Reviews of Nuclear Safety Regulations

International Nuclear Information System (INIS)

2011-01-01

Full text: Senior nuclear regulators today concluded a Workshop on the Lessons Learned from the IAEA Integrated Regulatory Review Service (IRRS) Missions. The U.S. Nuclear Regulatory Commission (NRC) hosted the workshop, in cooperation with the International Atomic Energy Agency, in Washington, DC, from 26 to 28 October 2011. About 60 senior regulators from 22 IAEA Member States took part in this workshop. The IRRS programme is an international peer review service offered by the IAEA to its Member States to provide an objective evaluation of their nuclear safety regulatory framework. The review is based on the internationally recognized IAEA Safety Standards. ''The United States Nuclear Regulatory Commission was pleased to host the IAEA's IRRS meeting this week. The discussions over the past three days have provided an important opportunity for regulators from many countries to come together to strengthen the international peer review process,'' said U.S. NRC Chairman Gregory B. Jaczko. ''Especially after the Fukushima Daiichi accident, the global community recognizes that IRRS missions fill a vital role in strengthening nuclear safety and security programs around the world, and we are proud to be a part of this important effort.'' The IAEA Action Plan on Nuclear Safety includes actions focused towards strengthening the existing IAEA peer reviews, incorporating lessons learned and improving their effectiveness. The workshop provided a platform for the exchange of information, experience and lessons learned from the IRRS missions, as well as expectations for the IRRS programme for the near future. Further improvements in the planning and implementation of the IRRS missions in the longer term were discussed. A strong commitment of all relevant national authorities to the IRRS programme was identified as a key element of an effective regulatory framework. The conclusions of the workshop will be issued in November 2011 and the main results will be reported to the IAEA

Who regulates food? Australians' perceptions of responsibility for food safety.

Science.gov (United States)

Henderson, Julie; Coveney, John; Ward, Paul

2010-01-01

Food scares have diminished trust in public institutions to guarantee food safety. Food governance after the food scare era is concerned with institutional independence and transparency leading to a hybrid of public and private sector management and to mechanisms for consumer involvement in food governance. This paper explores Australian consumers' perceptions of who is, and should be responsible for food safety. Forty-seven participants were interviewed as part of a larger study on trust in the food system. Participants associate food governance with government, industry, and the individual. While few participants can name the national food regulator, there is a strong belief that the government is responsible for regulating the quality and safety of food. Participants are wary of the role of the food industry in food safety, believing that profit motives will undermine effective food regulation. Personal responsibility for food safety practices was also identified. While there are fewer mechanisms for consumer involvement and transparency built into the food governance system, Australian consumers display considerable trust in government to protect food safety. There is little evidence of the politicisation of food, reflecting a level of trust in the Australian food governance system that may arise from a lack of exposure to major food scares.

Fusion safety regulations in the United States: Progress and trends

International Nuclear Information System (INIS)

DeLooper, J.

1994-01-01

This paper explores the issue of regulations as they apply to current and future fusion experimental machines. It addresses fusion regulatory issues, current regulations used for fusion, the Tokamak Fusion Test Reactor experience with regulations, and future regulations to achieve fusion's safety and environmental potential

A study in improvement of administrative system in the nuclear safety regulation

International Nuclear Information System (INIS)

Yook, Dong Il; Kuk, Doe Hyeong; Lee, Seong Min; Kim, Jong Sam; Hwang, Sun Ho

2001-03-01

One of the most important tasks to improve nuclear safety regulation system is to separate nuclear regulatory institutes from public agencies which promote the development nuclear power. Moreover, nuclear safety regulation should be not only specialized but optimized to be adapted for new environments such as high-tech information age. Especially, it is necessary to reform the current nuclear safety regulation systems both to be effective under the local self-administration which began to operate in recent years and to be supported by local residents

A study in improvement of administrative system in the nuclear safety regulation

Energy Technology Data Exchange (ETDEWEB)

Yook, Dong Il; Kuk, Doe Hyeong; Lee, Seong Min; Kim, Jong Sam; Hwang, Sun Ho [Chungnam National Univ., Taejon (Korea, Republic of)

2001-03-15

One of the most important tasks to improve nuclear safety regulation system is to separate nuclear regulatory institutes from public agencies which promote the development nuclear power. Moreover, nuclear safety regulation should be not only specialized but optimized to be adapted for new environments such as high-tech information age. Especially, it is necessary to reform the current nuclear safety regulation systems both to be effective under the local self-administration which began to operate in recent years and to be supported by local residents.

International experts conclude IAEA peer review of Iran's safety regulation of Bushehr NPP

International Nuclear Information System (INIS)

2010-01-01

Full text: An international team of nuclear safety experts today completed an IAEA mission to review the effectiveness of Iran's safety regulation of its first nuclear power plant and to identify possible improvements before the plant begins operation. Upon invitation of the Islamic Republic of Iran, the International Atomic Energy Agency (IAEA) assembled a team of senior regulators from seven Member States for an Integrated Regulatory Review Service (IRRS) mission. The scope of the mission was limited to the safety regulation of Bushehr nuclear power plant (BNPP-1). The IRRS review took place from 20 February to 2 March at the INRA offices in Tehran and included a technical visit to the BNPP-1 site. The mission was an objective peer review based on IAEA safety standards, and was neither an inspection, nor an audit. Ms. Olena Mykolaichuk, IRRS Team Leader and Head of the State Nuclear Regulatory Committee of Ukraine, commended her INRA counterparts: 'The regulatory work performed on the Bushehr construction and in preparation for commissioning has demonstrated significant progress of INRA as a nuclear regulatory authority,' she said. Philippe Jamet, Director of the IAEA's Nuclear Installation Safety Division, added: 'Through this IRRS mission, both Iran and the international experts contribute to the enhancement of nuclear safety and worldwide experience sharing.' In the course of its review the IRRS team identified the following strengths: - INRA has a dedicated, conscientious staff, demonstrating clear commitments to further improvements. - INRA clearly recognizes the value of peer reviews and international cooperation regarding nuclear safety. - Despite a shortage of staff, INRA demonstrated strong leadership while performing both review and assessment and inspection tasks during the BNPP-1 construction and pre-commissioning. - INRA has developed an excellent computerized documentation control system. Recommendations and suggestions to improve INRA's regulatory

Public opinion poll on safety and regulations of nuclear energy

Energy Technology Data Exchange (ETDEWEB)

Park, M. I.; Park, B. I.; Lee, S. M. [Gallup Korea, Seoul (Korea, Republic of)

2004-02-15

The purpose of this poll is not only to research understanding on safety and regulations of nuclear energy and to compare the result by time series followed 2003 to 2002 years, also to establish the public relations strategies and to offer information for developing long-term policies. The contents of the study are on the general perception, safety, management of nuclear power station, regulations and surroundings about nuclear energy.

Evolution of nuclear safety regulation for BARC Facilities

International Nuclear Information System (INIS)

Jayarajan, K.; Taly, Y.K.

2017-01-01

Safety programmes in BARC stared during the formative years and grown its stature, as the years passed by. Seventeen years of BSC, with one hundred meetings, have been quite eventful with several achievements. BSC could bring all facilities of BARC under its safety umbrella and could streamline many safety and regulatory activities. BSC aims at incident free operation of all facilities and protection of the workers, the public, the environment from radiation and other hazards. Although, incidents could not be entirely prevented, BSC have taken every event as a lesson and used the experience for improving safety. Safety enhancement is an endless journey, which has to be performed by joining hands of the managers, designers, manufacturers, inspectors and operators, in addition to the regulators

75 FR 50700 - Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, and Drawbridge...

Science.gov (United States)

2010-08-17

...] Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, and Drawbridge Operation... notice lists temporary safety zones, security zones, special local regulations, and drawbridge operation... responsive to the safety and security needs within their jurisdiction; therefore, District Commanders and...

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2004-01-01

systems important to safety in nuclear power plants, for all phases of the system life cycle. The guidance is applicable to systems important to safety. Since at present the reliability of a computer based system cannot be predicted on the sole basis of, or built in by, the design process, it is difficult to define and to agree systematically on any possible relaxation in the guidance to apply to software for safety related systems. Whenever possible, recommendations which apply only to safety systems and not to safety related systems are explicitly identified. The guidance relates primarily to the software used in computer based systems important to safety. Guidance on the other aspects of computer based systems, such as those concerned with the design of the computer based system itself and its hardware, is limited to the issues raised by the development, verification and validation of software.The main focus of this Safety Guide is on the preparation of documentation that is used for an adequate demonstration of the safety and reliability of computer based systems important to safety.This Safety Guide applies to all types of software: pre-existing software or firmware (such as an operating system), software to be specifically developed for the project, or software to be developed from an existing pre developed equipment family of hardware or software modules. This Safety Guide is intended for use by those involved in the production, assessment and licensing of computer based systems, including plant system designers, software designers and programmers, verifiers, validators, certifiers and regulators, as well as plant operators. The various interfaces between those involved are considered. (author)

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2005-01-01

systems important to safety in nuclear power plants, for all phases of the system life cycle. The guidance is applicable to systems important to safety. Since at present the reliability of a computer based system cannot be predicted on the sole basis of, or built in by, the design process, it is difficult to define and to agree systematically on any possible relaxation in the guidance to apply to software for safety related systems. Whenever possible, recommendations which apply only to safety systems and not to safety related systems are explicitly identified. The guidance relates primarily to the software used in computer based systems important to safety. Guidance on the other aspects of computer based systems, such as those concerned with the design of the computer based system itself and its hardware, is limited to the issues raised by the development, verification and validation of software.The main focus of this Safety Guide is on the preparation of documentation that is used for an adequate demonstration of the safety and reliability of computer based systems important to safety. This Safety Guide applies to all types of software: pre-existing software or firmware (such as an operating system), software to be specifically developed for the project, or software to be developed from an existing pre developed equipment family of hardware or software modules. This Safety Guide is intended for use by those involved in the production, assessment and licensing of computer based systems, including plant system designers, software designers and programmers, verifiers, validators, certifiers and regulators, as well as plant operators. The various interfaces between those involved are considered

Software for computer based systems important to safety in nuclear power plants. Safety guide

International Nuclear Information System (INIS)

2000-01-01

systems important to safety in nuclear power plants, for all phases of the system life cycle. The guidance is applicable to systems important to safety. Since at present the reliability of a computer based system cannot be predicted on the sole basis of, or built in by, the design process, it is difficult to define and to agree systematically on any possible relaxation in the guidance to apply to software for safety related systems. Whenever possible, recommendations which apply only to safety systems and not to safety related systems are explicitly identified. The guidance relates primarily to the software used in computer based systems important to safety. Guidance on the other aspects of computer based systems, such as those concerned with the design of the computer based system itself and its hardware, is limited to the issues raised by the development, verification and validation of software.The main focus of this Safety Guide is on the preparation of documentation that is used for an adequate demonstration of the safety and reliability of computer based systems important to safety.This Safety Guide applies to all types of software: pre-existing software or firmware (such as an operating system), software to be specifically developed for the project, or software to be developed from an existing pre developed equipment family of hardware or software modules. This Safety Guide is intended for use by those involved in the production, assessment and licensing of computer based systems, including plant system designers, software designers and programmers, verifiers, validators, certifiers and regulators, as well as plant operators. The various interfaces between those involved are considered

49 CFR 397.2 - Compliance with Federal motor carrier safety regulations.

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false Compliance with Federal motor carrier safety...) FEDERAL MOTOR CARRIER SAFETY ADMINISTRATION, DEPARTMENT OF TRANSPORTATION FEDERAL MOTOR CARRIER SAFETY REGULATIONS TRANSPORTATION OF HAZARDOUS MATERIALS; DRIVING AND PARKING RULES General § 397.2 Compliance with...

A study on enforcement effects of radiation safety control regulations for diagnostic X-ray equipment

International Nuclear Information System (INIS)

Sung, Mo IL; Park, Myeong Hwan; Kwon, Duk Moon; Lee, Joon IL

1999-01-01

The purposes of this study are to analyze the realities after enforcements of safety control regulations for diagnostic X-ray equipment and to suggest means for an improvement of low radiation safety control. A questionnaire survey for medical radiologic technologists was carried out to determine enforcement effects of the safety control regulations. The results of analysis from the survey are as follows. That is, most of he respondents realized the importance of the radiation safety control system, but about a half of them revealed that regulations were not well observed in accordance with their purposes. Only 43.9 percent of the respondents took an active part in quality control of radiation. And responsibility, sex, age, and knowledge for safety control were important indicators for observations of the regulations. Training for the safety control regulations are needed to ensure safety control and proper usage of diagnostic X-ray equipment. And management of organizations using diagnostic X-ray equipment have to understand and stress the importance of radiation safety control system. (author)

The UK nuclear regulator's view of external influences on safety

International Nuclear Information System (INIS)

Summers, J.L.

2001-01-01

Over the past forty or so years, significant changes have taken place in the UK nuclear industry and the pace of change is continually increasing. As a consequence, the Nuclear Installations Inspectorate (NII), the UK's nuclear regulator, has also had to change. This paper describes some of the challenges to safety that have arisen in recent years and how NII's style of regulation has had to adapt to ensure that safety is maintained and improved. NII's approach has been to: be proactive in its relations with Government and market regulators; adopt new competencies to equip it for the challenges it faces; strive to improve its efficiency and effectiveness; and develop new approaches to regulating changes in licensees' organisations and ways of working. Importantly, NII seeks to anticipate change rather than react to it. (author)

Safety performance indicators used by the Russian Safety Regulatory Authority in its practical activities on nuclear power plant safety regulation

International Nuclear Information System (INIS)

Khazanov, A.L.

2005-01-01

The Sixth Department of the Nuclear, Industrial and Environmental Regulatory Authority of Russia, Scientific and Engineering Centre for Nuclear and Radiation Safety process, analyse and use the information on nuclear power plants (NPPs) operational experience or NPPs safety improvement. Safety performance indicators (SPIs), derived from processing of information on operational violations and analysis of annual NPP Safety Reports, are used as tools to determination of trends towards changing of characteristics of operational safety, to assess the effectiveness of corrective measures, to monitor and evaluate the current operational safety level of NPPs, to regulate NPP safety. This report includes a list of the basic SPIs, those used by the Russian safety regulatory authority in regulatory activity. Some of them are absent in list of IAEA-TECDOC-1141 ('Operational safety performance indicators for nuclear power plants'). (author)

A German perspective on advances in safety standards and regulations

International Nuclear Information System (INIS)

Berg, H.P.; Herttrich, P.M.

1993-01-01

At present, different proposals for evolutionary or innovative reactors are under consideration. Therefore, it is necessary that the regulators give guidance on the required safety characteristics of future designs of nuclear power plants. On the one hand, existing regulations have to be updated according to the current state of science and technology. Best available and adequately approved technology has to be used as a yardstick for the acceptability of future basic design features. On the other hand, potential safety features of innovative or revolutionary designs must be considered as serious competitors and potential technical solutions taking the state of maturity of the concepts, the extent of practical experience and the level of effort needed for realization into due account. On this background, recent developments of the Atomic Energy Act, of safety regulations and investigations of requirements for future designs in the Federal Republic of Germany and current projects of international cooperation are presented. (author)

Assessment of policy issues in nuclear safety regulation according to circumstantial changes

Energy Technology Data Exchange (ETDEWEB)

Chang, Soon Heung; Lee, Byong Ho; Baek, Woon Pil; Lee, Seong Wook; Choi, Seong Soo; Roh, Chang Hyun; Lee, Kwang Gu [Korea Advanced Institute of Scienc and Technology, Taejon (Korea, Republic of)

1998-03-15

The objective of the work is to assess various issues in nuclear safety regulation in consideration of circumstantial changes. Emphasis is given to the safety of operating NPPs. The derivation of an effective regulation system considering 'Rhodic Safety Review (PSR)', 'operating License Renewal (LR)', 'backfitting' and 'maintenance rule' is the main objective of the first two years. It is found that those approaches should be introduced in Korea as soon as possible, with cross lingkage to maximize the effectiveness of regulation. In particular, the approaches for PSR are discussed with consultation of IAEA document and foreign practices.

Development in France of nuclear safety technical regulations and standards used in the licensing procedure

International Nuclear Information System (INIS)

Lebouleux, P.

1983-04-01

Initially, the Commissariat a l'Energie Atomique was the overall structure which encompassed all nuclear activities in France, including those connected with radiological protection and nuclear safety. As other partners appeared, the Authorities have laid down national regulations relative to nuclear installations since 1963. These regulations more particularly provide for the addition of prescriptions with which the applicant must comply to obtain the necessary licenses and the establishment of General Technical Regulations pertaining to nuclear safety. The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operation of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. A RFS, or a letter, can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

The improvement of nuclear safety regulation : American, European, Japanese, and South Korean experiences

International Nuclear Information System (INIS)

Cho, Byung Sun

2005-01-01

Key concepts in South Korean nuclear safety regulation are safety and risk. Nuclear regulation in South Korea has required reactor designs and safeguards that reduce the risk of a major accident to less than one in a million reactor-years-a risk supposedly low enough to be acceptable. To data, in South Korean nuclear safety regulation has involved the establishment of many technical standards to enable administration enforcement. In scientific lawsuits in which the legal issue is the validity of specialized technical standards that are used for judge whether a particular nuclear power plant is to be licensed, the concept of uncertainty law is often raised with regard to what extent the examination and judgement by the judicial power affects a discretion made by the administrative office. In other words, the safety standards for nuclear power plants has been adapted as a form of the scientific technical standards widely under the idea of uncertainty law. Thus, the improvement of nuclear safety regulation in South Korea seems to depend on the rational lawmaking and a reasonable, judicial examination of the scientific standards on nuclear safety

Legal status of minister's notices and technology standards of 'Korea institute of nuclear safety'(KINS) to regulate nuclear safety

International Nuclear Information System (INIS)

Jung, S. K.; Jung, M. M.; Kim, S. W.; Jang, K. H.; Oh, B. J.

2003-01-01

Concerning nuclear safety or technology standards, each of 'notices' issued by minister of science and technology(MOST) empowered by law of its regulation is obviously forceful as a law, if not all. But the standards made by the chief of Korea institute of nuclear safety(KINS) to meet the tasks entrusted to KINS by MOST is only conditionally forceful as a law, that is, on the condition that law or regulation empowered the chief of KINS to make nuclear safety and/or technology standards

Environmental Regulation and Food Safety: Studies of Protection ...

International Development Research Centre (IDRC) Digital Library (Canada)

2006-01-01

Jan 1, 2006 ... Book cover Environmental Regulation and Food Safety: Studies of ... are sometimes perceived in developing countries as nontariff barriers to trade. ... In some cases, products that had initially been refused access to a ...

Food suppliers' perceptions and practical implementation of food safety regulations in Taiwan

Directory of Open Access Journals (Sweden)

Wen-Hwa Ko

2015-12-01

Full Text Available The relationships between the perceptions and practical implementation of food safety regulations by food suppliers in Taiwan were evaluated. A questionnaire survey was used to identify individuals who were full-time employees of the food supply industry with at least 3 months of experience. Dimensions of perceptions of food safety regulations were classified using the constructs of attitude of employees and corporate concern attitude for food safety regulation. The behavior dimension was classified into employee behavior and corporate practice. Food suppliers with training in food safety were significantly better than those without training with respect to the constructs of perception dimension of employee attitude, and the constructs of employee behavior and corporate practice associated with the behavior dimension. Older employees were superior in perception and practice. Employee attitude, employee behavior, and corporate practice were significantly correlated with each other. Satisfaction with governmental management was not significantly related to corporate practice. The corporate implementation of food safety regulations by suppliers was affected by employees' attitudes and behaviors. Furthermore, employees' attitudes and behaviors explain 35.3% of corporate practice. Employee behavior mediates employees' attitudes and corporate practices. The results of this study may serve as a reference for governmental supervision and provide training guidelines for workers in the food supply industry.

The ConCom Safety Management Scale: developing and testing a measurement instrument for control-based and commitment-based safety management approaches in hospitals.

Science.gov (United States)

Alingh, Carien W; Strating, Mathilde M H; van Wijngaarden, Jeroen D H; Paauwe, Jaap; Huijsman, Robbert

2018-03-06

Nursing management is considered important for patient safety. Prior research has predominantly focused on charismatic leadership styles, although it is questionable whether these best characterise the role of nurse managers. Managerial control is also relevant. Therefore, we aimed to develop and test a measurement instrument for control-based and commitment-based safety management of nurse managers in clinical hospital departments. A cross-sectional survey design was used to test the newly developed questionnaire in a sample of 2378 nurses working in clinical departments. The nurses were asked about their perceptions of the leadership behaviour and management practices of their direct supervisors. Psychometric properties were evaluated using confirmatory factor analysis and reliability estimates. The final 33-item questionnaire showed acceptable goodness-of-fit indices and internal consistency (Cronbach's α of the subscales range: 0.59-0.90). The factor structure revealed three subdimensions for control-based safety management: (1) stressing the importance of safety rules and regulations; (2) monitoring compliance; and (3) providing employees with feedback. Commitment-based management consisted of four subdimensions: (1) showing role modelling behaviour; (2) creating safety awareness; (3) showing safety commitment; and (4) encouraging participation. Construct validity of the scale was supported by high factor loadings and provided preliminary evidence that control-based and commitment-based safety management are two distinct yet related constructs. The findings were reconfirmed in a cross-validation procedure. The results provide initial support for the construct validity and reliability of our ConCom Safety Management Scale. Both management approaches were found to be relevant for managing patient safety in clinical hospital departments. The scale can be used to deepen our understanding of the influence of patient safety management on healthcare professionals

Reference values on safety regulation of land disposal of low level radioactive solid waste (the second interim report) and its incorporation into legal regulations

International Nuclear Information System (INIS)

Aoki, Terumi

1994-01-01

Safety regulation of land disposal of low level radioactive solid waste in Japan is based on 'the basic philosophy on the safety regulation of land disposal of low level radioactive solid waste' determined by the Nuclear safety Committee (October 1985). The basic philosophy on the upper limit of radioactivity of disposed wastes was published as the reference values in the interim report (February 1987) and in the second interim report (June 1992). In the second interim report, the upper limits of radioactivity are established for three types of solid radioactive wastes: 1) metals, incombustible or flame resistant wastes generated nuclear reactor facilities and solidified in vessels, 2) large metallic structures generated from decommissioning of reactor facilities and difficult to solidify in vessels, and 3) radioactive concrete waste generated from decommissioning of reactor facilities. The upper limits of radioactivity are presented for C-14, Co-60, Ni-63, Sr-90, Cs-137, alfa-emmitters, Ca-41 (for concrete) and Eu-152 (for concrete). Related laws and regulations in Japan on safe disposal of low level wastes are explained. (T.H.)

Knowledge Management for Safety Regulators: Cooperation to Achieve a Much Needed Product

International Nuclear Information System (INIS)

Mallick, S.

2016-01-01

Full text: Knowledge management (KM) has been identified by a number of IAEA documents as one of the key factors that can contribute to the safe and efficient operation of nuclear facilities in Member States. The IAEA Strategic Approaches to Education and Training in Nuclear and Radiation, Transport and Waste Safety identify and underline KM as an important line of action for effective national and organizational strategies in education and training. The capacity building “umbrella concept”, developed within the Action Plan in Nuclear Safety, also recognizes KM as one of the main four pillars (Education and Training, Human Resource Development, Knowledge Management and Knowledge Networks) of capacity building. Within existing IAEA publications, there is currently no specific practical guidance on how to develop and implement KM programmes for regulators. As such, in 2014, the IAEA Steering Committee on Regulatory Capacity Building and Knowledge Management requested the IAEA to develop a publication providing such practical guidance. The objective of the publication is to provide practical guidance to Member States on how to plan, establish and maintain an effective safety KM programme for regulators of facilities and activities. The report will identify benefits and uses of KM by regulators and will describe how a regulator could use KM in support of its functions. This presentation will provide an overview of the Knowledge Management for Safety Regulators document while highlighting the cross-departmental cooperation (i.e., NS and NE) used in its development. Furthermore, this presentation will provide insight into the challenges currently being faced by safety regulators vis-à-vis KM programmes and present potential paths forward with respect to the definition of efficient and effective KM indicators. (author

Stakeholder confidence in effective safety regulation. A regulator's view on the role of independent research capability

International Nuclear Information System (INIS)

Kotra, Janet; Mohanty, Sitakanto

2006-01-01

The authors provided a regulator's view on the role of independent research capability and its relationship to stakeholder confidence. They underscored the NRC's commitment to regulatory openness in its Strategic Plan. A number of actions have been adopted to achieve openness: public access to information about risks, safety and licensee performance that is accurate and timely; enhanced awareness of NRC as an independent regulator; fair and timely process for public involvement in NRC's decision-making; and early public involvement and two-way communication to enhance public confidence in NRC's regulatory process. The presentation reviewed the ways through which the NRC seeks to inspire confidence in its process as independent regulator and in future decisions concerning whether to authorize the U.S. DOE to construct the proposed repository at Yucca Mountain. Key to this will be reviewing all information objectively, making open decisions based on sound, scientific judgements about the facts; and maintaining an open and fair public process, and accessing independent R and D. It was noted that among the requirements for the safety review for the Yucca Mountain repository will be extensive technical and scientific analyses, evaluation of expert judgement, and long-range modelling assessments of expected repository performance. NRC requires independent scientific and engineering analyses to develop technical bases for regulations and guidance; evaluate adequacy of DOE's safety case for a potential repository; assist preparation of NRC Safety Evaluation Report; provide technical support for NRC testimony during licensing hearing; and develop effective outreach and communication tools. Confidence in NRC's use of science and engineering will depend upon: competence; independence; open and fair process; regulatory outcomes that are subject to verification and monitoring. To assist, the NRC established the Centre for Nuclear Waste Regulatory

Study on the development of safety regulations for geological disposal of high-level radioactive waste

International Nuclear Information System (INIS)

Wei Fangxin

2012-01-01

The development of regulations under Regulations on Safety Management of Radioactive Waste has become necessary as the issuance of it. The regulations related to geological disposal of high-level radioactive waste can promote the progress of research and development on geological disposal of high-level radioactive waste in China. This paper has present suggestions on development of regulations on geological disposal of high-level radioactive waste by analyzing development of safety regulations on geological disposal of high-level radioactive waste in foreign countries and problems occurred in China and discussed important issues related to the development of safety regulations on geological disposal of high-level radioactive waste. (author)

Safety regulation for the design approval of special form radioactive sources

International Nuclear Information System (INIS)

Cho, Woon-Kap

2009-01-01

Several kinds of special form radioactive sources for industrial, medical applications are being produced in Korea. Special form radioactive sources should meet strict safety requirements specified in the domestic safety regulations and the design of the sources should be certified by the regulatory authority, the Ministry of Education, Science and Technology (MEST). Several safety tests such as impact, percussion, heating, and leak tests are performed on the sources according to the domestic regulations and the international safety standards such as ANSI N542-1977 and ISO 2919-1999(E). As a regulatory expert body, Korea Institute of Nuclear Safety (KINS) assesses various types of application documents, such as safety analysis report, quality assurance program, and other documents evidencing fulfillment of requirements for design approval of the special form radioactive sources, submitted by a legal person who intends to produce special form radioactive sources and then reports the assessment result to MEST. A design approval certificate is issued to the applicant by MEST on the basis of a technical evaluation report presented by KINS.

A comparison of some Mexican/U.S. safety regulations

Energy Technology Data Exchange (ETDEWEB)

Bunner, W.R. [Training Associates, Columbus, OH (United States)

1994-12-31

In the US, safety and hygiene began to be enforced broadly with the formation of the US Department of Labor`s, Occupational Safety and Health Administration (OSHA) in 1970. In Mexico, the 1917 Constitution required companies to protect their workers against safety and hygiene hazards in the workplace. Additional requirements were added with the Federal Labor Law of 1931. General safety and hygiene regulations were added in 1934. Modern-day federal labor law in Mexico requires the creation of mixed safety and hygiene commissions in all industries. However, only about 114,000 workplaces have registered mixed commissions. In a similar vein, the most favored OSHA reform bill in the US proposes to require safety and health committees in all work places. At this time such committees are common in larger companies but not in smaller ones.

CONFORMITY TO OCCUPATIONAL SAFETY AND HEALTH REGULATIONS IN MALAYSIAN SMALL AND MEDIUM ENTERPRISES

OpenAIRE

Baba Md Deros; Ahmad Rasdan Ismail; Jaharah A. Ghani; Mohd Yusri Mohd Yusof

2014-01-01

Regulation on occupational safety and health in Malaysia had evolved from the prescriptive factory and machinery act to a self-regulated occupational safety and health act. However, from the authors’ observation the high standards of occupational safety and health culture that surpass the legal requirement were not widely practiced by Small and Medium Enterprises (SMEs). The two main objectives of this study are: First, first, to identify and determine the level of conformity and second...

Outline of safety regulations and administrations for commercial nuclear power plants in Japan

International Nuclear Information System (INIS)

Kinichi Yamamoto

1987-01-01

Outline of safety regulations and administrations for the commercial nuclear power plants in Japan is briefly described. The strict measures for safety assurance are always taken based on the principle of defense-indepth. In the actual procedures of regulatory control, the examinations and inspections shall be performed at each individual step in the stage of applications, and also in the stage of constructions. Thus, those regulatory examinations and inspections shall be performed in detail and carefully, and at the most suitable time; resulting in an effective regulatory control by the Ministry of International Trade and Industry. (author)

Food suppliers' perceptions and practical implementation of food safety regulations in Taiwan.

Science.gov (United States)

Ko, Wen-Hwa

2015-12-01

The relationships between the perceptions and practical implementation of food safety regulations by food suppliers in Taiwan were evaluated. A questionnaire survey was used to identify individuals who were full-time employees of the food supply industry with at least 3 months of experience. Dimensions of perceptions of food safety regulations were classified using the constructs of attitude of employees and corporate concern attitude for food safety regulation. The behavior dimension was classified into employee behavior and corporate practice. Food suppliers with training in food safety were significantly better than those without training with respect to the constructs of perception dimension of employee attitude, and the constructs of employee behavior and corporate practice associated with the behavior dimension. Older employees were superior in perception and practice. Employee attitude, employee behavior, and corporate practice were significantly correlated with each other. Satisfaction with governmental management was not significantly related to corporate practice. The corporate implementation of food safety regulations by suppliers was affected by employees' attitudes and behaviors. Furthermore, employees' attitudes and behaviors explain 35.3% of corporate practice. Employee behavior mediates employees' attitudes and corporate practices. The results of this study may serve as a reference for governmental supervision and provide training guidelines for workers in the food supply industry. Copyright © 2015. Published by Elsevier B.V.

The Role of the Regulator in the Field of Safety Culture to Shun Nuclear Accident

International Nuclear Information System (INIS)

Kandil, M.M.

2016-01-01

The 2011 accident at the Fukushima Daiichi nuclear power plant in Japan has, as might be expected, led to improvements in equipment at plants around the world that have fortified safety systems and allowed for better protection against rare, extreme natural events. Equally important to the process of improving nuclear safety is the emphasis placed on implementing quality improvements to the human side of nuclear safety, a crucial element that is often not considered by those outside the nuclear sector. Ensuring nuclear reactor safety is not only a question of physical protection against all credible threats, enhancing robustness of important safety systems and increasing redundancy of back-up power and water cooling systems, but also one of making certain that qualified and trained staff are supported by effective procedures. However, these assets are valued only in an organizational culture that places a premium on ensuring high levels of safety, or implementing what is called an effective “nuclear safety culture”. Principles, characteristics and factors for effective safety culture are to great extent similar between licencees and regulatory bodies and can be applied for developing RB’s safety. Safety is the primary purpose of the regulatory body, Regulator plays a significant role in the field of nuclear safety even though the prime responsibility for safety belongs to the operator, and it is the regulator which actually decides what is considered to be safe. In order to effectively implement the international principle of high level of nuclear safety, nuclear safety culture should be clearly named as an objective in international nuclear legal acts and the regulator’s responsibility for promotion of nuclear safety culture should be established. What is more difficult for the regulator is finding the right balance of firmness but fairness in dealing with the operator. In addition to enforcing safety regulations, the regulator should have a positive

Periodic Safety Review in Interim Storage Facilities - Current Regulation and Experiences in Germany

International Nuclear Information System (INIS)

Neles, Julia Mareike; Schmidt, Gerhard

2014-01-01

Periodic safety reviews in nuclear power plants in Germany have been performed since the end of the 1980's as an indirect follow-up of the accident in Chernobyl and, in the meantime, are formally required by law. During this process the guidelines governing this review were developed in stages and reached their final form in 1996. Interim storage facilities and other nuclear facilities at that time were not included, so the guidelines were solely focused on the specific safety issues of nuclear power plants. Following IAEA's recommendations, the Western European Nuclear Regulator Association (WENRA) introduced PSRs in its safety reference levels for storage facilities (current version in WGWD report 2.1 as of Feb 2011: SRLs 59 - 61). Based on these formulations, Germany improved its regulation in 2010 with a recommendation of the Nuclear Waste Management Commission (Entsorgungskommission, ESK), an expert advisory commission for the federal regulatory body BMU. The ESK formulated these detailed requirements in the 'ESK recommendation for guides to the performance of periodic safety reviews for interim storage facilities for irradiated fuel elements and heat-generating radioactive waste'. Before finalization of the guideline a test phase was introduced, aimed to test the new regulation in practice and to later include the lessons learned in the final formulation of the guideline. The two-year test phase started in October 2011 in which the performance of a PSR will be tested at two selected interim storage facilities. Currently these recommendations are discussed with interested/concerned institutions. The results of the test phase shall be considered for improvements of the draft and during the final preparation of guidelines. Currently the PSR for the first ISF is in an advanced stage, the second facility just started the process. Preliminary conclusions from the test phase show that the implementation of the draft guideline requires interpretation. The aim of a

Risk-based and deterministic regulation

International Nuclear Information System (INIS)

Fischer, L.E.; Brown, N.W.

1995-07-01

Both risk-based and deterministic methods are used for regulating the nuclear industry to protect the public safety and health from undue risk. The deterministic method is one where performance standards are specified for each kind of nuclear system or facility. The deterministic performance standards address normal operations and design basis events which include transient and accident conditions. The risk-based method uses probabilistic risk assessment methods to supplement the deterministic one by (1) addressing all possible events (including those beyond the design basis events), (2) using a systematic, logical process for identifying and evaluating accidents, and (3) considering alternative means to reduce accident frequency and/or consequences. Although both deterministic and risk-based methods have been successfully applied, there is need for a better understanding of their applications and supportive roles. This paper describes the relationship between the two methods and how they are used to develop and assess regulations in the nuclear industry. Preliminary guidance is suggested for determining the need for using risk based methods to supplement deterministic ones. However, it is recommended that more detailed guidance and criteria be developed for this purpose

Assessing risks and regulating safety standards in the oil and gas industry: the Peruvian experience.

OpenAIRE

Arturo Leonardo Vásquez Cordano; Julio Salvador Jácome; Raúl Lizardo García Carpio; Victor Fernández Guzman

2013-01-01

Environmental regulation has usually focused on controlling continuous sources of pollution such as CO2 emissions through carbon taxes. However, the 2010 oil spill in the Gulf of Mexico has shown that accidents associated to safety failures can also generate bursts of pollution with serious environmental consequences. Regulating safety conditions to prevent accidents in the oil and gas industry is challenging because public regulators cannot perfectly observe whether firms comply with safety ...

Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations

International Nuclear Information System (INIS)

2007-01-01

The major result of the work is the identification of consensus and common technical positions on a set of important licensing issues raised by the design and operation of computer-based systems used in Nuclear Power Plants for safety functions. The purpose is to introduce greater consistency and more mutual acceptance into current practices. To achieve these common positions, detailed consideration was paid to the licensing approaches followed in the different countries represented by the experts of the task force. The report is intended to be useful: - to coordinate regulators' and safety experts' technical viewpoints in the design of regulators' national policies and in revisions of guidelines; - as a reference in safety cases and demonstrations of safety of software based systems; - as guidance for system design specifications by manufacturers and major I and C suppliers on the international market. The task force decided at an early stage to focus attention on computer based systems used in Nuclear Power Plants for the implementation of safety functions; namely, those systems classified by the IAEA as 'Safety Systems'. Therefore, recommendations of this report - except those of chapter 1.11 - primarily address 'safety systems' and not 'safety related systems'. It was felt that the most difficult aspects of the licensing of digital programmable systems are rooted in the specific properties of the technology. The objective was therefore to delineate practical and technical licensing guidance, rather than discussing or proposing basic principles or requirements. The design requirements and the basic principles of nuclear safety in force in each member state are assumed to remain applicable. This report represents the consensus view achieved by the experts who contributed to the task force. It is the result of what was at the time of its initiation a first attempt at the international level to achieve consensus among nuclear regulators on practical methods for

The safety regulation of small-scale coal mines in China: Analysing the interests and influences of stakeholders

International Nuclear Information System (INIS)

Song, Xiaoqian; Mu, Xiaoyi

2013-01-01

Small scale coal mines (SCMs) have played an important role in China’s energy supply. At the same time, they also suffer from many social, economic, environmental, and safety problems. The Chinese government has made considerable efforts to strengthen the safety regulation of the coal mining industry. Yet, few of these efforts have proven to be very effective. This paper analyzes the interests and influences of key stakeholders in the safety regulation of SCMs, which includes the safety regulator, the local government, the mine owner, and mineworkers. We argue that the effective regulation of coal mine safety must both engage and empower mineworkers. - Highlights: ► Small scale coal mines have played an important role in China's energy supply. ► We analyze the interests and influences of key stakeholders in the safety regulation of small coal mines. ► The mineworkers have the strongest interest but least influence. ► An effective regulation must engage the mineworkers, organize, and empower them.

Safety regulation: The lessons of workplace safety rule management for managing the regulatory burden

OpenAIRE

Hale, A.R.; Borys, D.; Adams, M.

2012-01-01

There is a strong political consensus in a number of countries that occupational safety and health regulation is stifling industrial innovation and development and is feeding a culture of damaging risk aversion and petty bureaucracy. In a number of countries this has led to proposals to repeal regulations and reduce the regulatory burden. The authors were commissioned to prepare a discussion paper on this issue by the Mercatus Center of George Mason University in Arlington, Virginia, aimed pa...

NRC - regulator of nuclear safety

International Nuclear Information System (INIS)

1997-01-01

The U.S. Nuclear Regulatory Commission (NRC) was formed in 1975 to regulate the various commercial and institutional uses of nuclear energy, including nuclear power plants. The agency succeeded the Atomic Energy Commission, which previously had responsibility for both developing and regulating nuclear activities. Federal research and development work for all energy sources, as well as nuclear weapons production, is now conducted by the U.S. Department of Energy. Under its responsibility to protect public health and safety, the NRC has three principal regulatory functions: (1) establish standards and regulations, (2) issue licenses for nuclear facilities and users of nuclear materials, and (3) inspect facilities and users of nuclear materials to ensure compliance with the requirements. These regulatory functions relate to both nuclear power plants and to other uses of nuclear materials - like nuclear medicine programs at hospitals, academic activities at educational institutions, research work, and such industrial applications as gauges and testing equipment. The NRC places a high priority on keeping the public informed of its work. The agency recognizes the interest of citizens in what it does through such activities as maintaining public document rooms across the country and holding public hearings, public meetings in local areas, and discussions with individuals and organizations

Advisory material for the IAEA regulations for the safe transport of radioactive material. Safety guide

International Nuclear Information System (INIS)

2008-01-01

Since the first edition in 1961, the Regulations for the Safe Transport of Radioactive Material of the IAEA (IAEA Regulations) have served as the basis of safety for the transport of radioactive material worldwide. In the discussions leading to the first edition of the IAEA Regulations, it was realized that there was need for a publication to supplement the Regulations which could give information of individual provisions as to their purpose, their scientific background and how to apply them in practice. In response, the Agency published Safety Series No. 7, entitled, in its first edition in 1961, 'Notes on Certain Aspects of the Regulations'. An additional source of information on the Regulations, providing advice on 'how' the user should comply with them which could be augmented from time to time in the light of latest experience, was provided by the Agency, initially in relation to the 1973 edition of the Regulations. This was entitled 'Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material' and designated Safety Series No. 37. This document is the result of combining the two Safety Series in a single publication. Thus the primary purpose of this publication is to provide guidance to users on proven and acceptable ways of complying with the Regulations. This Advisory Material is not a stand-alone text and it only has significance when used as a companion to the IAEA Safety Standards Series No. ST-1, Regulations for the Safe Transport of Radioactive Material (1996 edition)

Improving construction site safety through leader-based verbal safety communication.

Science.gov (United States)

Kines, Pete; Andersen, Lars P S; Spangenberg, Soren; Mikkelsen, Kim L; Dyreborg, Johnny; Zohar, Dov

2010-10-01

The construction industry is one of the most injury-prone industries, in which production is usually prioritized over safety in daily on-site communication. Workers have an informal and oral culture of risk, in which safety is rarely openly expressed. This paper tests the effect of increasing leader-based on-site verbal safety communication on the level of safety and safety climate at construction sites. A pre-post intervention-control design with five construction work gangs is carried out. Foremen in two intervention groups are coached and given bi-weekly feedback about their daily verbal safety communications with their workers. Foremen-worker verbal safety exchanges (experience sampling method, n=1,693 interviews), construction site safety level (correct vs. incorrect, n=22,077 single observations), and safety climate (seven dimensions, n=105 questionnaires) are measured over a period of up to 42 weeks. Baseline measurements in the two intervention and three control groups reveal that foremen speak with their workers several times a day. Workers perceive safety as part of their verbal communication with their foremen in only 6-16% of exchanges, and the levels of safety at the sites range from 70-87% (correct observations). Measurements from baseline to follow-up in the two intervention groups reveal that safety communication between foremen and workers increases significantly in one of the groups (factor 7.1 increase), and a significant yet smaller increase is found when the two intervention groups are combined (factor 4.6). Significant increases in the level of safety are seen in both intervention groups (7% and 12% increases, respectively), particularly in regards to 'access ways' and 'railings and coverings' (39% and 84% increases, respectively). Increases in safety climate are seen in only one of the intervention groups with respect to their 'attention to safety.' No significant trend changes are seen in the three control groups on any of the three measures

Safety practice and regulations in different IGORR member countries

International Nuclear Information System (INIS)

Hickman, C.; Minguet, J.L.; Arnould, F.

1999-01-01

In the suggestions of the 1996 IGORR 5 conference, Technicatome proposed 'Comparing Regulations for Research Reactors in Participating Countries'. The aim was to enhance and facilitate the dissemination of pertinent information amongst potential utilities of operational research reactors. A questionnaire on the following topics was subsequently sent out to IGORR 5 participants : Procedures for Research Reactors and Associated Equipment, Safety Analysis, Safety Related Components, Radiation Protection and Management of Nuclear materials. The objective of the present paper is to identify major trends, similarities and differences in the approaches adopted by different countries. Its scope has been limited to: Licensing and Regulatory approach; Operating and Safety documents; Safety Analysis; Radiological Safety; Management of Nuclear Materials. The investigations carried out indicate that to a large extent international recommendations (IAEA, ICPR,..) are being followed and that there is a general tendency to integrate them into national legislation and regulations. Although Safety Culture varies from one country to another an overall general consensus exists on the basic approach to safety inasmuch as: different countries have their own legally defined Safety Authorities, a Preliminary Safety Report is required before a research reactor can be built, and a final Safety Report before the core can be loaded with nuclear fuel and the reactor made critical; these documents must be accepted by the Safety Authorities concerned; a combination of defense-in-depth strategy (deterministic approach) and probabilistic analysis is applied; three or more safety classes are used to categorize systems and components; the single failure criterion is taken into consideration for systems and components having safety functions; both Operating Basis and Safety Shutdown type earthquakes are considered; the crashing of an aircraft onto a research reactor is taken into consideration

Future regulatory research needs on risk-informed and performance-based regulation

International Nuclear Information System (INIS)

Kim, Wong Sik; Kim, Hho Jung

2004-01-01

The USNRC has pursued the incorporation of risk-informed and performance-based regulation (RIPBR) into nuclear safety regulatory system, as an alternative to improve existing nuclear safety regulation of nuclear power plants, which is deterministic and prescriptive. It focuses on the use of risk insight from probabilistic safety assessment (PSA). Recently, it becomes necessary to find a way to improve regulatory efficiency and effectiveness in order to cover the increasing regulatory needs in Korea. Also, the utility has optimized design and operation of the plant using PSA insight and equipment performance information. According to the increase of the necessity for regulatory improvement using risk and performance information, KINS (Korea Institute of Nuclear Safety) is developing, as a part of a mid and long-term project of Nuclear R and D program, how to adopt the RIPBR in Korean nuclear regulatory system. As the interim results, three basic directions and several principles that are necessary to implement RIPBR model were already identified from the previous study. This paper suggests a direction to future regulatory research on RIPBR based on the previous studies including the review of international trend of RIPBR and the evaluation of risk-informed regulatory environment

Nuclear safety regulation in the People's Republic of China

International Nuclear Information System (INIS)

Shi Guangchang

1987-01-01

The present report gives a general view of how the problem of nuclear safety is dealt with in China, with particular reference to the nuclear power plants. The most relevant nuclear legal regulations and procedures are reported. Organization of the National Nuclear Safety Administration (NNSA) of China and its working activities are presented. The report gives also the principle and practice with regard to licensing process and regulatory inspection of nuclear power plant in China. (author)

Trends in food safety standards and regulation implications for developing countries

OpenAIRE

Caswell, Julie A.

2003-01-01

"Food safety is affected by the decisions of producers, processors, distributors, food service operators, and consumers, as well as by government regulations. In developed countries, the demand for higher levels of food safety has led to the implementation of regulatory programs that address more types of safety-related attributes (such as bovine spongiform encephalopathy (BSE), microbial pathogens, environmental contaminants, and animal drug and pesticide residues) and impose stricter standa...

Development of measures to assess the safety of existing NPPs and the effectiveness of regulations and regulatory actions (including 'prescriptive' and 'performance based' approaches). Peer discussions on regulatory practices

International Nuclear Information System (INIS)

1996-09-01

This report arises from the fourth series of peer discussions on regulatory practices entitled D evelopment of measures to assess the safety of existing nuclear power plants and the effectiveness of regulations and regulatory actions (including 'prescriptive' and 'performance based' approaches) . Senior regulators from 23 Member States participated in four peer group discussions during 1995-1996. This report presents the outcome of these meetings and recommendations of good practices identified by these senior regulators. The purpose of this report is to disseminate the views which the senior regulators presented at the meetings relating to measures used for assessing the safety of existing nuclear power plants and evaluating the effectiveness of regulators and regulatory actions. The intention in doing this is to assist Member States in the enhancement of their regulatory practices by identifying commonly accepted good practices. This report is structured so that it covers the subject matter under the following main headings: 'Prescriptive and Performance Based' Approaches to Regulation; Common Features of Regulatory Approaches; Effectiveness of the Regulator and Regulatory Actions; Recommendations of Good Practice. It is important to note that recommendations of good practice are included if they have been identified by at least one of the groups. It does not follow that all of the groups or individual Member States would necessarily endorse all of the recommendations. However, it is considered that if a single group of senior regulators judge that a particular practice is worthy of recommendation then it should be included for serious consideration. In some cases the same recommendations arise from all of the Groups

[Problems of safety regulation under radioactive waste management in Russia].

Science.gov (United States)

Monastyrskaia, S G; Kochetkov, O A; Barchukov, V G; Kuznetsova, L I

2012-01-01

Analysis of the requirements of Federal Law N 190 "About radioactive waste management and incorporation of changes into some legislative acts of the Russian Federation", as well as normative-legislative documents actual and planned to be published related to provision of radiation protection of the workers and the public have been done. Problems of safety regulation raised due to different approaches of Rospotrebnadzor, FMBA of Russia, Rostekhnadzor and Minprirody with respect to classification and categorization of the radioactive wastes, disposal, exemption from regulatory control, etc. have been discussed in the paper. Proposals regarding improvement of the system of safety regulation under radioactive waste management and of cooperation of various regulatory bodies have been formulated.

Risk-based safety indicators

International Nuclear Information System (INIS)

Szikszai, T.

1997-01-01

The presentation discusses the following issues: The objectives of the risk-based indicator programme. The characteristics of the risk-based indicators. The objectives of risk-based safety indicators - in monitoring safety; in PSA applications. What indicators? How to produce the risk based indicators? PSA requirements

Analysis of Driving Safety Criteria Based on National Regulations for the Suspension Systems of NGVs

Directory of Open Access Journals (Sweden)

Ronald Mauricio Martinod

2015-01-01

Full Text Available The work analyses the technical evaluation process of the suspension system for vehicles that have been adapted to natural-gas-fuelled engines from power light-duty gasoline, and diesel vehicles; this evaluation is done through a mechanical review established by national regulations. The development of this analysis is focused on establishing the relationship between the natural-gas-fuelled equipment and the dynamic effect caused by the extra-weight, according to two measuring criteria that determine the safety and driving comfort, these are: (i tire-road adhesion index; and (ii tire excitation phase angle. The paper also proposes new elements that can be added to the current national regulations and that are currently applied to assess the suspension of natural gas vehicles, recorded using a test standard benchmark for the evaluation of the suspension.

Integrating environmental management into food safety and food packaging in Malaysia: review of the food regulation 1985

Science.gov (United States)

Nordin, N. H.; Hara, H.; Kaida, N.

2017-05-01

Food safety is an important issue that is related to public safety to prevent the toxicity threats of the food. Management through legal approach has been used in Malaysia as one of the predominant approaches to manage the environment. In this regard, the Food Regulation 1985 has been one of the mechanisms of environmental management through legal approach in controlling the safety of packaged food in food packaging industry in Malaysia. The present study aims to analyse and to explain the implementation of the Food Regulation 1985 in controlling the safety of packaged food in Malaysia and to integrate the concept of environmental management into the food safety issue. Qualitative analysis on the regulation document revealed that there are two main themes, general and specific, while their seven sub themes are included harmful packages, safety packages, reuse packages, polyvinyl chloride (PVC), alcoholic bottle, toys, money and others and iron powder. The implementation of the Food Regulation 1985 in controlling the safety of packaged food should not be regarded solely for regulation purposes but should be further developed for a broader sense of food safety from overcoming the food poisoning.

The software safety analysis based on SFTA for reactor power regulating system in nuclear power plant

International Nuclear Information System (INIS)

Liu Zhaohui; Yang Xiaohua; Liao Longtao; Wu Zhiqiang

2015-01-01

The digitalized Instrumentation and Control (I and C) system of Nuclear power plants can provide many advantages. However, digital control systems induce new failure modes that differ from those of analog control systems. While the cost effectiveness and flexibility of software is widely recognized, it is very difficult to achieve and prove high levels of dependability and safety assurance for the functions performed by process control software, due to the very flexibility and potential complexity of the software itself. Software safety analysis (SSA) was one way to improve the software safety by identify the system hazards caused by software failure. This paper describes the application of a software fault tree analysis (SFTA) at the software design phase. At first, we evaluate all the software modules of the reactor power regulating system in nuclear power plant and identify various hazards. The SFTA was applied to some critical modules selected from the previous step. At last, we get some new hazards that had not been identified in the prior processes of the document evaluation which were helpful for our design. (author)

Consideration of timescales in the finnish safety regulations for spent fuel disposal

International Nuclear Information System (INIS)

Ruokola, E.

2010-01-01

Esko Ruokola (STUK) presented an example of regulatory approach and explained that the Finnish spent fuel disposal program is progressing towards the construction license stage. The Government Decree on the Safety of Nuclear Waste Disposal which entered into force on 1 St December 2008 will be detailed by a STUK Guide that is currently being updated. These regulations distinguish three post-closure time periods for which different safety criteria are defined: The Environmentally Predictable Future: During this first period, extending up to several thousands of years, predictable environmental changes will occur. People may be exposed to the disposed radioactive substances only due to limited early failures of engineered barriers, due to e.g. fabrication defects. Disposal shall be so designed that as a consequence of expected evolutions: 1. The annual dose to the most exposed members of the public shall remain below 0.1 mSv. 2. The average annual doses to other members of the public shall remain insignificantly low. STUK provides guidance for the different elements of the safety assessment including potential exposure pathways, potential changes in the environment to be considered, assumption on climate change and human habits, as well as the reference conditions for the most exposed individual and people living in the surroundings. Era of Extreme Climate Changes: Beyond about 10 000 years, great climatic changes, such as permafrost and glaciation, will occur and a conservative approach is followed. For this time period, the radiation protection criteria are based on release rates of radionuclides from the geosphere to biosphere (geo-bio flux constraints). The STUK guide specifies the nuclide specific constraints for the activity release to the environment for individual radionuclides. The selected approach by STUK implies that the implementer need not to consider the biosphere scenarios when preparing his safety case for the time period discussed as the regulator

The development of regulatory expectations for computer-based safety systems for the UK nuclear programme

Energy Technology Data Exchange (ETDEWEB)

Hughes, P. J. [HM Nuclear Installations Inspectorate Marine Engineering Submarines Defence Nuclear Safety Regulator Serco Assurance Redgrave Court, Merton Road, Bootle L20 7HS (United Kingdom); Westwood, R.N; Mark, R. T. [FLEET HQ, Leach Building, Whale Island, Portsmouth, PO2 8BY (United Kingdom); Tapping, K. [Serco Assurance,Thomson House, Risley, Warrington, WA3 6GA (United Kingdom)

2006-07-01

The Nuclear Installations Inspectorate (NII) of the UK's Health and Safety Executive (HSE) has completed a review of their Safety Assessment Principles (SAPs) for Nuclear Installations recently. During the period of the SAPs review in 2004-2005 the designers of future UK naval reactor plant were optioneering the control and protection systems that might be implemented. Because there was insufficient regulatory guidance available in the naval sector to support this activity the Defence Nuclear Safety Regulator (DNSR) invited the NII to collaborate with the production of a guidance document that provides clarity of regulatory expectations for the production of safety cases for computer based safety systems. A key part of producing regulatory expectations was identifying the relevant extant standards and sector guidance that reflect good practice. The three principal sources of such good practice were: IAEA Safety Guide NS-G-1.1 (Software for Computer Based Systems Important to Safety in Nuclear Power Plants), European Commission consensus document (Common Position of European Nuclear Regulators for the Licensing of Safety Critical Software for Nuclear Reactors) and IEC nuclear sector standards such as IEC60880. A common understanding has been achieved between the NII and DNSR and regulatory guidance developed which will be used by both NII and DNSR in the assessment of computer-based safety systems and in the further development of more detailed joint technical assessment guidance for both regulatory organisations. (authors)

Environmental Regulation and Food Safety: Studies of Protection ...

International Development Research Centre (IDRC) Digital Library (Canada)

1 janv. 2006 ... Environmental Regulation and Food Safety intéressera les artisans des politiques et les ONG , les chercheurs et les spécialistes de l'économie ... This funding will help strengthen the Science, Technology and Innovation Policy Research Organization's (STIPRO) role as a credible public policy institution in ...

Safety management and control policy. A study of the safety regulation of offshore oil activity by the Norwegian Petroleum Directorate. Sikkerhetsstyring og reguleringsteknikk. Oljedirektoratets regulering av sikkerheten ved produksjon av petroleum

Energy Technology Data Exchange (ETDEWEB)

Graver, H P

1983-01-01

The Norwegian Petroleum Directorate (NPD) is the main administrative body with responsibility to regulate and control the safety aspects of drilling for and production of petroleum on the Norwegian Continental Shelf. Its responsibility does not, however, include the aspects of maritime safety, which are regulated by the Norwegian Maritime Directorate. This study is limited to the regulation of safety on fixed installations for production of petroleum. The object has been to describe the methods applied by the NPD to achieve better safety, and to give answers to why these specific methods of approach have developed as they have. A conclusion that may be drawn from this study is that there exists a relationship of close cooperation between the NPD and the oil industry represented by the operating companies. Only this can explain the differences we find in the NPD approach as compared to the approach of other parts of public administration. Such a relationship probably leads to better safety within the scope of technical rationality than would have a more hostile relationship between the Directorate and the industry. This has its price, however. Aspects of the safety question not included within the limits of a purely technical approach are not as easily taken into account. Partly due to this fact, other parties with interests in safety are not represented.

Safety regulation : The lessons of workplace safety rule management for managing the regulatory burden

NARCIS (Netherlands)

Hale, A.R.; Borys, D.; Adams, M.

2012-01-01

There is a strong political consensus in a number of countries that occupational safety and health regulation is stifling industrial innovation and development and is feeding a culture of damaging risk aversion and petty bureaucracy. In a number of countries this has led to proposals to repeal

Radiation sources safety and radioactive materials security regulation in Ukraine

International Nuclear Information System (INIS)

Smyshliaiev, A.; Holubiev, V.; Makarovska, O.

2001-01-01

Radiation sources are widely used in Ukraine. There are about 2500 users in industry, science, education and about 2800 in medicine. About 80,000 sealed radiation sources with total kerma-equivalent of 450 Gy*M 2 /sec are used in Ukraine. The exact information about the radiation sources and their users will be provided in 2001 after the expected completion of the State inventory of radiation sources in Ukraine. In order to ensure radiation source safety in Ukraine, a State System for regulation of activities dealing with radiation sources has been established. The system includes the following elements: establishment of norms, rules and standards of radiation safety; authorization activity, i.e. issuance of permits (including those in the form of licences) for activities dealing with radiation sources; supervisory activity, i.e. control over observance of norms, rules and standards of radiation safety and fulfilment of conditions of licences for activities dealing with radiation sources, and also enforcement. Comprehensive nuclear legislation was developed and implemented from 1991 to 2000. Radiation source safety is regulated by three main nuclear laws in Ukraine: On the use of nuclear energy and radiation safety (passed on 8 February 1995); On Human Protection from Impact of Ionizing Radiation (passed on 14 January 1998); On permissive activity in the area of nuclear energy utilization (passed on 11 January 2000). The regulatory authorities in Ukraine are the Ministry for Ecology and Natural Resources (Nuclear Regulatory Department) and the Ministry of Health (State sanitary-epidemiology supervision). According to the legislation, activities dealing with radiation sources are forbidden without an officially issued permit in Ukraine. Permitted activities with radiation sources are envisaged: licensing of production, storage and maintenance of radiation sources; licensing of the use of radiation sources; obligatory certification of radiation sources and transport

Preparing Safety Cases for Operating Outside Prescriptive Fatigue Risk Management Regulations.

Science.gov (United States)

Gander, Philippa; Mangie, Jim; Wu, Lora; van den Berg, Margo; Signal, Leigh; Phillips, Adrienne

2017-07-01

Transport operators seeking to operate outside prescriptive fatigue management regulations are typically required to present a safety case justifying how they will manage the associated risk. This paper details a method for constructing a successful safety case. The method includes four elements: 1) scope (prescriptive rules and operations affected); 2) risk assessment; 3) risk mitigation strategies; and 4) monitoring ongoing risk. A successful safety case illustrates this method. It enables landing pilots in 3-pilot crews to choose the second or third in-flight rest break, rather than the regulatory requirement to take the third break. Scope was defined using a month of scheduled flights that would be covered (N = 4151). These were analyzed in the risk assessment using existing literature on factors affecting fatigue to estimate the maximum time awake at top of descent and sleep opportunities in each break. Additionally, limited data collected before the new regulations showed that pilots flying at landing chose the third break on only 6% of flights. A prospective survey comparing subjective reports (N = 280) of sleep in the second vs. third break and fatigue and sleepiness ratings at top of descent confirmed that the third break is not consistently superior. The safety case also summarized established systems for fatigue monitoring, risk assessment and hazard identification, and multiple fatigue mitigation strategies that are in place. Other successful safety cases have used this method. The evidence required depends on the expected level of risk and should evolve as experience with fatigue risk management systems builds.Gander P, Mangie J, Wu L, van den Berg M, Signal L, Phillips A. Preparing safety cases for operating outside prescriptive fatigue risk management regulations. Aerosp Med Hum Perform. 2017; 88(7):688-696.

Basic concept on safety regulation for land disposal of low level radioactive solid wastes

International Nuclear Information System (INIS)

1985-01-01

As to the land disposal of low level radioactive solid wastes, to which the countermeasures have become the urgent problem at present, it is considered to be a realistic method to finally store the solid wastes concentratedly outside the sites of nuclear power stations and others, and effort has been exerted by those concerned to realize it. Besides, as for extremely low level radioactive solid wastes, the measures of disposing them corresponding to the radioactivity level are necessary, and the concrete method has been examined. The Committee on Safety Regulation for Radioactive Wastes has discussed the safety regulation for those since April, 1984, and the basic concept on the safety regulation was worked up. It is expected that the safety of the land disposal of low level radioactive solid wastes can be ensured when the safety regulation is carried out in conformity with this basic concept. The present status of the countermeasures to the land disposal of low level radioactive solid wastes is shown. As the concrete method, the disposal in shallow strate has been generally adopted. At present, the plan for the final storage in Aomori Prefecture is considered, and it will be started with the first stage of four-stage control. (Kako, I.)

Regulatory risks associated with nuclear safety legislation after Fukushima Daiichi Nuclear Accident in Japan. Focus on legal structure of the nuclear reactor regulation act

International Nuclear Information System (INIS)

Tanabe, Tomoyuki; Maruyama, Masahiro

2016-01-01

Nuclear safety regulations enforced after Fukushima Daiichi Nuclear Accident under the Nuclear Reactor Regulation Act face the following regulatory problems that involve potential risk factors for nuclear businesses; 1) 'entity based regulation' unable to cope with business cessation or bankruptcy of the entity subject of regulation, 2) potential risk of the Nuclear Regulation Authority's inappropriate involvement in nuclear industry policy beyond their duty, and 3) compliance of backfits under vague regulations. In order to alleviate them, this report, through analyzing these regulatory problems from the view point of sound development of the nuclear industry, proposes the following regulatory reforms; (1) To clarify the rule for industry policy in nuclear regulations and enable the authority, Ministry of Economy, Trade and Industry, to choose most appropriate industrial policy measure. (2) Through establishing safety goals as measures to promote continuous improvement of nuclear safety regulations, to stimulate timely adjustments of the regulations, and to introduce a legal mechanism into the nuclear regulation systems under which validity of administrative law and its application can be checked. (author)

77 FR 6007 - Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation...

Science.gov (United States)

2012-02-07

...] Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation... they could be published in the Federal Register. This notice lists temporary safety zones, security... the safety and security needs within their jurisdiction; therefore, District Commanders and COTPs have...

33 CFR 165.117 - Regulated Navigation Areas, Safety and Security Zones: Deepwater Ports, First Coast Guard District.

Science.gov (United States)

2010-07-01

..., Safety and Security Zones: Deepwater Ports, First Coast Guard District. 165.117 Section 165.117... Limited Access Areas First Coast Guard District § 165.117 Regulated Navigation Areas, Safety and Security... section are designated as regulated navigation areas. (2) Safety and security zones. All waters within a...

Risk-based safety indicators

International Nuclear Information System (INIS)

Sedlak, J.

2001-12-01

The report is structured as follows: 1. Risk-based safety indicators: Typology of risk-based indicators (RBIs); Tools for defining RBIs; Requirements for the PSA model; Data sources for RBIs; Types of risks monitored; RBIs and operational safety indicators; Feedback from operating experience; PSO model modification for RBIs; RBI categorization; RBI assessment; RBI applications; Suitable RBI applications. 2. Proposal for risk-based indicators: Acquiring information from operational experience; Method of acquiring safety relevance coefficients for the systems from a PSA model; Indicator definitions; On-line indicators. 3. Annex: Application of RBIs worldwide. (P.A.)

GENERAL CONSIDERATIONS ON REGULATIONS AND SAFETY REQUIREMENTS FOR QUADRICYCLES

Directory of Open Access Journals (Sweden)

Ana Pavlovic

2015-12-01

Full Text Available In recent years, a new class of compact vehicles has been emerging and wide-spreading all around Europe: the quadricycle. These four-wheeled motor vehicles, originally derived from motorcycles, are a small and fuel-efficient mean of transportation used in rural or urban areas as an alternative to motorbikes or city cars. In some countries, they are also endorsed by local authorities and institutions which support small and environmentally-friendly vehicles. In this paper, several general considerations on quadricycles will be provided including the vehicle classification, evolution of regulations (as homologation, driver licence, emissions, etc, technical characteristics, safety requirements, most relevant investigations, and other additional useful information (e.g. references, links. It represents an important and actual topic of investigation for designers and manufacturers considering that the new EU regulation on the approval and market surveillance of quadricycles will soon enter in force providing conclusive requirements for functional safety environmental protection of these promising vehicles.

76 FR 70342 - Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation...

Science.gov (United States)

2011-11-14

...] Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation... published in the Federal Register. This notice lists temporary safety zones, security zones, special local... Commanders and Captains of the Port (COTP) must be immediately responsive to the safety and security needs...

The safety and regulation of natural products used as foods and food ingredients.

Science.gov (United States)

Abdel-Rahman, Ali; Anyangwe, Njwen; Carlacci, Louis; Casper, Steve; Danam, Rebecca P; Enongene, Evaristus; Erives, Gladys; Fabricant, Daniel; Gudi, Ramadevi; Hilmas, Corey J; Hines, Fred; Howard, Paul; Levy, Dan; Lin, Ying; Moore, Robert J; Pfeiler, Erika; Thurmond, T Scott; Turujman, Saleh; Walker, Nigel J

2011-10-01

The use of botanicals and dietary supplements derived from natural substances as an adjunct to an improved quality of life or for their purported medical benefits has become increasingly common in the United States. This review addresses the safety assessment and regulation of food products containing these substances by the U.S. Food and Drug Administration (FDA). The issue of safety is particularly critical given how little information is available on the toxicity of some of these products. The first section uses case studies for stevia and green tea extracts as examples of how FDA evaluates the safety of botanical and herbal products submitted for consideration as Generally Recognized as Safe under the Federal Food, Drug, and Cosmetics Act. The 1994 Dietary Supplement Health Education Act (DSHEA) created a regulatory framework for dietary supplements. The article also discusses the regulation of this class of dietary supplements under DSHEA and addresses the FDA experience in analyzing the safety of natural ingredients described in pre-market safety submissions. Lastly, we discuss an ongoing interagency collaboration to conduct safety testing of nominated dietary supplements.

Patient safety issues in office-based surgery and anaesthesia in Switzerland: a qualitative study.

Science.gov (United States)

McLennan, Stuart; Schwappach, David; Harder, Yves; Staender, Sven; Elger, Bernice

2017-08-01

To identify the spectrum of patient safety issues in office-based surgery and anaesthesia in Switzerland. Purposive sample of 23 experts in surgery and anaesthesia and quality and regulation in Switzerland. Data were collected via individual qualitative interviews using a researcher-developed semi-structured interview guide between March 2016 and September 2016. Interviews were transcribed and analysed using conventional content analysis. Issues were categorised under the headings "structure", "process", and "outcome". Experts identified two key overarching patient safety and regulatory issues in relation to office-based surgery and anaesthesia in Switzerland. First, experts repeatedly raised the current lack of data and transparency of the setting. It is unknown how many surgeons are operating in offices, how many and what types of operations are being done, and what the outcomes are. Secondly, experts also noted the limited oversight and regulation of the setting. While some standards exists, most experts felt that more minimal safety standards are needed regarding the requirements that must be met to do office-based surgery and what can and cannot be done in the office-based setting are needed, but they advocated a self-regulatory approach. There is a lack of empirical data regarding the quantity and quality office-based surgery and anaesthesia in Switzerland. Further research is needed to address these research gaps and inform health policy in relation to patient safety in office-based surgery and anaesthesia in Switzerland. Copyright © 2017. Published by Elsevier GmbH.

Sor/88-391, 21 July 1988, uranium mines (Ontario) occupational health and safety regulations, amendment

International Nuclear Information System (INIS)

1988-08-01

These Regulations (SOR/84-435) were made to establish uniformity in the laws governing occupational health and safety in mines in the Province of Ontario. To ensure conformity, the legal references in the Regulations have been amended to accord with the 1987 amendment of the Ontario Occupational Health and Safety Act [fr

A direction to adopting risk-informed and performance-based regulation (RIPBR) in Korea

International Nuclear Information System (INIS)

Kim, W.S.; Sung, K.Y.; Lee, C.J.; Choi, Y.H.; Choi, Y.S.; Kim, H.J.

2004-01-01

The USNRC has pursued the incorporation of new regulatory approach of risk-informed and performance-based regulation (RIPBR) into nuclear safety regulation, as an alternative to improve existing nuclear safety regulation of nuclear power plants, which is deterministic and prescriptive. It focuses on the use of risk insight from probabilistic safety assessment (PSA). Recently, it becomes necessary to find a way to improve regulatory efficiency and effectiveness in order to cover the increasing regulatory needs in Korea. Also, the utility has optimized design and operation of the plant using PSA insight and equipment performance information. According to the increase of the necessity for regulatory improvement using risk and performance information, KINS (Korea Institute of Nuclear Safety) is developing, as a part of mid- and long-term project of Nuclear development program, how to adopt the RIPBR in Korean nuclear regulation. This paper presents the interim result of the study that comprises the assessment of feasibility to adopt the RIPBR, and basic directions and principles for implementing RIPBR model. It is concluded that adopting RIPBR is essential for risk management of the plant, public acceptance to nuclear safety, improvement of existing regulation, minimization of unnecessary regulatory burden, and effective use of regulatory resources, etc. Three basic directions and several principles that are necessary to implement RIPBR model are identified from the study. The application of the directions and principles to the assessment of RIPBR model to be established in the near future is expected to result in making the adoption of new regulatory system more objective and consistent. (authors)

The most prominent safety guarantees

International Nuclear Information System (INIS)

Lucenet, G.

1978-01-01

The Creys-Malville Nuclear Centre has been designed using the safety analysis implemented since the beginning of the developments of breeder reactors in France and the Super Phenix follows almost the same safety regulations as its predecessor the Phenix reactor. These regulations are based on: 'Recommendations for the safety standards of the Super Phenix' drawn up by the French Safety Authorities in July 1973. The prominent points are summarised. (C.F.)

Coal Mine Health and Safety Regulation 2006 under the Coal Mine Health and Safety Act 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-12-22

The aim of the Act is to secure the health, safety and welfare of people in connection with coal operations (which include all places of work where coal is mined and certain other places). The Regulation contains provisions about the following matters: (a) places of work to which the Act does not apply, (b) duties relating to health, welfare and safety at coal operations, including the following: (i) the nomination of the operator of a coal operation and the provision of health and safety information for incoming operators, (ii) the contents of health and safety management systems for coal operations, (iii) major hazards and the contents of major hazard management plans for coal operations, (iv) duties relating to contractors, (v) the contents of management structures and emergency management systems for coal operations, escape and rescue plans and fire fighting plans and high risk activities, (c) notifications, including (i) notification of incidents, (ii) inquiries, (iii) notification of other matters to the Chief Inspector), (d) aspects of safety at coal operations, including the following: (i) controlled materials, plants and practices, (ii) coal dust explosion prevention and suppression, (iii) ventilation at coal operations, (iv) escape from coal operations, (v) the operation of transport at coal operations, (vi) surveys and certified plans, (vii) employment at coal operations, (e) the licensing of certain activities, (f) competence standards, (g) the Coal Competence Board, (h) check inspectors, (i) exemptions from provisions of this Regulation, (j) the following miscellaneous matters concerning coal mine health and safety: (i) the keeping of records and reporting, (ii) penalties, the review of decisions by the Administrative Decisions Tribunal, fees and charges, consultation, information and other miscellaneous matters, (k) savings and transitional provisions.

The role of the regulator in promoting and evaluating safety culture. Operating experience feedback programme approach

International Nuclear Information System (INIS)

Perez, S.

2002-01-01

Promoting and Evaluating Safety Culture (S.C.) in Operating Organizations must be one of the main Nuclear Regulator goals to achieve. This can be possible only if each and every one of the regulatory activities inherently involves S.C. It can be seen throughout attitudes, values, uses and practices in both individuals and the whole regulatory organization. One among all the regulatory tools commonly used by regulators to promote and evaluate the commitment of the licensees with safety culture as a whole involves organizational factors and particular attention is directed to the operating organization. This entailed a wide range of activities, including all those related with management of safety performance. Operating Experience Feedback Programme as a tool to enhance safety operation is particularly useful for regulators in the evaluation of the role of S.C. in operating organization. Safety Culture is recognized as a subset of the wider Organizational Culture. Practices that improve organizational effectiveness can also contribute to enhance safety. An effective event investigation methodology is a specific practice, which contributes to a healthy Safety Culture. (author)

Practice specific model regulations: Radiation safety of non-medical irradiation facilities. Interim report for comment

International Nuclear Information System (INIS)

2003-08-01

The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (Standards or BSS) were published as IAEA Safety Series No. 115 in 1996. This publication is the culmination of efforts over the past decades towards harmonization of radiation protection and safety standards internationally, and is jointly sponsored by the Food and Agriculture Organisation of the United Nations (FAO), the International Atomic Energy Agency (IAEA), the International Labour Organisation (ILO), the OECD Nuclear Energy Agency (OECD/NEA), the Pan American Health Organisation (PAHO) and the World Health Organisation (WHO). The purpose of the Standards is to establish basic requirements for protection against the risks associated with exposure to ionizing radiation and for the safety of radiation sources that may deliver such exposure (hereinafter called 'radiation safety'). The requirements are based on the principles set out in the Safety Fundamentals, published as IAEA Safety Series Nos 110 and 120. The Standards can be implemented only through an effective radiation safety infrastructure that includes adequate laws and regulations, an efficient regulatory system, supporting experts and services, and a 'safety culture' shared by all those with responsibilities for protection, including both management and workers. IAEA-TECDOC-1067, Organization and Implementation of a National Regulatory Infrastructure Governing Protection against Ionizing Radiation and the Safety of Radiation Sources, provides detailed guidance on how to establish or improve national radiation safety infrastructure in order to implement the requirements of the Standards. The TECDOC covers the elements of a radiation safety infrastructure at the national level needed to apply the Standards to radiation sources such as those used in medicine, agriculture, research, industry and education. It also provides advice on approaches to the organization and operation of

Investigation on regulatory requirements for radiation safety management

International Nuclear Information System (INIS)

Han, Eun Ok; Choi, Yoon Seok; Cho, Dae Hyung

2013-01-01

NRC recognizes that efficient management of radiation safety plan is an important factor to achieve radiation safety service. In case of Korea, the contents to perform the actual radiation safety management are legally contained in radiation safety management reports based on the Nuclear Safety Act. It is to prioritize the importance of safety regulations in each sector in accordance with the current situation of radiation and radioactive isotopes-used industry and to provide a basis for deriving safety requirements and safety regulations system maintenance by the priority of radiation safety management regulations. It would be helpful to achieve regulations to conform to reality based on international standards if consistent safety requirements is developed for domestic users, national standards and international standards on the basis of the results of questions answered by radiation safety managers, who lead on-site radiation safety management, about the priority of important factors in radioactive sources use, sales, production, moving user companies, to check whether derived configuration requirements for radiation safety management are suitable for domestic status

Efficacy of Web-Based Instruction to Provide Training on Federal Motor Carrier Safety Regulations

Science.gov (United States)

2011-05-01

This report presents an evaluation of the current state-of-the-art Web-based instruction (WBI), reviews the current computer platforms of potential users of WBI, reviews the current status of WBI applications for Federal Motor Carrier Safety Administ...

SAFETY ASSESSMENT AND LIABILITY REGULATIONS IN THE CONTEXT OF GENETICALLY MODIFIED FOOD IN THE BRICS COUNTRIES

Directory of Open Access Journals (Sweden)

Sh. K. Balashanmugam

2018-01-01

Full Text Available International trade of food products is expected to increase rapidly with the widespread introduction of genetically modified (GM food. There will be greater participation of developing countries based on investment as well as research and development. Investment in research and development and commercial production of GM crops is high in Asia, particularly in India and China, but also in Latin American countries, such as Brazil, and on the African continent, especially in South Africa. Despite the merits, the introduction of GM foods in the world market has continued to raise public concerns touching upon health, legal, social, ethical and environmental issues. Especially, the issue of contamination is considered asignificant threat at many stages of development of GM food. Transboundary aspects and certain aspects of the components of the food safety system such as safety assessment, liability and redress are still not completely addressed. The present study is the systematic review of the extent of the development of legislation and institutional mechanisms in relation to safety assessment and liability mechanisms for regulating the emerging GM foods in the developing countries of BRICS. Additionally, the comparison of the components of national food safety systems of Brazil, Russia, India, China and South Africa reveals differences in policy and regulation in relation to GM food.

Harmonization of nuclear and radiation safety regulations for nuclear power plants with reference levels of Western European Nuclear Regulators Association (WENRA)

International Nuclear Information System (INIS)

Bojchuk, V.S.; Mikolajchuk, O.A.; Gromov, G.V.; Dibach, O.M.; Godovanyuk, G.M.; Nosovs'kij, A.V.

2014-01-01

Self-evaluation of the Ukrainian regulations on nuclear and radiation safety that apply to nuclear power plants for compliance with the reference levels of the Western European Nuclear Regulators Association (WENRA) is presented. Proposals on improvement of the regulations upon self-evaluation are provided

INFLUENCE OF PLANNING, ORGANIZATIONAL CHARACTERISTICS AND REGULATION ON ROAD TRAFFIC SAFETY OF PEDESTRIANS

Directory of Open Access Journals (Sweden)

G. M. Kuharenok

2011-01-01

Full Text Available The paper presents results of research on planning, organizational characteristics and regulation modes at  the regulated pedestrian crossings, located out of crossroads in the street and road network of Minsk. Some regularities pertaining to the influence of the investigated characteristics on road traffic safety of pedestrians are revealed in the paper. Practical offers on increase of road traffic safety of pedestrians in the Republic of Belarus have been developed on the basis of the executed investigations and cited in the paper. 

Providing current radiation safety according to new version of 'Ukrytie' object regulation

International Nuclear Information System (INIS)

Borovoj, A.A.; Vysotskij, E.D.; Krinitsyn, A.P.; Bogatov, S.A.

1999-01-01

Main provisions are given of the 'Ukryttia' object's Regulation related to provision of radiation safety during the object's operation. The safety is provided due to the realization by the object's personnel of functions of global monitoring of current radiation conditions, as well as of the measures of operative or preventive suppression of radiation abnormalities sources

Transports of radioactive materials. Legal regulations, safety and security concepts, experience

International Nuclear Information System (INIS)

Schwarz, Guenther

2012-01-01

In Germany, approximately 650,000 to 750,000 units containing radioactive materials for scientific, medical and technical applications are shipped annually by surface, air and water transports. Legally speaking, radioactive materials are dangerous goods which can cause hazards to life, health, property and the environment as a result of faulty handling or accidents in transit. For protection against these hazards, their shipment therefore is regulated in extensive national and international rules of protection and safety. The article contains a topical review of the international and national transport regulations and codes pertaining to shipments of radioactive materials, and of the protection concepts underlying these codes so as to ensure an adequate standard of safety and security in shipping radioactive materials in national and international goods traffic. (orig.)

Model Regulations for the Use of Radiation Sources and for the Management of the Associated Radioactive Waste. Supplement to IAEA Safety Standards Series No. GS-G-1.5

International Nuclear Information System (INIS)

2015-01-01

IAEA Safety Standards Series No. GSR Part 1, Governmental, Legal and Regulatory Framework for Safety, requires that governments establish laws and statutes to make provisions for an effective governmental, legal and regulatory framework for safety. The framework for safety includes the establishment of a regulatory body. The regulatory body has the authority and responsibility for promulgating regulations, and for preparing their implementation. This publication provides advice on an appropriate set of regulations covering all aspects of the use of radiation sources and the safe management of the associated radioactive waste. The regulations provide the framework for the regulatory requirements and conditions to be incorporated into individual authorizations for the use of radiation sources in industry, medical facilities, research and education and agriculture. The regulations also establish criteria to be used for assessing compliance. This publication allows States to appraise the adequacy of their existing regulations and regulatory guides, and can be used as a reference for those States developing regulations for the first time. The regulations set out in this publication will need to be adapted to take account of local conditions, technical resources and the scale of facilities and activities in the State. The set of regulations in this publication is based on the requirements established in the IAEA safety standards series, in particular in IAEA Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, in IAEA Safety Standards Series No. GSR Part 5, Predisposal Management of Radioactive Waste, and in IAEA Safety Standards Series No. SSR-5, Disposal of Radioactive Waste. They are also derived from the Code of Conduct of the Safety and Security of Radiation Sources and the Guidance on the Import and Export of Radioactive Sources. This publication allows States to appraise the

Model Regulations for the Use of Radiation Sources and for the Management of the Associated Radioactive Waste. Supplement to IAEA Safety Standards Series No. GS-G-1.5

International Nuclear Information System (INIS)

2013-12-01

IAEA Safety Standards Series No. GSR Part 1, Governmental, Legal and Regulatory Framework for Safety, requires that governments establish laws and statutes to make provisions for an effective governmental, legal and regulatory framework for safety. The framework for safety includes the establishment of a regulatory body. The regulatory body has the authority and responsibility for promulgating regulations, and for preparing their implementation. This publication provides advice on an appropriate set of regulations covering all aspects of the use of radiation sources and the safe management of the associated radioactive waste. The regulations provide the framework for the regulatory requirements and conditions to be incorporated into individual authorizations for the use of radiation sources in industry, medical facilities, research and education and agriculture. The regulations also establish criteria to be used for assessing compliance. This publication allows States to appraise the adequacy of their existing regulations and regulatory guides, and can be used as a reference for those States developing regulations for the first time. The regulations set out in this publication will need to be adapted to take account of local conditions, technical resources and the scale of facilities and activities in the State. The set of regulations in this publication is based on the requirements established in the IAEA safety standards series, in particular in IAEA Safety Standards Series No. GSR Part 3 (Interim), Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards, in IAEA Safety Standards Series No. GSR Part 5, Predisposal Management of Radioactive Waste, and in IAEA Safety Standards Series No. SSR-5, Disposal of Radioactive Waste. They are also derived from the Code of Conduct of the Safety and Security of Radiation Sources and the Guidance on the Import and Export of Radioactive Sources. This publication allows States to appraise the

Japan reforms its nuclear safety

International Nuclear Information System (INIS)

Anon.

2013-01-01

The Fukushima Daiichi NPP accident deeply questioned the bases of nuclear safety and nuclear safety regulation in Japan. It also resulted in a considerable loss of public confidence in the safety of nuclear power across the world. Although the accident was caused by natural phenomena, institutional and human factors also largely contributed to its devastating consequences, as shown by the Japanese Diet's and Government's investigation reports. 'Both regulators and licensees were held responsible and decided to fully reconsider the existing approaches to nuclear safety. Consequently, the regulatory system underwent extensive reform based on the lessons learned from the accident,' Yoshihiro Nakagome, the President of Japan Nuclear Energy Safety Organisation, an ETSON member TSO, explains. (orig.)

76 FR 9646 - Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation...

Science.gov (United States)

2011-02-22

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Parts 100, 117, 147, and 165 [USCG-2010-0399] Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation Regulations and Regulated Navigation Areas AGENCY: Coast Guard, DHS. ACTION: Notice of expired temporary rules...

Impact of Safety-Related Regulations on Codeine Use in Children: A Quasi-Experimental Study Using Taiwan's National Health Insurance Research Database.

Science.gov (United States)

Lin, Chih-Wan; Wang, Ching-Huan; Huang, Wei-I; Ke, Wei-Ming; Chao, Pi-Hui; Chen, Wen-Wen; Hsiao, Fei-Yuan

2017-07-01

Safety concerns regarding potential life-threatening adverse events associated with codeine have resulted in policy decisions to restrict its use in pediatrics. However, whether these drug safety communications have had an immediate and strong impact on codeine use remains in question. We aimed to investigate the impact of the two implemented safety-related regulations (label changes and reimbursement regulations) on the use of codeine for upper respiratory infection (URI) or cough. A quasi-experimental study was performed using Taiwan's National Health Insurance Research Database. Quarterly data of codeine prescription rates for URI/cough visits were reported, and an interrupted time series design was used to assess the impact of the safety regulations on the uses of codeine among children with URI/cough visits. Multivariable logistic regression models were used to explore patient and provider characteristics associated with the use of codeine. The safety-related regulations were associated with a significant reduction in codeine prescription rates of -4.24% (95% confidence interval [CI] -4.78 to -3.70), and the relative reduction compared with predicted rates based on preregulation projections was 60.4, 56.6, and 53.2% in the first, second, and third year after the regulations began, respectively. In the postregulation period, physicians specializing in otolaryngology (odds ratio [OR] 1.47, 95% CI 1.45-1.49), practicing in district hospitals (OR 6.84, 95% CI 5.82-8.04) or clinics (OR 6.50, 95% CI 5.54-7.62), and practicing in the least urbanized areas (OR 1.60, 95% CI 1.55-1.64) were more likely to prescribe codeine to children than their counterparts. Our study provides a successful example of how to effectively reduce the codeine prescriptions in children in the 'real-world' settings, and highlights areas where future effort could be made to improve the safety use of codeine. Future research is warranted to explore whether there was a simultaneous decrease in

Use of risk information to safety regulation. Fabrication facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

A procedure of ISA (Integrated Safety Analysis) for uranium fuel fabrication/enrichment facilities has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. There are two major activities in the year. First one is a study on ISA procedure for external events such as earthquakes. Second one is that for chemical consequences such as UF6 and HF. Other than the activities a fundamental study on a policy of utilizing risk information was conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

Safety applications of computer based systems for the process industry

International Nuclear Information System (INIS)

Bologna, Sandro; Picciolo, Giovanni; Taylor, Robert

1997-11-01

Computer based systems, generally referred to as Programmable Electronic Systems (PESs) are being increasingly used in the process industry, also to perform safety functions. The process industry as they intend in this document includes, but is not limited to, chemicals, oil and gas production, oil refining and power generation. Starting in the early 1970's the wide application possibilities and the related development problems of such systems were recognized. Since then, many guidelines and standards have been developed to direct and regulate the application of computers to perform safety functions (EWICS-TC7, IEC, ISA). Lessons learnt in the last twenty years can be summarised as follows: safety is a cultural issue; safety is a management issue; safety is an engineering issue. In particular, safety systems can only be properly addressed in the overall system context. No single method can be considered sufficient to achieve the safety features required in many safety applications. Good safety engineering approach has to address not only hardware and software problems in isolation but also their interfaces and man-machine interface problems. Finally, the economic and industrial aspects of the safety applications and development of PESs in process plants are evidenced throughout all the Report. Scope of the Report is to contribute to the development of an adequate awareness of these problems and to illustrate technical solutions applied or being developed

Safety Evaluation of Kartini Reactor Based on Instrumentation System Design

International Nuclear Information System (INIS)

Tjipta Suhaemi; Djen Djen Dj; Itjeu K; Johnny S; Setyono

2003-01-01

The safety of Kartini reactor has been evaluated based on instrumentation system aspect. The Kartini reactor is designed by BATAN. Design power of the reactor is 250 kW, but it is currently operated at 100 kW. Instrumentation and control system function is to monitor and control the reactor operation. Instrumentation and control system consists of safety system, start-up and automatic power control, and process information system. The linear power channel and logarithmic power channel are used for measuring power. There are 3 types of control rod for controlling the power, i.e. safety rod, shim rod, and regulating rod. The trip and interlock system are used for safety. There are instrumentation equipment used for measuring radiation exposure, flow rate, temperature and conductivity of fluid The system of Kartini reactor has been developed by introducing a process information system, start-up system, and automatic power control. It is concluded that the instrumentation of Kartini reactor has followed the requirement and standard of IAEA. (author)

Regulation for delivery of subsidies for public relations and safety

International Nuclear Information System (INIS)

1984-01-01

The regulations provide for subsidies for the public relations activities and safety operations carried out by a local government for the local inhabitants in the vicinity of a nuclear power generation, etc. facility. This type of activity includes the dissemination of information on nuclear power, studies on securing the safety of the inhabitants and communication concerning the facility safety. The contents are as follows: limits of the subsidies, terms of subsidy allocations, the application for subsidies, determination of subsidy allocations, withdrawal of applications, the conditions to the allocations, a report on the work proceedings, a report on the results, confirmation on the sum of subsidies, withdrawal of the decision for subsidies, limitations for disposal of the properties, etc. (Mori, K.)

Regulation for delivery of subsidies for public relations and safety

International Nuclear Information System (INIS)

1985-01-01

The regulations provide for subsidies for the public relations activities and safety operations carried out by a local government for the local inhabitants in the vicinity of a nuclear power generation, etc. facility. This type of activity includes the dissemination of information on nuclear power, studies on securing the safety of the inhabitants and communication concerning the facility safety. The contents are as follows : limits of the subsidies, terms of subsidy allocations, the application for subsidies, determination of subsidy allocations, withdrawal of applications, the conditions to the allocations, a report on the work proceedings, a report on the results, confirmation on the sum of subsidies, withdrawal of the decision for subsidies, limitations for disposal of the properties, etc. (Kubozono, M.)

Patient-Centered Robot-Aided Passive Neurorehabilitation Exercise Based on Safety-Motion Decision-Making Mechanism

Directory of Open Access Journals (Sweden)

Lizheng Pan

2017-01-01

Full Text Available Safety is one of the crucial issues for robot-aided neurorehabilitation exercise. When it comes to the passive rehabilitation training for stroke patients, the existing control strategies are usually just based on position control to carry out the training, and the patient is out of the controller. However, to some extent, the patient should be taken as a “cooperator” of the training activity, and the movement speed and range of the training movement should be dynamically regulated according to the internal or external state of the subject, just as what the therapist does in clinical therapy. This research presents a novel motion control strategy for patient-centered robot-aided passive neurorehabilitation exercise from the point of the safety. The safety-motion decision-making mechanism is developed to online observe and assess the physical state of training impaired-limb and motion performances and regulate the training parameters (motion speed and training rage, ensuring the safety of the supplied rehabilitation exercise. Meanwhile, position-based impedance control is employed to realize the trajectory tracking motion with interactive compliance. Functional experiments and clinical experiments are investigated with a healthy adult and four recruited stroke patients, respectively. The two types of experimental results demonstrate that the suggested control strategy not only serves with safety-motion training but also presents rehabilitation efficacy.

Pesticide regulations and farm worker safety: the need to improve pesticide regulations in Viet Nam.

Science.gov (United States)

Phung, Dung Tri; Connell, Des; Miller, Greg; Rutherford, Shannon; Chu, Cordia

2012-06-01

Agricultural pesticide use in Viet Nam has more than tripled since 1990. However, pesticide legislation and regulations have not been developed in response to this large increase in usage, as a result of which pesticides pose a serious threat to human health and the environment. This paper identifies the need to improve pesticide regulations in Viet Nam through a comparative analysis of pesticide regulations in Viet Nam and the United States of America, where the rate of acute poisoning among agricultural workers is much lower than in Viet Nam and where information pertaining to pesticide regulations is made accessible to the public. The analysis identified several measures that would help to improve Viet Nam's pesticide regulations. These include enhancing pesticide legislation, clarifying the specific roles and active involvement of both the environmental and health sectors; performing a comprehensive risk-benefit evaluation of pesticide registration and management practices; improving regulations on pesticide suspension and cancellation, transport, storage and disposal; developing import and export policies and enhancing pesticide-related occupational safety programmes.

The challenges for global harmonisation of food safety norms and regulations: issues for India.

Science.gov (United States)

Prakash, Jamuna

2014-08-01

Safe and adequate food is a human right, safety being a prime quality attribute without which food is unfit for consumption. Food safety regulations are framed to exercise control over all types of food produced, processed and sold so that the customer is assured that the food consumed will not cause any harm. From the Indian perspective, global harmonisation of food regulations is needed to improve food and nutrition security, the food trade and delivery of safe ready-to-eat (RTE) foods at all places and at all times. The Millennium Development Goals (MDGs) put forward to transform developing societies incorporate many food safety issues. The success of the MDGs, including that of poverty reduction, will in part depend on an effective reduction of food-borne diseases, particularly among the vulnerable group, which includes women and children. Food- and water-borne illnesses can be a serious health hazard, being responsible for high incidences of morbidity and mortality across all age groups of people. Global harmonisation of food regulations would assist in facilitating food trade within and outside India through better compliance, ensuring the safety of RTE catered foods, as well as addressing issues related to the environment. At the same time, regulations need to be optimum, as overregulation may have undue negative effects on the food trade. © 2013 Society of Chemical Industry.

Safety culture and accident analysis-A socio-management approach based on organizational safety social capital

International Nuclear Information System (INIS)

Rao, Suman

2007-01-01

One of the biggest challenges for organizations in today's competitive business environment is to create and preserve a self-sustaining safety culture. Typically, Key drivers of safety culture in many organizations are regulation, audits, safety training, various types of employee exhortations to comply with safety norms, etc. However, less evident factors like networking relationships and social trust amongst employees, as also extended networking relationships and social trust of organizations with external stakeholders like government, suppliers, regulators, etc., which constitute the safety social capital in the Organization-seem to also influence the sustenance of organizational safety culture. Can erosion in safety social capital cause deterioration in safety culture and contribute to accidents? If so, how does it contribute? As existing accident analysis models do not provide answers to these questions, CAMSoC (Curtailing Accidents by Managing Social Capital), an accident analysis model, is proposed. As an illustration, five accidents: Bhopal (India), Hyatt Regency (USA), Tenerife (Canary Islands), Westray (Canada) and Exxon Valdez (USA) have been analyzed using CAMSoC. This limited cross-industry analysis provides two key socio-management insights: the biggest source of motivation that causes deviant behavior leading to accidents is 'Faulty Value Systems'. The second biggest source is 'Enforceable Trust'. From a management control perspective, deterioration in safety culture and resultant accidents is more due to the 'action controls' rather than explicit 'cultural controls'. Future research directions to enhance the model's utility through layering are addressed briefly

Australian Experience in Implementing Transport Safety Regulations and Transport Security Recommendations

International Nuclear Information System (INIS)

Sarkar, S.

2016-01-01

Australian transport safety and security regulatory framework is governed by Commonwealth, State and Territory legislations. There are eleven competent authorities in Australia that includes three Commonwealth authorities, six states and two territory authorities. IAEA Regulations for Safe Transport of Radioactive Material (TS-R-1, 2005 edition) is applied through Australian Radiation Protection and Nuclear Safety Agency (ARPANSA) Code of Practice for Transport of Radioactive Material 2008 by road, rail and waterways not covered by marine legislations. All states and territories apply this Transport Code through their regulatory system. For air transport, the Civil Aviation Act 1988 adopts the requirements of the ICAO Technical Instructions for the Safe Transport of Dangerous Goods by Air DOC 9284, which also adopts TS-R-1. The security of radioactive material in air transport is achieved via the Aviation Transport Security Act 2004. For sea transport Australian Marine Order 41 applies the requirements of IMDG (International Maritime Dangerous Goods) Code which also adopts TS-R-1. The security of radioactive material (nuclear material) is governed by two Commonwealth Agencies namely, ARPANSA and ASNO (Australian Safeguards and Non-proliferation Office) . ARPANSA regulates the security of radioactive sources through ARPANSA Code of Practice for the Security of Radioactive Sources 2007 which is based on the IAEA Draft Security Series. ASNO regulates security of nuclear material including U, Th and Pu through the Nuclear Non-Proliferation (Safeguards) Act, and the object of which is to give effect to certain obligations that Australia has as a party to the NPT, Australia’s safeguards agreement with the IAEA, and other bilateral safeguards agreements and certain obligations that Australia has as a party to the Convention for the Physical Protection of Nuclear Materials (CPPNM). This paper presents the effectiveness of regulatory approaches for safe and secure

Implementation of ICRP-60, BBS-115 and the patient directives in radiation safety regulations of TAEK

International Nuclear Information System (INIS)

Okyar, H.B.; Vural, M.

2001-01-01

clearance procedures. The preamble to the Basic Safety Standards states that it is presumed in the Standards that Governments have an adequate national infrastructure in place in order to discharge their responsibilities for radiation protection and safety. In Turkey, the relevant national authority for regulating activities involving radioactive sources is the Turkish Atomic Energy Authority (TAEK). The structure of TAEK and its legislation will be introduced. Radiation Safety Regulation (Official Journal no.: 20983) which was issued in 6 September 1991 was revised and issued in 24 March 2000 (Official Journal no.: 23999). The revised version of the Radiation Safety Regulation based on BSS-115 and EC Directives includes definitions, exemptions, responsibilities, dose limits (significant decrease in the limits follows the recommendations of ICRP-60), redefinition of controlled and supervised areas, import and re-export procedures of radioactive materials, redefinition of licensing procedures, limitations in import radiation generators used in medicine, quality control, guidance levels of dose, dose rate and activity for medical exposures (including diagnostic radiological procedures, diagnostic procedures in nuclear medicine), dose levels in interventions and guidelines for intervention levels and action levels in emergency exposure situations. (author)

Risk-informed regulation

International Nuclear Information System (INIS)

Hoffman, D.R.

2003-01-01

In assessing safety for nuclear facilities, regulators have traditionally used a deterministic approach. New techniques for assessing nuclear or radiological risks make it possible for regulators to incorporate risk insights into their regulations. By 'risk-informing' the regulatory processes, independent bodies tasked with protecting the health and safety of the public can focus on those design and operational issues most important to safety. Such an approach is a move away from prescriptive regulations that were based on conservative engineering judgments toward regulations focused on issues that contribute significantly to safety. Despite the availability of probabilistic risk assessment (PRA) tools, organisations often struggle with how to best use this capability. Most international regulations are still based largely on deterministic analyses that were developed without the benefit of quantitative or measurable estimates of risk. PRA considers issues of risk in a more comprehensive manner by examining a wider spectrum of initiating events and their frequency, and considers the likelihood of events in a rigorous and comprehensive manner. In some countries, nuclear regulators are actively moving toward increasing the use of risk insights in a variety of strategic arenas, including risk-informed technical specifications (operating limits and conditions), in-service inspection and testing, programs, and assessment and enforcement actions. A risk-informed approach enhances the traditional deterministic approach by explicitly considering a broader range of safety challenges, focusing resources on the basis of risk significance, considering a broader range of counter measures to mitigate challenges, and explicitly identifying and quantifying uncertainties in analyses. (author)

Realism in nuclear criticality safety

International Nuclear Information System (INIS)

McLaughlin, T. P.

2009-01-01

Commercial nuclear power plant operation and regulation have made remarkable progress since the Three Mile Island Accident. This is attributed largely to a heavy dose of introspection and self-regulation by the industry and to a significant infusion of risk-informed and performance-based regulation by the Nuclear Regulatory Commission. This truly represents reality in action both by the plant operators and the regulators. On the other hand, the implementation of nuclear criticality safety in ex-reactor operations involving significant quantities of fissile material has not progressed, but, tragically, it has regressed. Not only is the practice of the discipline in excess of a factor of ten more expensive than decades ago; the trend continues. This unfortunate reality is attributed to a lack of coordination within the industry (as contrasted to what occurred in the reactor operations sector), and to a lack of implementation of risk-informed and performance-based regulation by the NRC While the criticality safety discipline is orders of magnitude smaller than the reactor safety discipline, both operators and regulators must learn from the progress made in reactor safety and apply it to the former to reduce the waste, inefficiency and potentially increased accident risks associated with current practices. Only when these changes are made will there be progress made toward putting realism back into nuclear criticality safety. (authors)

A study on the relevance and influence of the existing regulation and risk informed/performance based regulation

Energy Technology Data Exchange (ETDEWEB)

Cheong, B. J.; Kang, J. M.; Kim, H. S.; Koh, S. H.; Kang, D. H.; Park, C. H. [Cheju Univ., Jeju (Korea, Republic of)

2003-02-15

The goal of this study is to estimate the relevance and Influence of the Existing Regulation and the RI-PBR to the institutionalization of the regulatory system. This study reviews the current regulatory system and the status of the RI-PBR implementation of the US NRC and Korea based upon SECY Papers, Risk Informed Regulation Implementation Plan (RIRIP) of the US NRC and other domestic studies. In order to investigate the perceptions, knowledge level, ground for the regulatory change, a survey was performed to Korean nuclear utilities, researchers and regulators on the perception on the RIR. The questionnaire was composed of 50 questions regarding personal details on work experience, level of education and specific field of work ; level of knowledge on the risk informed performance based regulation (RI-PBR); the perception of the current regulation, the effectiveness, level of procedure, flexibility, dependency on the regulator and personal view, and the perception of the RI-PBR such as flexibility of regulation, introduction time and the effect of RI-PBR, safety improvement, public perception, parts of the existing regulatory system that should be changed, etc. 515 answered from all sectors of the nuclear field; utilities, engineering companies, research institutes, and regulatory bodies.

State of bus safety in the U.S. : summary of federal and state regulations.

Science.gov (United States)

2014-06-01

This report provides a comprehensive overview of transit bus safety regulations and standards developed by all 50 states, as well as : information on how state departments of transportation (DOT) regulate the maintenance or operation of transit/parat...

Risk assessment and safety regulations in offshore oil and gas ...

African Journals Online (AJOL)

Risk management of which risk assessment is part, and safety regulations are common in the offshore oil and gas industry management system. The process of conducting risk assessment is mostly a challenge for operational personnel assigned to perform this function. The most significant problem is the decision to use ...

Safety culture and accident analysis-A socio-management approach based on organizational safety social capital

Energy Technology Data Exchange (ETDEWEB)

Rao, Suman [Risk Analyst (India)]. E-mail: sumanashokrao@yahoo.co.in

2007-04-11

One of the biggest challenges for organizations in today's competitive business environment is to create and preserve a self-sustaining safety culture. Typically, Key drivers of safety culture in many organizations are regulation, audits, safety training, various types of employee exhortations to comply with safety norms, etc. However, less evident factors like networking relationships and social trust amongst employees, as also extended networking relationships and social trust of organizations with external stakeholders like government, suppliers, regulators, etc., which constitute the safety social capital in the Organization-seem to also influence the sustenance of organizational safety culture. Can erosion in safety social capital cause deterioration in safety culture and contribute to accidents? If so, how does it contribute? As existing accident analysis models do not provide answers to these questions, CAMSoC (Curtailing Accidents by Managing Social Capital), an accident analysis model, is proposed. As an illustration, five accidents: Bhopal (India), Hyatt Regency (USA), Tenerife (Canary Islands), Westray (Canada) and Exxon Valdez (USA) have been analyzed using CAMSoC. This limited cross-industry analysis provides two key socio-management insights: the biggest source of motivation that causes deviant behavior leading to accidents is 'Faulty Value Systems'. The second biggest source is 'Enforceable Trust'. From a management control perspective, deterioration in safety culture and resultant accidents is more due to the 'action controls' rather than explicit 'cultural controls'. Future research directions to enhance the model's utility through layering are addressed briefly.

Highway Safety, Economic Behavior, and Driving Environment

OpenAIRE

Keeler, Theodore E.

1991-01-01

Economic analysis has enhanced our understanding of the efficacy of highway safety regulations. Specifically, a consumer-theoretic literature has developed on drivers' responses to regulations, based on ideas first set forth by Lester lave and W. E. Weber (1970) and more fully thought out by Sam Peltzman (1975). Meanwhile, an empirical literature has also developed, testing hypotheses relating to the effects on safety of speed limits, safety-device regulations, and alcohol policies, among oth...

Identification of Behavior Based Safety by Using Traffic Light Analysis to Reduce Accidents

Science.gov (United States)

Mansur, A.; Nasution, M. I.

2016-01-01

This work present the safety assessment of a case study and describes an important area within the field production in oil and gas industry, namely behavior based safety (BBS). The company set a rigorous BBS and its intervention program that implemented and deployed continually. In this case, observers requested to have discussion and spread a number of determined questions related with work behavior to the workers during observation. Appraisal of Traffic Light Analysis (TLA) as one tools of risk assessment used to determine the estimated score of BBS questionnaire. Standardization of TLA appraisal in this study are based on Regulation of Minister of Labor and Occupational Safety and Health No:PER.05/MEN/1996. The result shown that there are some points under 84%, which categorized in yellow category and should corrected immediately by company to prevent existing bad behavior of workers. The application of BBS expected to increase the safety performance at work time-by-time and effective in reducing accidents.

Nuclear safety philosophy and its general application to fuel management and handling - a regulator's viewpoint

International Nuclear Information System (INIS)

Petty, I.C.

1995-01-01

The Nuclear Safety Division (NSD) of the Health and Safety Executive (HSE) informs the UK Nuclear Industry of the principles that it applies in assessing whether licensees have demonstrated that their nuclear plants are as safe as is reasonably practicable. The paper commences with a discussion of the non-prescriptive approach to health and safety regulation which is the basis of the regulatory activities of NSD's operating arm -the Nuclear Installations Inspectorate (NII). It then describes in broad terms the overall approach used by NII for analysing the safety of nuclear plant, including fuel, which will cover both deterministic and probabilistic methodologies. The paper then introduces the sections of the Safety Assessment Principles which apply to nuclear fuel safety (both fuel handling and management). Most of these principles are of a general nature and do not just apply to fuel. The paper explains how safety cases might relate to the SAPs and offers some views on how a licensee might interpret them in developing his safety case. Particular emphasis is placed on the importance of submitting a high quality safety case and the type of information that should be in it. The advantages of the approach proposed, to the licensee as well as to the regulator, are identified. (author)

Regulations of 19 August 1978 on the optional principles of the Nuclear Safety Committee

International Nuclear Information System (INIS)

1978-01-01

These regulations were published in the Turkish Official Gazette of 19 August 1978 and were made pursuant to Decree no. 7/9141 of 1975 on licensing of nuclear installations which established the Nuclear Safety Committee. They determine the duties and responsibilities of the Committee, its qualifications, its operating principles and its relations with the Nuclear Safety Assistance Service set up in the Turkish Atomic Energy Commission for the purposes of assisting its Secretary General. The regulations also lay down the procedures to be applied for consultations on granting licences. (NEA) [fr

Converting the GSR part3 into a national regulations for the protection and safety of radiation sources

International Nuclear Information System (INIS)

Hatim, Abdulrahman

2016-04-01

The achievement and maintenance of a high level of Radiation Protection and Safety of Radiation Sources depends on a sound legal and governmental infrastructure, including a regulatory body with well-defined responsibilities and functions. The project aimed at converting the IAEA GRS Part 3 into National regulations in Sudan for the protection against the harmful effects of ionizing radiation and safety of radiation sources. The regulations developed covered general requirements for radiation protection, verification of safety, planned exposure situations, emergency exposure situations and existing exposure situation. The Government of Sudan is expected to empower the Sudanese Nuclear Radiological Regulatory Authority (SNRAA) and other relevant authorities to undertake the conversion of IAEA GSR Part 3 into national regulations to be used to regulate all facilities and activities in Sudan. (au)

Fusion safety data base

International Nuclear Information System (INIS)

Laats, E.T.; Hardy, H.A.

1983-01-01

The purpose of this Fusion Safety Data Base Program is to provide a repository of data for the design and development of safe commercial fusion reactors. The program is sponsored by the United States Department of Energy (DOE), Office of Fusion Energy. The function of the program is to collect, examine, permanently store, and make available the safety data to the entire US magnetic-fusion energy community. The sources of data will include domestic and foreign fusion reactor safety-related research programs. Any participant in the DOE Program may use the Data Base Program from his terminal through user friendly dialog and can view the contents in the form of text, tables, graphs, or system diagrams

Critical Reflections on Conservatism in Nuclear Safety Regulation

International Nuclear Information System (INIS)

Choi, Young Sung; Choi, Kwang Sik

2007-01-01

A recent report published by the Committee on Nuclear Regulatory Activities (CNRA) of the OECD Nuclear Energy Agency (NEA) says that a fundamental principle for safety regulators is the practice of conservative decision making. Nuclear regulators frequently face challenging issues surrounded by uncertainties or lack of data and information. No matter what efforts will be made to collect the available information and to assess the issues, nobody can clear all the uncertainties and make absolutely certain decision. More often than not, the regulators have to make a decision in light of continuing uncertainties and limited information. It is at this point that the principle of conservatism should play a role. However the principle comes in many diverse forms such as default conservatism, precautionary principle, defense in depth and realistic conservatism. These different forms of conservatism have different roles and meanings that will take a decision maker to drastically different results. This paper reviews different forms of conservatism in critical way, presents analytical framework for decision making under uncertainty and suggests future research works needed

Study of Evaluation OSH Management System Policy Based On Safety Culture Dimensions in Construction Project

Science.gov (United States)

Latief, Yusuf; Armyn Machfudiyanto, Rossy; Arifuddin, Rosmariani; Mahendra Fira Setiawan, R.; Yogiswara, Yoko

2017-07-01

Safety Culture in the construction industry is very influential on the socio economic conditions that resulted in the country’s competitiveness. Based on the data, the accident rate of construction projects in Indonesia is very high. In the era of the Asian Economic Community (AEC) Indonesian contractor is required to improve competitiveness, one of which is the implementation of the project without zero accident. Research using primary and secondary data validated the results of the literature experts and questionnaire respondents were analyzed using methods SmartPLS, obtained pattern of relationships between dimensions of safety culture to improve the performance of Safety. The results showed that the behaviors and Cost of Safety into dimensions that significantly affect the performance of safety. an increase in visible policy-based on Regulation of Public Work and Housing No 5/PRT/M/2014 to improve to lower the accident rate.

The role of the Gosatomnadzor of Russia in national regulating of safety of radiation sources and security of radioactive materials

International Nuclear Information System (INIS)

Mikhailov, M.V.; Sitnikov, S.A.

2001-01-01

As at the end of 1999, the Gosatomnadzor of Russia supervised 6551 radiation sources, including 1285 unsealed sources with individual activity from a minimal level to 1x10 12 Bq and a total activity of 585x10 12 Bq, and also 5266 sealed sources with individual activity from 30 to 1x10 17 Bq and the total activity of more than 11x10 17 Bq. A national infrastructure has been created in the Russian Federation in order to regulate the safety of nuclear energy use. The infrastructure includes the legal system and the regulatory authorities based on and acting according to it. The regulation of radiation safety, including assurance of radiation source safety and radioactive material security (management of disused sources, planning, preparedness and response to abnormal events and emergencies, recovery of control over orphan sources, informing users and others who might be affected by lost source, and education and training in the safety of radiation sources and the security of radioactive materials), is realized within this infrastructure. The legal system includes federal laws ('On the Use of Nuclear Energy' and 'On Public Radiation Safety'), a number of decrees and resolutions of the President and the Government of the Russian Federation, federal standards and rules for nuclear energy use, and also departmental and industrial manuals and rules, State standards, construction standards and rules and other documents. The safety regulation tasks have been defined by these laws, according to which regulatory authorities are entrusted with the development, approval and putting into force of standards and rules in the nuclear energy use, with issuing licenses for carrying out nuclear activities, with safety supervision assurance, with review and inspection implementation, with control over development and realization of protective measures for workers, population and environment in emergencies at nuclear and radiation hazardous facilities. Russian national regulatory

Safety experts complete second IAEA regulatory review of UK nuclear regulator

International Nuclear Information System (INIS)

2009-01-01

Full text: Nuclear safety experts today concluded a 10-day mission to peer-review the UK Nuclear Regulator: Health and Safety Executive (HSE), Nuclear Directorate (ND). At the request of the UK Government, the International Atomic Energy Agency assembled a team of ten high-level regulatory experts from eight nations to conduct the Integrated Regulatory Review Service (IRRS) mission. The mission was the second of three planned IRRS missions for the United Kingdom. The first was held in March 2006 to begin a process to assess the nation's readiness to regulate and license new reactor designs, considered as a result of the Energy Policy review initiated by the British Prime Minister and the Secretary of State for Trade and Industry (DTI) in 2005. The IRRS team leader Mr. William Borchardt, Executive Director of Operations from the US Nuclear Regulatory Commission, stated, ''The IAEA IRRS serves an important role in both benchmarking against its safety standards and in promoting dialogue between nuclear safety regulators from around the world.'' During the 2nd mission the IRRS the team reviewed HSE/ND progress since the first IRRS mission and recent regulatory developments, the regulation of operating power plants and fuel cycle facilities, the inspection and enforcement programme for nuclear power plants and fuel cycle facilities, and the emergency preparedness and response programme. The IAEA found that HSE/ND has made significant progress toward improving its effectiveness in regulating existing nuclear power plants and in preparing to license new nuclear reactors designs. Many of the findings identified in the 2006 report had been fully addressed and therefore could be considered closed, the others are being addressed in accordance with a comprehensive action plan. IRRS team members visited the Heysham 1 Nuclear Power Plant near Lancaster, the Sellafield site at Cumbria and the Strategic Control Centre at Hutton, and they met senior managers from HSE and a UK

Development of a safety and regulation systems simulation program II

International Nuclear Information System (INIS)

1985-05-01

This report describes the development of a safety and regulation systems simulation program under contract to the Atomic Energy Control Board of Canada. A systems logic interaction simulation (SLISIM) program was developed for the AECB's HP-1000 computer which operates in the interactive simulation (INSIM) program environment. The SLISIM program simulates the spatial neutron dynamics, the regulation of the reactor power and in this version the CANDU-PHW 600 MW(e) computerized shutdown systems' trip parameters. The modular concept and interactive capability of the INSIM environment provides the user with considerable flexibility of the setup and control of the simulation

Behavior based safety

International Nuclear Information System (INIS)

Sudhikumaran, T.V.; Mehta, S.C.; Goyal, D.K.

2009-01-01

Behaviour Based Safety (popularly known as BBS) is a new methodology for achieving injury free work place and total Safety Culture. BBS is successfully being implemented and is being practiced as a work methodology for achieving a loss and injury free work environment and work practice. Through BBS, it was brought out that the root causes of all Industrial accidents some how originate from the 'at risk' behaviour of some individual or group of individuals at some level. The policy of NPCIL is to excel in the field of Industrial and Fire Safety in comparison to international standards. This article indents to bring out the various parameters helping in installing BBS programme at any plant. (author)

Global Nuclear Safety and Security Network

International Nuclear Information System (INIS)

Guo Lingquan

2013-01-01

The objectives of the Regulatory Network are: - to contribute to the effectiveness of nuclear regulatory systems; - to contribute to continuous enhancements, and - to achieve and promote radiation and nuclear safety and security by: • Enhancing the effectiveness and efficiency of international cooperation in the regulation of nuclear and radiation safety of facilities and activities; • Enabling adequate access by regulators to relevant safety and security information; • Promoting dissemination of information on safety and security issues as well as information of good practices for addressing and resolving these issues; • Enabling synergies among different web based networks with a view to strengthening and enhancing the global nuclear safety framework and serving the specific needs of regulators and international organizations; • Providing additional information to the public on international regulatory cooperation in safety and security matters

Safety and regulation in the use of radiation in medicine: status in India and future perspective

International Nuclear Information System (INIS)

Gopalakrishnan, A.; Parthasarathy, K.S.; Ghosh, P.K.

1996-01-01

This paper briefly reviews the history of radiation protection, regulatory aspects and the status of radiation safety in radiotherapy, radiodiagnosis and nuclear medicine in India. The revised basic safety standards and the future developments envisaged in the safety and regulation are also mentioned. (author). 24 refs., 8 tabs

Recent development in safety regulation of nuclear fuel cycle activities

International Nuclear Information System (INIS)

Kato, S.

2001-01-01

Through the effort of deliberation and legislation over five years, Japanese government structure was reformed this January, with the aim of realizing simple, efficient and transparent administration. Under the reform, the Agency for Nuclear and Industrial Safety (ANIS) was founded in the Ministry of Economy, Trade and Industry (METI) to be responsible for safety regulation of energy-related nuclear activities, including nuclear fuel cycle activities, and industrial activities, including explosives, high-pressure gasses and mining. As one of the lessons learned from the JCO criticality accident of September 1999, it was pointed out that the government's inspection function was not enough for fuel fabrication facilities. Accordingly, new statutory regulatory activities were introduced, namely, inspection of observance of safety rules and procedures for all kinds of nuclear operators and periodic inspection of fuel fabrication facilities. In addition, in order to cope with insufficient safety education and training of workers in nuclear facilities, licensees of nuclear facilities are required by law to specify safety education and training for their workers. ANIS is committed to enforce these new regulatory activities effectively and efficiently. In addition, it is going to be prepared, in its capacity as safety regulatory authority, for future development of Japanese fuel cycle activities, including commissioning of JNFL Rokkasho reprocessing plant and possible application for licenses for JNFL MOX fabrication plant and for spent fuel interim storage facilities. (author)

The role of the nuclear safety regulator

International Nuclear Information System (INIS)

Mellado, I.

2007-01-01

The Consejo de Seguridad Nuclear (CSN), or Nuclear Safety Council, is the only Spanish institution qualified in nuclear safety and radiological protection. Created in 1980, the CSN is independent of the Central State Administration, and possesses its own legal standing, estate and resources acquired directly from tax revenues. The CSN proposes regulations and advises the government on subjects within its competence, including the criteria for siting nuclear facilities once the autonomous regions have been informed. The CSN is responsible for issuing mandatory and binding reports to the Ministry of Industry. Tourism and Commerce, and for inspections and evaluation of the facilities included within its realm of competence throughout their phases (construction, start-up, operating and decommissioning). It is also responsible for the radiological control and surveillance of workers, the general public and the environment, as described below. In 1999, a new responsibility was assigned to the CSN to perform studies, assessment and inspections in relation to all phases of radioactive waste and spent fuel management. The CSN reports to the Spanish Parliament and is not subject to the hierarchy or auspices of the Government or the organisations in charge of promoting nuclear energy. The Council itself is an Associative Body comprised of 5 members, appointed by Parliament for a 6 year term (these members cannot be removed). Under this Council is situated an extensive technical body. A General Secretary is seconded by Technical Directors in the area of Nuclear Safety and Radiological Protection. As well there are a R and D Office, an Inspection Office, and a Technical Standards Office. The CSN counts 446 workers, of which 191 are university graduate specialists in nuclear safety or radiological protection. The average age is 45 years. Ongoing training is provided in technical specialties and management. (author)

Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations

International Nuclear Information System (INIS)

2010-01-01

It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An undesirable consequence of this situation is that the licensing approaches taken by nuclear safety authorities and by technical support organisations are determined independently with only limited informal technical co-ordination and information exchange. It is notable that several software implementations of nuclear safety systems have been marred by costly delays caused by difficulties in co-ordinating the development and qualification process. It was thus felt necessary to compare the respective licensing approaches, to identify where a consensus already exists, and to see how greater consistency and more mutual acceptance could be introduced into current practices. This report is the result of the work of a group of regulator and safety authorities' experts. The 2007 version was completed at the invitation of the Western European Nuclear Regulators' Association (WENRA). The major result of the work is the identification of consensus and common technical positions on a set of important licensing issues raised by the design and operation of computer based systems used in nuclear power plants for the implementation of safety functions. The purpose is to introduce greater consistency and more mutual acceptance into current practices. To achieve these common positions, detailed consideration was paid to the licensing approaches followed in the different countries represented by the experts of the task force. The report is intended to be useful: - to coordinate regulators' and safety experts' technical viewpoints in the design of regulators' national policies and in revisions

Licensing of safety critical software for nuclear reactors. Common position of seven European nuclear regulators and authorised technical support organisations

Energy Technology Data Exchange (ETDEWEB)

2010-07-01

It is widely accepted that the assessment of software cannot be limited to verification and testing of the end product, i.e. the computer code. Other factors such as the quality of the processes and methods for specifying, designing and coding have an important impact on the implementation. Existing standards provide limited guidance on the regulatory and safety assessment of these factors. An undesirable consequence of this situation is that the licensing approaches taken by nuclear safety authorities and by technical support organisations are determined independently with only limited informal technical co-ordination and information exchange. It is notable that several software implementations of nuclear safety systems have been marred by costly delays caused by difficulties in co-ordinating the development and qualification process. It was thus felt necessary to compare the respective licensing approaches, to identify where a consensus already exists, and to see how greater consistency and more mutual acceptance could be introduced into current practices. This report is the result of the work of a group of regulator and safety authorities' experts. The 2007 version was completed at the invitation of the Western European Nuclear Regulators' Association (WENRA). The major result of the work is the identification of consensus and common technical positions on a set of important licensing issues raised by the design and operation of computer based systems used in nuclear power plants for the implementation of safety functions. The purpose is to introduce greater consistency and more mutual acceptance into current practices. To achieve these common positions, detailed consideration was paid to the licensing approaches followed in the different countries represented by the experts of the task force. The report is intended to be useful: - to coordinate regulators' and safety experts' technical viewpoints in the design of regulators' national

The UK health and safety executive's policies on information relating to nuclear safety regulation

International Nuclear Information System (INIS)

Williams, L.

1994-01-01

How a message is transmitted can be as important as what is said. To be effective a message has to be timely, targeted and clear. People do not always remember what was said, by how and when it was said. This paper discusses some of the tools which the Nuclear Safety Division (NSD), the UK's nuclear regulator, has used and emphasizes the need to recognize the importance of a recipient interest in attempting to transmit a message. (author). 4 refs

NRC safety research in support of regulation. Selected highlights

International Nuclear Information System (INIS)

1986-05-01

The report presents selected highlights of how research has contributed to the regulatory effort. It explains the research role of the NRC and nuclear safety research contributions in the areas of: pressure vessel integrity, piping, small- and large-break loss-of-coolant accidents, hydrogen and containment, source term analysis, seismic hazards and high-level waste management. The report also provides a summary of current and future research directions in support of regulation

Safety Supervisory Strategy for an Upper-Limb Rehabilitation Robot Based on Impedance Control

Directory of Open Access Journals (Sweden)

Lizheng Pan

2013-02-01

Full Text Available User security is an important consideration for robots that interact with humans, especially for upper-limb rehabilitation robots, during the use of which stroke patients are often more susceptible to injury. In this paper, a novel safety supervisory control method incorporating fuzzy logic is proposed so as to guarantee the impaired limb's safety should an emergency situation occur and the robustness of the upper-limb rehabilitation robot control system. Firstly, a safety supervisory fuzzy controller (SSFC was designed based on the impaired-limb's real-time physical state by extracting and recognizing the impaired-limb's tracking movement features. Then, the proposed SSFC was used to automatically regulate the desired force either to account for reasonable disturbance resulting from pose or position changes or to respond in adequate time to an emergency based on an evaluation of the impaired-limb's physical condition. Finally, a position-based impedance controller was implemented to achieve compliance between the robotic end-effector and the impaired limb during the robot-assisted rehabilitation training. The experimental results show the effectiveness and potential of the proposed method for achieving safety and robustness for the rehabilitation robot.

48 CFR 1252.217-80 - Department of Labor Safety and Health Regulations for Ship Repairing.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Department of Labor Safety and Health Regulations for Ship Repairing. 1252.217-80 Section 1252.217-80 Federal Acquisition Regulations System DEPARTMENT OF TRANSPORTATION CLAUSES AND FORMS SOLICITATION PROVISIONS AND CONTRACT CLAUSES Text of Provisions and Clauses 1252.217-80...

Learning and nuclear safety: New reactors and US regulation

International Nuclear Information System (INIS)

Nichols, E.; Wildavsky, A.

1992-01-01

Gathering and analyzing data from operating reactors has become part of government and industry programs to improve performance in plants already on line and to inform development of future reactors. In the United States, however, early development and certain other factors combined to encourage a bias in learning. Regulation and learning from operational data intersect in ways that limit participation, data collection, and positive response to findings. Past learning has shown the advantage of simpler more standard designs with passive or inherent safety features. However, even designs incorporating these past lessons are apt to face tough regulatory tests and much criticism as operating experience is gathered. Only the operational success of new standardized reactors is apt to help rationalize regulation. (orig.)

Department of Energy Construction Safety Reference Guide

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

DOE has adopted the Occupational Safety and Health Administration (OSHA) regulations Title 29 Code of Federal Regulations (CFR) 1926 ``Safety and Health Regulations for Construction,`` and related parts of 29 CFR 1910, ``Occupational Safety and Health Standards.`` This nonmandatory reference guide is based on these OSHA regulations and, where appropriate, incorporates additional standards, codes, directives, and work practices that are recognized and accepted by DOE and the construction industry. It covers excavation, scaffolding, electricity, fire, signs/barricades, cranes/hoists/conveyors, hand and power tools, concrete/masonry, stairways/ladders, welding/cutting, motor vehicles/mechanical equipment, demolition, materials, blasting, steel erection, etc.

Food safety regulations: what we learned from the Fukushima nuclear accident

International Nuclear Information System (INIS)

Hamada, Nobuyuki; Ogino, Haruyuki

2012-01-01

On 11 March 2011, the magnitude-9.0 earthquake and a substantial tsunami struck off the northeast coast of Japan. The Fukushima nuclear power plants were inundated and stricken, followed by radionuclide releases outside the crippled reactors. Provisional regulation values for radioactivity in food and drink were set on 17 March and were adopted from the preset index values, except that for radioiodines in water and milk ingested by infants. For radiocesiums, uranium, plutonium and transuranic α emitters, index values were defined in all food and drink not to exceed a committed effective dose of 5 mSv/year. Index values for radioiodines were defined not to exceed a committed equivalent dose to the thyroid of 50 mSv/year, and set in water, milk and some vegetables, but not in other foodstuffs. Index values were calculated as radioactive concentrations of indicator radionuclides ( 131 I for radioiodines, 134 Cs and 137 Cs for radiocesiums) by postulating the relative radioactive concentration of coexisting radionuclides (e.g., 132 I, 133 I, 134 I, 135 I and 132 Te for 131 I). Surveys were thence conducted to monitor levels of 131 I, 134 Cs and 137 Cs. Provisional regulation values were exceeded in tap water, raw milk and some vegetables, and restrictions on distribution and consumption began on 21 March. Fish contaminated with radioiodines at levels of concern were then detected, so that the provisional regulation value for radioiodines in seafood adopted from that in vegetables were additionally set on 5 April. Overall, restrictions started within 25 days after the first excess in each food or drink item, and maximum levels were detected in leafy vegetables (54,100 Bq/kg for 131 I, and a total of 82,000 Bq/kg for 134 Cs and 137 Cs). This paper focuses on the logic behind such food safety regulations, and discusses its underlying issues. The outlines of the food monitoring results for 24,685 samples and the enforced restrictions will also be described. - Highlights

Project CHERISH (Children in Home Environments: Regulation To Improve Safety and Health). Final Report.

Science.gov (United States)

Grubb, Paul Dallas

In 1990, Project CHERISH (Children in Home Environments: Regulation to Increase Safety and Health) enabled the Texas Department of Human Services to implement and evaluate several innovative strategies to strengthen regulation of family day care homes. This report contains descriptions of those strategies, an evaluation of their efficacy, and…

76 FR 7107 - Quarterly Listings; Safety Zones, Security Zones, Special Local Regulations, Drawbridge Operation...

Science.gov (United States)

2011-02-09

... defined boundary for which regulations for vessels navigating within the area have been established by the...)...... 9/19/2008 USCG-2008-0814 San Diego, CA Safety Zones (Part 165)...... 9/6/2008 USCG-2008-0827 Ocean... (Part 165). USCG-2009-0402 Ocean City, NJ Safety Zones (Part 165)...... 10/10/2009 USCG-2009-0403...

Presenting information on regulation values improves the public’s sense of safety: Perceived mercury risk in fish and shellfish and its effects on consumption intention

Science.gov (United States)

Suzuki, Mai; Yamaguchi, Tomiko

2017-01-01

Risk communication aims to promote health and understanding through information exchange; however, explanations regarding the basis of regulation values for the public are insufficient. Moreover, it is unclear how information presentation affects the public’s sense of safety and their consumption intentions. We first investigated the relationship between perception of mercury-risk in fish and shellfish and individual attributes and knowledge. We then examined how presenting information on regulation values and primary factors regarding perception affected sense of safety toward regulations and food-consumption intentions. An online survey was conducted with Japanese individuals (N = 1148). Respondents were randomly assigned to one of three groups based on the presentation level of regulation values. People who frequently consumed tuna had a high perception of dread risk of mercury. This suggests that the dread risk perception of mercury does not determine tuna-type consumption behavior; rather, individuals’ consumption behavior determines dread risk perception of mercury. Among those with high tuna-type consumption, those receiving information that a safety factor of 10 times had been considered showed a significantly greater sense of safety than did the group that was not presented with information on regulation values (odds ratio (95% confidence interval): 2.04 (1.18–3.53), p values showed a weak but significantly positive correlation with excessive intake of tuna-type fish (odds ratio: 2.95 (0.93–9.32), p values increases sense of safety; however, it may also lead to excessive intake. PMID:29267301

75 FR 4305 - Regulatory Guidance Concerning the Applicability of the Federal Motor Carrier Safety Regulations...

Science.gov (United States)

2010-01-27

... review of, or preparation and transmission of, typed messages via wireless phones. Because of the safety... Secretary broad power in carrying out motor carrier safety statutes and regulations to ``prescribe.... Handheld or other wireless electronic devices that are brought into a CMV are considered ``additional...

The nuclear safety regulation in Japan and the response to changes of circumstances surrounding the nuclear electricity generation

International Nuclear Information System (INIS)

Hombu, K.; Hirota, M.; Taniguchi, T.; Tanaka, N.; Akimoto, S.

2001-01-01

The influences of external factors on nuclear safety are discussed in this paper, based on the views on the circumstances of nuclear electricity generation. The following external factors, which might have some potential impacts on nuclear safety, are selected for discussion: (1) The deregulation in the electricity generation industry; (2) The modification of approval/certification system in the regulation of electricity generation; (3) The influences on social atmosphere due to the occurrence of a series of troubles; (4) The government reform and the structural adjustment of industry and (5) Others. Our further discussion seems to focus on the following 2 issues: (a) Whether nuclear power and the other electrical sources should compete with each other for short term economical cost, or whether factors of cost stability and competitiveness as well as longer term energy supply security and global environmental issues ranging over several decades should be considered; (b) How to realize the appropriate regulation from the perspective of public acceptance and confidence (when a series of troubles occur) without imposing unnecessary burdens on industry and without jeopardizing safety. These issues may be common among many countries and can be widely discussed. (author)

Intelligent monitoring-based safety system of massage robot

Institute of Scientific and Technical Information of China (English)

胡宁; 李长胜; 王利峰; 胡磊; 徐晓军; 邹雲鹏; 胡玥; 沈晨

2016-01-01

As an important attribute of robots, safety is involved in each link of the full life cycle of robots, including the design, manufacturing, operation and maintenance. The present study on robot safety is a systematic project. Traditionally, robot safety is defined as follows: robots should not collide with humans, or robots should not harm humans when they collide. Based on this definition of robot safety, researchers have proposed ex ante and ex post safety standards and safety strategies and used the risk index and risk level as the evaluation indexes for safety methods. A massage robot realizes its massage therapy function through applying a rhythmic force on the massage object. Therefore, the traditional definition of safety, safety strategies, and safety realization methods cannot satisfy the function and safety requirements of massage robots. Based on the descriptions of the environment of massage robots and the tasks of massage robots, the present study analyzes the safety requirements of massage robots; analyzes the potential safety dangers of massage robots using the fault tree tool; proposes an error monitoring-based intelligent safety system for massage robots through monitoring and evaluating potential safety danger states, as well as decision making based on potential safety danger states; and verifies the feasibility of the intelligent safety system through an experiment.

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-10-15

The IAEA's Statute authorizes the Agency to 'establish or adopt... standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to 'establish or adopt... standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the

Product-based Safety Certification for Medical Devices Embedded Software.

Science.gov (United States)

Neto, José Augusto; Figueiredo Damásio, Jemerson; Monthaler, Paul; Morais, Misael

2015-01-01

Worldwide medical device embedded software certification practices are currently focused on manufacturing best practices. In Brazil, the national regulatory agency does not hold a local certification process for software-intensive medical devices and admits international certification (e.g. FDA and CE) from local and international industry to operate in the Brazilian health care market. We present here a product-based certification process as a candidate process to support the Brazilian regulatory agency ANVISA in medical device software regulation. Center of Strategic Technology for Healthcare (NUTES) medical device embedded software certification is based on a solid safety quality model and has been tested with reasonable success against the Class I risk device Generic Infusion Pump (GIP).

International cooperation for the development of consistent and stable transportation regulations to promote and enhance safety and security

International Nuclear Information System (INIS)

Strosnider, J.

2004-01-01

International commerce of radioactive materials crosses national boundaries, linking separate regulatory institutions with a common purpose and making it necessary for these institutions to work together in order to achieve common safety goals in a manner that does not place an undue burden on industry and commerce. Widespread and increasing use of radioactive materials across the world has led to increases in the transport of radioactive materials. The demand for consistency in the oversight of international transport has also increased to prevent unnecessary delays and costs associated with incongruent or redundant regulatory requirements by the various countries through which radioactive material is transported. The International Atomic Energy Agency (IAEA) is the authority for international regulation of transportation of radioactive materials responsible for promulgation of regulations and guidance for the establishment of acceptable methods of transportation for the international community. As such, the IAEA is seen as the focal point for consensus building between its Member States to develop consistency in transportation regulations and reviews and to ensure the safe and secure transport of radioactive material. International cooperation is also needed to ensure stability in our regulatory processes. Changes to transportation regulations should be based on an anticipated safety benefit supported by risk information and insights gained from continuing experience, evaluation, and research studies. If we keep safety as the principle basis for regulatory changes, regulatory stability will be enhanced. Finally, as we endeavour to maintain consistency and stability in our international regulations, we must be mindful of the new security challenges that lay before the international community as a result of a changing terrorist environment. Terrorism is a problem of global concern that also requires international cooperation and support, as we look for ways to

Moving beyond command-and-control: reflexivity in the regulation of occupational safety and health and the environment.

NARCIS (Netherlands)

Aalders, M.V.C.; Wilthagen, T.

1997-01-01

Direct or "command-and-control" regulation has had limited success in dealing with occupational health and safety and with environmental regulation. This lack of success has led policymakers to experiment with self-regulation as an alternative means of achieving the goals of social regulation. The

Schedules of Provisions of the IAEA Regulations for the Safe Transport of Radioactive Material (2009 Ed.). Safety Guide

International Nuclear Information System (INIS)

2014-01-01

This Safety Guide is issued in support of Regulations for the Safe Transport of Radioactive Material (IAEA Safety Standards Series No. TS-R-1, 2009 Edition). It lists the paragraph numbers of the Transport Regulations that are relevant for specified types of consignment, classified according to their UN numbers. It does not provide additional recommendations. The intended users are consignors and consignees, carriers, shippers, regulators, and end users involved in the transport of radioactive material. A person or organization intending to transport a particular type of consignment of radioactive material must meet requirements in all sections of the Transport Regulations. This Safety Guide aids users by providing a listing of the relevant requirements of the Transport Regulations for each type of radioactive material, package or shipment. Once a consignor has classified the radioactive material to be shipped, the appropriate UN number can be assigned and the paragraph numbers of the requirements that apply for the shipment can be found in the corresponding schedule

Trends in pharmacy staff's perception of patient safety in Swedish community pharmacies after re-regulation of conditions.

Science.gov (United States)

Kälvemark Sporrong, Sofia; Nordén-Hägg, Annika

2014-10-01

All changes in the regulation of pharmacies have an impact on the work carried out in pharmacies and also on patient safety, regardless of whether this is the intention or not. To compare staff apprehension regarding some aspects of patient safety and quality in community pharmacies prior to and after the 2009 changes in regulation of the Swedish community pharmacy market. Questionnaires targeted at pharmacy staff before and after the changes in regulation (in 2008, 2011/12, and 2012/13 respectively) used four identical items, making comparisons of some aspects possible. All four items demonstrated a significant decrease in the first survey after the changes as compared to before. In the second survey significant differences were found on the two items representing safety climate whereas the items representing team climate and management showed no significant differences. The comparison carried out in this study indicates a negative effect in Swedish community pharmacies on safety and quality issues, as experienced by pharmacy staff. It is recommended that the possible effects of healthcare reforms are assessed before implementation, in order to counteract conceivable decline in factors including patient safety and working conditions.

Development of safety evaluation methods and analysis codes applied to the safety regulations for the design and construction stage of fast breeder reactor

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

The purposes of this study are to develop the safety evaluation methods and analysis codes needed in the design and construction stage of fast breeder reactor (FBR). In JFY 2012, the following results are obtained. As for the development of safety evaluation methods needed in the safety examination conducted for the reactor establishment permission, development of the analysis codes, such as core damage analysis code, were carried out following the planned schedule. As for the development of the safety evaluation method needed for the risk informed safety regulation, the quantification technique of the event tree using the Continuous Markov chain Monte Carlo method (CMMC method) were studied. (author)

A Response to Proposed Equal Employment Opportunity Commission Regulations on Employer-Sponsored Health, Safety, and Well-Being Initiatives.

Science.gov (United States)

2016-03-01

The aim of this study was to identify areas of consensus in response to proposed Equal Employment Opportunity Commission Americans with Disabilities Act of 1990 and Genetic Information Nondiscrimination Act of 2008 regulations on employer-sponsored health, safety, and well-being initiatives. The consensus process included review of existing and proposed regulations, identification of key areas where consensus is needed, and a methodical consensus-building process. Stakeholders representing employees, employers, consulting organizations, and wellness providers reached consensus around five areas, including adequate privacy notice on how medical data are collected, used, and protected; effective, equitable use of inducements that influence participation in programs; observance of reasonable alternative standards; what constitutes reasonably designed programs; and the need for greater congruence between federal agency regulations. Employee health and well-being initiatives that are in accord with federal regulations are comprehensive, evidence-based, and are construed as voluntary by employees and regulators alike.

A Study on the Estimation Method of Risk Based Area for Jetty Safety Monitoring

Directory of Open Access Journals (Sweden)

Byeong-Wook Nam

2015-09-01

Full Text Available Recently, the importance of safety-monitoring systems was highlighted by the unprecedented collision between a ship and a jetty in Yeosu. Accordingly, in this study, we introduce the concept of risk based area and develop a methodology for a jetty safety-monitoring system. By calculating the risk based areas for a ship and a jetty, the risk of collision was evaluated. To calculate the risk based areas, we employed an automatic identification system for the ship, stopping-distance equations, and the regulation velocity near the jetty. In this paper, we suggest a risk calculation method for jetty safety monitoring that can determine the collision probability in real time and predict collisions using the amount of overlap between the two calculated risk based areas. A test was conducted at a jetty control center at GS Caltex, and the effectiveness of the proposed risk calculation method was verified. The method is currently applied to the jetty-monitoring system at GS Caltex in Yeosu for the prevention of collisions.

Safety Margins and Their Economical Value in a De-regulated Market

International Nuclear Information System (INIS)

Vidard, Michel

2002-01-01

The definition of safety margins is sometimes ambiguous. Depending on assumptions used to evaluate the evolution of plant parameters and on acceptance criteria, the same design could well turn out to have positive, zero, or negative margin for the same operating situation. Very often, considering that an optimized reactor would have to operate with zero margin compared to at least one safety criterion, designers or utilities considered in their analyses penalizing assumptions. This was done for example either considering reduced component capability or very high core peaking factors, the latter generally exceeding by far what would be anticipated in perturbed situations. This approach has three major drawbacks: -having a reasonable understanding of the real importance of safety margins is difficult, -if a non-conservatism is identified in a methodology, there is a high risk of being in a no-compliance situation from a regulatory standpoint, -it leads to a limitation on allowable electrical output and constraints on technical specifications for example. In a regulated market, such a situation can be tolerable as the final customer has to pay the extra financial burden in any case. In a de-regulated market, the situation is significantly different. The final customer can choose his supplier, and is likely to go to those offering the best prices, i.e. those making optimal use of their available resources. There is so a need for better understanding of real plant capabilities. Revisiting assumptions used for evaluating safety margins is so highly recommended, if not imperative, to electricity companies. This will helpful to reshape company strategies in case of evolution of market conditions. (author)

A double-regulated oncolytic adenovirus with improved safety for adenocarcinoma therapy

International Nuclear Information System (INIS)

Wei, Na; Fan, Jun Kai; Gu, Jin Fa; He, Ling Feng; Tang, Wen Hao; Cao, Xin; Liu, Xin Yuan

2009-01-01

Safety and efficiency are equally important to be considered in developing oncolytic adenovirus. Previously, we have reported that ZD55, an oncolytic adenovirus with the deletion of E1B-55K gene, exhibited potent antitumor activity. In this study, to improve the safety of ZD55, we utilized MUC1 promoter to replace the native promoter of E1A on the basis of ZD55, and generated a double-regulated adenovirus, named MUD55. Our data demonstrated that the expression of early and late genes of MUD55 was both reduced in MUC1-negative cells, resulting in its stricter glandular-tumor selective progeny production. The cytopathic effect of MUD55 was about 10-fold lower than mono-regulated adenovirus ZD55 or Ad.MUC1 in normal cells and not obviously attenuated in glandular tumor cells. Moreover, MUD55 showed the least liver toxicity when administrated by intravenous injection in nude mice. These results indicate that MUD55 could be a promising candidate for the treatment of adenocarcinoma.

The costs of uncertainty: regulating health and safety in the Canadian uranium industry

International Nuclear Information System (INIS)

Robinson, I.

1982-04-01

Federalism, and particularly federal/provincial jurisdictional relationships, have led to considerable uncertainty in the regulation of occupational health and safety and of environmental protection in the Canadian uranium mining industry. The two principal uranium producing provinces in Canada are Saskatchewan and Ontario. Since 1978, in an attempt to avoid constitutional issues, both these provinces and the federal government as well have proceeded unilaterally with health and safety reforms for the industry. In Saskatchewan this has resulted in areas of overlapping jurisdiction, which have led to uncertainty over the legal enforceability of the provincial regulations. In Ontario, the province has left significant gaps in the protection of both workers and the environment. Little progress can be expected in eliminating these gaps and overlaps until the current administrative and jurisdictional arrangements are understood

Computer-based and web-based radiation safety training

Energy Technology Data Exchange (ETDEWEB)

Owen, C., LLNL

1998-03-01

The traditional approach to delivering radiation safety training has been to provide a stand-up lecture of the topic, with the possible aid of video, and to repeat the same material periodically. New approaches to meeting training requirements are needed to address the advent of flexible work hours and telecommuting, and to better accommodate individuals learning at their own pace. Computer- based and web-based radiation safety training can provide this alternative. Computer-based and web- based training is an interactive form of learning that the student controls, resulting in enhanced and focused learning at a time most often chosen by the student.

The challenge of defining risk-based metrics to improve food safety: inputs from the BASELINE project.

Science.gov (United States)

Manfreda, Gerardo; De Cesare, Alessandra

2014-08-01

In 2002, the Regulation (EC) 178 of the European Parliament and of the Council states that, in order to achieve the general objective of a high level of protection of human health and life, food law shall be based on risk analysis. However, the Commission Regulation No 2073/2005 on microbiological criteria for foodstuffs requires that food business operators ensure that foodstuffs comply with the relevant microbiological criteria. Such criteria define the acceptability of a product, a batch of foodstuffs or a process, based on the absence, presence or number of micro-organisms, and/or on the quantity of their toxins/metabolites, per unit(s) of mass, volume, area or batch. The same Regulation describes a food safety criterion as a mean to define the acceptability of a product or a batch of foodstuff applicable to products placed on the market; moreover, it states a process hygiene criterion as a mean indicating the acceptable functioning of the production process. Both food safety criteria and process hygiene criteria are not based on risk analysis. On the contrary, the metrics formulated by the Codex Alimentarius Commission in 2004, named Food Safety Objective (FSO) and Performance Objective (PO), are risk-based and fit the indications of Regulation 178/2002. The main aims of this review are to illustrate the key differences between microbiological criteria and the risk-based metrics defined by the Codex Alimentarius Commission and to explore the opportunity and also the possibility to implement future European Regulations including PO and FSO as supporting parameters to microbiological criteria. This review clarifies also the implications of defining an appropriate level of human protection, how to establish FSO and PO and how to implement them in practice linked to each other through quantitative risk assessment models. The contents of this review should clarify the context for application of the results collected during the EU funded project named BASELINE (www

Note n. SD3-DEM-01 regulations procedures relative to the based nuclear installations dismantling

International Nuclear Information System (INIS)

2003-02-01

This note aims to define the regulations procedures relative to the safety of based nuclear installations dismantling defined by the decree of the 11 december 1963 modified. The first part describes the two main phases of a based nuclear installation life, the operating and the dismantling phase. The second part is devoted to the procedures. (A.L.B.)

Nuclear safety regulation on nuclear safety equipment activities in relation to human and organizational factors

International Nuclear Information System (INIS)

Li Tianshu

2013-01-01

Based on years of knowledge in nuclear safety supervision and experience of investigating and dealing with violation events in repair welding of DFHM, this paper analyzes major faults in manufacturing and maintaining activities of nuclear safety equipment in relation to human and organizational factors. It could be deducted that human and organizational factors has definitely become key features in the development of nuclear energy and technology. Some feasible measures to reinforce supervision on nuclear safety equipment activities have also been proposed. (author)

Food Safety Regulation and Firm Productivity: Evidence from the French Food Industry

OpenAIRE

Requillart, Vincent; Nauges, Celine; Simioni, Michel; Bontemps, Christophe

2012-01-01

The purpose of this article is to assess whether food safety regulations imposed by the European Union in the 2000s may have induced a slow-down in the productivity of firms in the food processing sector. The impact of regulations on costs and productivity has seldom been studied. This article contributes to the literature by measuring productivity change using a panel of French food processing firms for the years 1996 to 2006. To do so, we develop an original iterative testing procedure b...

33 CFR 165.T09-1080 - Safety Zone and Regulated Navigation Area, Chicago Sanitary and Ship Canal, Romeoville, IL.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Safety Zone and Regulated Navigation Area, Chicago Sanitary and Ship Canal, Romeoville, IL. 165.T09-1080 Section 165.T09-1080 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) PORTS AND WATERWAYS SAFETY REGULATED NAVIGATION AREAS AND LIMITED...

Guidelines on the safety of light-based home-use hair removal devices from the European Society for Laser Dermatology

DEFF Research Database (Denmark)

Town, Graham; Ash, C; Dierickx, C

2012-01-01

. These guidelines provide a definition of light-based home-use technology, to inform healthcare professionals about home-use light-based technology and encourage manufacturers wishing to sell in Europe to adopt 'best practice'. The review presents the current status on standards and regulation issues and considers...... home-use safety issues, encompassing human, device and electrical safety, given risks to the eyes and skin from optical radiation both to the consumer and persons in the vicinity. Proposed technical measurement methodology is considered with focus on recognized critical parameters for the safe use...... of light-based hair removal technology including recording the technical performance and safety claims of a range of home-use hair removal devices. The literature review emphasizes potential adverse incidents and safety aspects of treating cosmetic conditions, such as unwanted hair growth. Although some...

Food safety regulations in Australia and New Zealand Food Standards.

Science.gov (United States)

Ghosh, Dilip

2014-08-01

Citizens of Australia and New Zealand recognise that food security is a major global issue. Food security also affects Australia and New Zealand's status as premier food exporting nations and the health and wellbeing of the Australasian population. Australia is uniquely positioned to help build a resilient food value chain and support programs aimed at addressing existing and emerging food security challenges. The Australian food governance system is fragmented and less transparent, being largely in the hands of government and semi-governmental regulatory authorities. The high level of consumer trust in Australian food governance suggests that this may be habitual and taken for granted, arising from a lack of negative experiences of food safety. In New Zealand the Ministry of Primary Industries regulates food safety issues. To improve trade and food safety, New Zealand and Australia work together through Food Standards Australia New Zealand (FSANZ) and other co-operative agreements. Although the potential risks to the food supply are dynamic and constantly changing, the demand, requirement and supply for providing safe food remains firm. The Australasian food industry will need to continually develop its system that supports the food safety program with the help of scientific investigations that underpin the assurance of what is and is not safe. The incorporation of a comprehensive and validated food safety program is one of the total quality management systems that will ensure that all areas of potential problems are being addressed by industry. © 2014 Society of Chemical Industry.

Safety management of software-based equipment

CERN Document Server

Boulanger, Jean-Louis

2013-01-01

A review of the principles of the safety of software-based equipment, this book begins by presenting the definition principles of safety objectives. It then moves on to show how it is possible to define a safety architecture (including redundancy, diversification, error-detection techniques) on the basis of safety objectives and how to identify objectives related to software programs. From software objectives, the authors present the different safety techniques (fault detection, redundancy and quality control). "Certifiable system" aspects are taken into account throughout the book. C

A primer of drug safety surveillance: an industry perspective. Part I: Information flow, new drug development, and federal regulations.

Science.gov (United States)

Allan, M C

1992-01-01

To place the fundamentals of clinical drug safety surveillance in a conceptual framework that will facilitate understanding and application of adverse drug event data to protect the health of the public and support a market for pharmaceutical manufacturers' products. Part I of this series provides a background for the discussion of drug safety by defining the basic terms and showing the flow of safety information through a pharmaceutical company. The customers for adverse drug event data are identified to provide a basis for providing quality service. The development of a drug product is briefly reviewed to show the evolution of safety data. Drug development and safety are defined by federal regulations. These regulations are developed by the FDA with information from pharmaceutical manufacturers. The intent of the regulations and the accompanying guidelines is described. An illustration from the news media is cited to show an alternative, positive approach to handling an adverse event report. This review uses primary sources from the federal laws (regulations), commentaries, and summaries. Very complex topics are briefly summarized in the text and additional readings are presented in an appendix. Secondary sources, ranging from newspaper articles to judicial summaries, illustrate the interpretation of adverse drug events and opportunities for drug safety surveillance intervention. The reference materials used were articles theoretically or practically applicable in the day-to-day practice of drug safety surveillance. The role of clinical drug safety surveillance in product monitoring and drug development is described. The process of drug safety surveillance is defined by the Food and Drug Administration regulations, product labeling, product knowledge, and database management. Database management is subdivided into the functions of receipt, retention, retrieval, and review of adverse event reports. Emphasis is placed on the dynamic interaction ;of the components

NRC safety research in support of regulation, 1986

International Nuclear Information System (INIS)

1987-09-01

This report is the second in a series of annual reports responding to congressional inquiries as to the utilization of nuclear regulatory research. NUREG-1175, ''NRC Safety Research in Support of Regulation,'' published in May 1986, reported major research accomplishments between about FY 1980 and FY 1985. This report narrates the accomplishments of FY 1986 and does not restate earlier accomplishments. Earlier research results are mentioned in the context of current results in the interest of continuity. Both the direct contributions to scientific and technical knowledge and their regulatory applications, when there has been a definite regulatory outcome during FY 1986, have been described

Upholding science in health, safety and environmental risk assessments and regulations

International Nuclear Information System (INIS)

Aschner, Michael; Autrup, Herman N.; Berry, Sir Colin L.; Boobis, Alan R.; Cohen, Samuel M.; Creppy, Edmond E.; Dekant, Wolfgang; Doull, John; Galli, Corrado L.; Goodman, Jay I.; Gori, Gio B.; Greim, Helmut A.; Joudrier, Philippe

2016-01-01

A public appeal has been advanced by a large group of scientists, concerned that science has been misused in attempting to quantify and regulate unmeasurable hazards and risks. The appeal recalls that science is unable to evaluate hazards that cannot be measured, and that science in such cases should not be invoked to justify risk assessments in health, safety and environmental regulations. The appeal also notes that most national and international statutes delineating the discretion of regulators are ambiguous about what rules of evidence ought to apply. Those statutes should be revised to ensure that the evidence for regulatory action is grounded on the standards of the scientific method, whenever feasible. When independent scientific evidence is not possible, policies and regulations should be informed by publicly debated trade-offs between socially desirable uses and social perceptions of affordable precaution. This article explores the premises, implications and actions supporting the appeal and its objectives.

Food safety regulatory systems in Europe and China：A study of how co-regulation can improve regulatory effectiveness

Institute of Scientific and Technical Information of China (English)

Kevin Chen; WANG Xin-xin; SONG Hai-ying

2015-01-01

Food safety has received a great deal of attention in both developed and developing countries in recent years. In China, the numerous food scandals and scares that have struck over the past decade have spurred signiifcant food safety regulatory reform, which has been increasingly oriented towards the public-private partnership model adopted by the Europe Union’s (EU) food safety regulatory system. This paper analyzes the development of both the EU’s and China’s food safety regu-latory systems, identiifes the current chalenges for China and additionaly considers the role of public-private partnership. The success of co-regulation in the food regulatory system would bring signiifcant beneifts and opportunities for China. Finaly, this paper recommends additional measures like training and grants to improve the private’s sector effectiveness in co-regulating China’s food safety issues.

Health and safety regulation of uranium mining and milling

International Nuclear Information System (INIS)

Dory, A.B.

1980-07-01

The Canadian Atomic Energy Control Board licenses all nuclear facilities in Canada, including uranium mines and mills. The protection of health, safety and the environment is one of the requirements of each licence. A limit of 4 Working Level Months exposure to radon and radon daughters annually has been set, and guidelines for weekly or more frequent workplace monitoring have been established. Personal monitoring devices are being tested, and thermoluminescent dosimeters are to be introduced. The Board reviews its licensees' ventilation plans continuously. The staged licensing process involves the granting of the following documents: 1) ore removal; 2) underground exploration permit; 3) site and construction approval; 4) mining facility operating licence; 5) shut-down approval. Compliance with regulations and licence conditions is monitored mainly by inspectors appointed by provincial agencies, with Board staff exercising auditing fuctions. The Board involves the workers directly with their own health and safety by sending their unions copies of all relevant documents and inviting comments

76 FR 27897 - Security and Safety Zone Regulations, Large Passenger Vessel Protection, Captain of the Port...

Science.gov (United States)

2011-05-13

... DEPARTMENT OF HOMELAND SECURITY Coast Guard 33 CFR Part 165 [Docket No. USCG-2011-0342] Security and Safety Zone Regulations, Large Passenger Vessel Protection, Captain of the Port Columbia River... will enforce the security and safety zone in 33 CFR 165.1318 for large passenger vessels operating in...

75 FR 16370 - Regulated Navigation Areas, Safety Zones, Security Zones; Deepwater Ports in Boston Captain of...

Science.gov (United States)

2010-04-01

... rule under Executive Order 13045, Protection of Children from Environmental Health Risks and Safety Risks. This rule is not an economically significant rule and would not create an environmental risk to...] RIN 1625-AA00, RIN 1625-AA11 Regulated Navigation Areas, Safety Zones, Security Zones; Deepwater Ports...

Qualification of FPGA-Based Safety-Related PRM System

International Nuclear Information System (INIS)

Miyazaki, Tadashi; Oda, Naotaka; Goto, Yasushi; Hayashi, Toshifumi

2011-01-01

Toshiba has developed Non-rewritable (NRW) Field Programmable Gate Array (FPGA)-based safety-related Instrumentation and Control (I and C) system. Considering application to safety-related systems, nonvolatile and non-rewritable FPGA which is impossible to be changed after once manufactured has been adopted in Toshiba FPGA-based system. FPGA is a device which consists only of basic logic circuits, and FPGA performs defined processing which is configured by connecting the basic logic circuit inside the FPGA. FPGA-based system solves issues existing both in the conventional systems operated by analog circuits (analog-based system) and the systems operated by central processing unit (CPU-based system). The advantages of applying FPGA are to keep the long-life supply of products, improving testability (verification), and to reduce the drift which may occur in analog-based system. The system which Toshiba developed this time is Power Range Neutron Monitor (PRM). Toshiba is planning to expand application of FPGA-based technology by adopting this development process to the other safety-related systems such as RPS from now on. Toshiba developed a special design process for NRW-FPGA-based safety-related I and C systems. The design process resolves issues for many years regarding testability of the digital system for nuclear safety application. Thus, Toshiba NRW-FPGA-based safety-related I and C systems has much advantage to be a would standard of the digital systems for nuclear safety application. (author)

Risk Level Based Management System: a control banding model for occupational health and safety risk management in a highly regulated environment

Energy Technology Data Exchange (ETDEWEB)

Zalk, D; Kamerzell, R; Paik, S; Kapp, J; Harrington, D; Swuste, P

2009-05-27

The Risk Level Based Management System (RLBMS) is an occupational risk management (ORM) model that focuses occupational safety, hygeiene, and health (OSHH) resources on the highest risk procedures at work. This article demonstrates the model's simplicity through an implementation within a heavily regulated research institution. The model utilizes control banding strategies with a stratification of four risk levels (RLs) for many commonly performed maintenance and support activities, characterizing risk consistently for comparable tasks. RLBMS creates an auditable tracking of activities, maximizes OSHH professional field time, and standardizes documentation and control commensurate to a given task's RL. Validation of RLs and their exposure control effectiveness is collected in a traditional quantitative collection regime for regulatory auditing. However, qualitative risk assessment methods are also used within this validation process. Participatory approaches are used throughout the RLBMS process. Workers are involved in all phases of building, maintaining, and improving this model. This work participation also improves the implementation of established controls.

Prescribing safety, negotiating expertise

International Nuclear Information System (INIS)

Rolina, Gregory

2010-01-01

Owing to their presumed impact on the safety of high-risk installations, the interactions between regulators and the regulated are a major but seldom explored subject of research in risk management. A study by experts on human and organizational factors in nuclear safety sheds light on the various phases (and their effects) of the process whereby experts produce assessments. Light is shed on a 'negotiated expertise' typical of the French style of safety regulations in nuclear installations. It is based on an ongoing technical dialog between experts and operators ('French cooking' for Anglo-Saxons). This analysis of 'expertise' and thus of the 'logics of action' implemented by experts proposes a typology of actions that can be transposed to other sorts of risk or other fields of activity. It hands us the keys for understanding a very contemporary activity. (author)

Protectionism or Legitimate Regulations: What can Trade Partners Expect from the New US Food Safety Regime?

OpenAIRE

Nakuja, T.; Kerr, William A.

2013-01-01

In January 2011, the US passed the Food Safety Modernization Act (FSMA) which represents a major legislative initiative to revise and strengthen the regulatory regime pertaining to foodborne illness and contamination. The tightening of the regulatory regime was justified on the basis of a number of high-profile foodborne disease incidents, which are claimed to have undermined public confidence in the US food safety system. While tightening food safety regulations inevitably increase barriers ...

A nuclear safety in 21 century

International Nuclear Information System (INIS)

Osmachkin, V.S.

2003-01-01

In the paper some topics of nuclear safety are discussed, namely current situation in the world energetics and a potential of nuclear energy for sustainable development of the world, Nuclear Safety Standards and modern trends in Safety Regulation, Radiation Protection Standards are rather conservative, are based on disputable approaches and have to be more pragmatic, necessity to overcome the syndromes of awful consequences of nuclear accidents at nuclear plants, residual risks of nuclear accidents have to be covered by clear compulsory insurance actions. It is shown, that now it is worthwhile to consider efficiency of existing methods of nuclear safety regulation. It is possible, that an idea of guaranteed safety [1] could become a new approach to nuclear safety. It is based on practically total elimination of severe accidents and insurance of residual risks of nuclear accidents. The realization of such idea necessitates the consideration of all spectrum of initiating events, human errors and man-made actions, more realistically predicting consequences of accidents and the probable economical detriments. It will be a benefit for gaining public support to nuclear power. (author)

Nuclear power reactor safety

International Nuclear Information System (INIS)

Pon, G.A.

1976-10-01

This report is based on the Atomic Energy of Canada Limited submission to the Royal Commission on Electric Power Planning on the safety of CANDU reactors. It discusses normal operating conditions, postulated accident conditions, and safety systems. The release of radioactivity under normal and accident conditions is compared to the limits set by the Atomic Energy Control Regulations. (author)

Implementation of an indicator-based safety management system for the EnKK NPP's

International Nuclear Information System (INIS)

Bassing, G.; Nasellu, M.; Ritter, J.

2004-01-01

This presentation at the Eurosafe Berlin 2004 will give an overview of the activities on safety management of EnBW Kernkraft GmbH taken up with a notifiable event in August 2001 at KKP 2 nuclear site. After this event EnBW announced the development and introduction of an indicator-based safety management system (SMS) at all sites of its nuclear power plants. A SMS team with members from all NPP sites was built which had to analyse all processes based on the DIN EN ISO 9000 philosophy and to control them by indicators. The regulatory authorities and their experts would accompany this process in a suitable fashion and monitor and review it after its introduction. This presentation shows the process during the development of the system, the status of its introduction and the general involvement of the regulator. (orig.)

Risk-based safety performance indicators for nuclear power plants

International Nuclear Information System (INIS)

Chakraborty, S.; Prohaska, G.; Flodin, Y.; Grint, G.; Habermacher, H.; Hallman, A.; Isasia, R.; Melendez, E.; Verduras, E.; Karsa, Z.; Khatib-Rahbar, M.; Koeberlein, K.; Schwaeger, C.; Matahri, N.; Moravcik, I.; Tkac, M.; Preston, J.

2003-01-01

In a Concerted Action (CA), sponsored by the European Commission within its 5th Framework Program, a consortium of eleven partners from eight countries has reviewed and evaluated the application of Safety Performance Indicators (SPIs), which - in combination with other tools - can be used to monitor and improve the safety of nuclear power plants. The project was aimed at identification of methods that can be used in a risk-informed regulatory system and environment, and to exploit PSA techniques for the development and use of meaningful additional/alternative SPIs. The CA included the review of existing indicator systems, and the collection of information on the experience from indicator systems by means of a specific questionnaire. One of the most important and challenging issues for nuclear plant owners and/or regulators is to recognize early signs of deterioration in safety performance, caused by influences from management, organization and safety culture (MOSC), before actual events and/or mishaps take place. Most of the existing SPIs as proposed by various organizations are considered as 'lagging' indicators, that is, they are expected to show an impact only when a downward trend has already started. Furthermore, most of the available indicators are at a relatively high level, such that they will not provide useful information on fundamental weaknesses causing the problem in the first place. Regulators' and utilities' views on the use of a Safety Performance Indicator System have also been a part of the development of the CA. (author)

Jefferson Lab IEC 61508/61511 Safety PLC Based Safety System

International Nuclear Information System (INIS)

Mahoney, Kelly; Robertson, Henry

2009-01-01

This paper describes the design of the new 12 GeV Upgrade Personnel Safety System (PSS) at the Thomas Jefferson National Accelerator Facility (TJNAF). The new PSS design is based on the implementation of systems designed to meet international standards IEC61508 and IEC 61511 for programmable safety systems. In order to meet the IEC standards, TJNAF engineers evaluated several SIL 3 Safety PLCs before deciding on an optimal architecture. In addition to hardware considerations, software quality standards and practices must also be considered. Finally, we will discuss R and D that may lead to both high safety reliability and high machine availability that may be applicable to future accelerators such as the ILC.

76 FR 14590 - Defense Federal Acquisition Regulation Supplement; Safety of Facilities, Infrastructure, and...

Science.gov (United States)

2011-03-17

... makes it unlikely that a small business could afford to sustain the infrastructure required to perform...-AG73 Defense Federal Acquisition Regulation Supplement; Safety of Facilities, Infrastructure, and... facilities, infrastructure, and equipment that are intended for use by military or civilian personnel of the...

Safety prediction for basic components of safety-critical software based on static testing

International Nuclear Information System (INIS)

Son, H.S.; Seong, P.H.

2000-01-01

The purpose of this work is to develop a safety prediction method, with which we can predict the risk of software components based on static testing results at the early development stage. The predictive model combines the major factor with the quality factor for the components, which are calculated based on the measures proposed in this work. The application to a safety-critical software system demonstrates the feasibility of the safety prediction method. (authors)

Determination of Safety Performance Grade of NPP Using Integrated Safety Performance Assessment (ISPA) Program

International Nuclear Information System (INIS)

Chung, Dae Wook

2011-01-01

Since the beginning of 2000, the safety regulation of nuclear power plant (NPP) has been challenged to be conducted more reasonable, effective and efficient way using risk and performance information. In the United States, USNRC established Reactor Oversight Process (ROP) in 2000 for improving the effectiveness of safety regulation of operating NPPs. The main idea of ROP is to classify the NPPs into 5 categories based on the results of safety performance assessment and to conduct graded regulatory programs according to categorization, which might be interpreted as 'Graded Regulation'. However, the classification of safety performance categories is highly comprehensive and sensitive process so that safety performance assessment program should be prepared in integrated, objective and quantitative manner. Furthermore, the results of assessment should characterize and categorize the actual level of safety performance of specific NPP, integrating all the substantial elements for assessing the safety performance. In consideration of particular regulatory environment in Korea, the integrated safety performance assessment (ISPA) program is being under development for the use in the determination of safety performance grade (SPG) of a NPP. The ISPA program consists of 6 individual assessment programs (4 quantitative and 2 qualitative) which cover the overall safety performance of NPP. Some of the assessment programs which are already implemented are used directly or modified for incorporating risk aspects. The others which are not existing regulatory programs are newly developed. Eventually, all the assessment results from individual assessment programs are produced and integrated to determine the safety performance grade of a specific NPP

Development of Taiwan's strategies for regulating nanotechnology-based pharmaceuticals harmonized with international considerations.

Science.gov (United States)

Guo, Jiun-Wen; Lee, Yu-Hsuan; Huang, Hsiau-Wen; Tzou, Mei-Chyun; Wang, Ying-Jan; Tsai, Jui-Chen

2014-01-01

Nanotechnology offers potential in pharmaceuticals and biomedical developments for improving drug delivery systems, medical imaging, diagnosis, cancer therapy, and regenerative medicine. Although there is no international regulation or legislation specifically for nanomedicine, it is agreed worldwide that considerably more attention should be paid to the quality, safety, and efficacy of nanotechnology-based drugs. The US Food and Drug Administration and the European Medicines Agency have provided several draft regulatory guidance and reflection papers to assist the development of nanomedicines. To cope with the impact of nanotechnology and to foster its pharmaceutical applications and development in Taiwan, this article reviews the trends of regulating nanotechnology-based pharmaceuticals in the international community and proposes strategies for Taiwan's regulation harmonized with international considerations. The draft regulatory measures include a chemistry, manufacturing, and controls (CMC) review checklist and guidance for CMC review of liposomal products. These have been submitted for discussion among an expert committee, with membership comprised of multidisciplinary academia, research institutions, the pharmaceutical industry, and regulators, and are currently approaching final consensus. Once a consensus is reached, these mechanisms will be recommended to the Taiwan Food and Drug Administration for jurisdiction and may be initiated as the starting point for regulating nanotechnology-based pharmaceuticals in Taiwan.

A task management system for compliance with health, safety, and environmental regulations

International Nuclear Information System (INIS)

Crump, J.J.; O'Gorman, T.P.

1992-01-01

Shell Western E and P Inc. (SWEPI) has developed a new computer system to help it comply with health, safety, and environmental (HS and E) regulations. It is a task management system that functions at the detailed inventory level. It schedules work, instructs operations, and records compliance status. This article discusses design and development of the system

Safety prediction for basic components of safety critical software based on static testing

International Nuclear Information System (INIS)

Son, H.S.; Seong, P.H.

2001-01-01

The purpose of this work is to develop a safety prediction method, with which we can predict the risk of software components based on static testing results at the early development stage. The predictive model combines the major factor with the quality factor for the components, both of which are calculated based on the measures proposed in this work. The application to a safety-critical software system demonstrates the feasibility of the safety prediction method. (authors)

Field Programmable Gate Array-based I and C Safety System

International Nuclear Information System (INIS)

Kim, Hyun Jeong; Kim, Koh Eun; Kim, Young Geul; Kwon, Jong Soo

2014-01-01

Programmable Logic Controller (PLC)-based I and C safety system used in the operating nuclear power plants has the disadvantages of the Common Cause Failure (CCF), high maintenance costs and quick obsolescence, and then it is necessary to develop the other platform to replace the PLC. The Field Programmable Gate Array (FPGA)-based Instrument and Control (I and C) safety system is safer and more economical than Programmable Logic Controller (PLC)-based I and C safety system. Therefore, in the future, FPGA-based I and C safety system will be able to replace the PLC-based I and C safety system in the operating and the new nuclear power plants to get benefited from its safety and economic advantage. FPGA-based I and C safety system shall be implemented and verified by applying the related requirements to perform the safety function

Field Programmable Gate Array-based I and C Safety System

Energy Technology Data Exchange (ETDEWEB)

Kim, Hyun Jeong; Kim, Koh Eun; Kim, Young Geul; Kwon, Jong Soo [KEPCO, Daejeon (Korea, Republic of)

2014-08-15

Programmable Logic Controller (PLC)-based I and C safety system used in the operating nuclear power plants has the disadvantages of the Common Cause Failure (CCF), high maintenance costs and quick obsolescence, and then it is necessary to develop the other platform to replace the PLC. The Field Programmable Gate Array (FPGA)-based Instrument and Control (I and C) safety system is safer and more economical than Programmable Logic Controller (PLC)-based I and C safety system. Therefore, in the future, FPGA-based I and C safety system will be able to replace the PLC-based I and C safety system in the operating and the new nuclear power plants to get benefited from its safety and economic advantage. FPGA-based I and C safety system shall be implemented and verified by applying the related requirements to perform the safety function.

The UK system for regulating the long-term safety of radioactive waste disposal

International Nuclear Information System (INIS)

Duncan, A.

1997-01-01

The general system is described for regulation of disposal of solid, long-lived radioactive wastes. The relevant Government policy is outlined, and the framework of legislation and arrangements for implementation, the associated guidance produced by regulatory bodies and the approach to assessment by regulators of a safety case for radioactive waste disposal are reported. Also, for the purposes of discussion in the Workshop, some of the practical issues are considered which are still in development in the UK in regard to regulatory methodology. (author)

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Arabic Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-07-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Chinese Edition)

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-03-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (French Edition)

International Nuclear Information System (INIS)

2013-01-01

The IAEA's Statute authorizes the Agency to ''establish or adopt standards of safety for protection of health and minimization of danger to life and property'' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Chinese Edition)

International Nuclear Information System (INIS)

2013-01-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Regulations for the Safe Transport of Radioactive Material. 2012 Edition. Specific Safety Requirements (Arabic Edition)

International Nuclear Information System (INIS)

2012-01-01

The IAEA's Statute authorizes the Agency to 'establish or adopt' standards of safety for protection of health and minimization of danger to life and property' - standards that the IAEA must use in its own operations, and which States can apply by means of their regulatory provisions for nuclear and radiation safety. The IAEA does this in consultation with the competent organs of the United Nations and with the specialized agencies concerned. A comprehensive set of high quality standards under regular review is a key element of a stable and sustainable global safety regime, as is the IAEA's assistance in their application. The IAEA commenced its safety standards programme in 1958. The emphasis placed on quality, fitness for purpose and continuous improvement has led to the widespread use of the IAEA standards throughout the world. The Safety Standards Series now includes unified Fundamental Safety Principles, which represent an international consensus on what must constitute a high level of protection and safety. With the strong support of the Commission on Safety Standards, the IAEA is working to promote the global acceptance and use of its standards. Standards are only effective if they are properly applied in practice. The IAEA's safety services encompass design, siting and engineering safety, operational safety, radiation safety, safe transport of radioactive material and safe management of radioactive waste, as well as governmental organization, regulatory matters and safety culture in organizations. These safety services assist Member States in the application of the standards and enable valuable experience and insights to be shared. Regulating safety is a national responsibility, and many States have decided to adopt the IAEA's standards for use in their national regulations. For parties to the various international safety conventions, IAEA standards provide a consistent, reliable means of ensuring the effective fulfilment of obligations under the conventions

Fog lamp regulation as a safety measure to reduce risk in fog conditions.

NARCIS (Netherlands)

Oppe, S.

1992-01-01

This short note summarizes the relevant aspects for a decision concerning the fog lamp use regulation. Most motorway accidents in the Netherlands took place in fog conditions in the early morning hours. The safety problem in fog conditions is a serious problem caused by bad driving behaviour. The

Catalogue and classification of technical safety standards, rules and regulations for nuclear power reactors and nuclear fuel cycle facilities

International Nuclear Information System (INIS)

Fichtner, N.; Becker, K.; Bashir, M.

1977-01-01

The present report is an up-dated version of the report 'Catalogue and Classification of Technical Safety Rules for Light-water Reactors and Reprocessing Plants' edited under code No EUR 5362e, August 1975. Like the first version of the report, it constitutes a catalogue and classification of standards, rules and regulations on land-based nuclear power reactors and fuel cycle facilities. The reasons for the classification system used are given and discussed

Is Model-Based Development a Favorable Approach for Complex and Safety-Critical Computer Systems on Commercial Aircraft?

Science.gov (United States)

Torres-Pomales, Wilfredo

2014-01-01

A system is safety-critical if its failure can endanger human life or cause significant damage to property or the environment. State-of-the-art computer systems on commercial aircraft are highly complex, software-intensive, functionally integrated, and network-centric systems of systems. Ensuring that such systems are safe and comply with existing safety regulations is costly and time-consuming as the level of rigor in the development process, especially the validation and verification activities, is determined by considerations of system complexity and safety criticality. A significant degree of care and deep insight into the operational principles of these systems is required to ensure adequate coverage of all design implications relevant to system safety. Model-based development methodologies, methods, tools, and techniques facilitate collaboration and enable the use of common design artifacts among groups dealing with different aspects of the development of a system. This paper examines the application of model-based development to complex and safety-critical aircraft computer systems. Benefits and detriments are identified and an overall assessment of the approach is given.

Mapping medical marijuana: state laws regulating patients, product safety, supply chains and dispensaries, 2017.

Science.gov (United States)

Klieger, Sarah B; Gutman, Abraham; Allen, Leslie; Pacula, Rosalie Liccardo; Ibrahim, Jennifer K; Burris, Scott

2017-12-01

(1) To describe open source legal data sets, created for research use, that capture the key provisions of US state medical marijuana laws. The data document how state lawmakers have regulated a medicine that remains, under federal law, a Schedule I illegal drug with no legitimate medical use. (2) To demonstrate the variability that exists across states in rules governing patient access, product safety and dispensary practice. Two legal researchers collected and coded state laws governing marijuana patients, product safety and dispensaries in effect on 1 February 2017, creating three empirical legal data sets. We used summary tables to identify the variation in specific statutory provisions specified in each state's medical marijuana law as it existed on 1 February 2017. We compared aspects of these laws to the traditional Federal approach to regulating medicine. Full data sets, codebooks and protocols are available through the Prescription Drug Abuse Policy System (http://www.pdaps.org/; Archived at http://www.webcitation.org/6qv5CZNaZ on 2 June 2017). Twenty-eight states (including the District of Columbia) have authorized medical marijuana. Twenty-seven specify qualifying diseases, which differ across states. All states protect patient privacy; only 14 protect patients against discrimination. Eighteen states have mandatory product safety testing before any sale. While the majority have package/label regulations, states have a wide range of specific requirements. Most regulate dispensaries (25 states), with considerable variation in specific provisions such as permitted product supply sources number of dispensaries per state and restricting proximity to various types of location. The federal ban in the United States on marijuana has resulted in a patchwork of regulatory strategies that are not uniformly consistent with the approach usually taken by the Federal government and whose effectiveness remains unknown. © 2017 Society for the Study of Addiction.

Harmonization of legislation and regulations to achieve food safety: US and Canada perspective.

Science.gov (United States)

Keener, Larry; Nicholson-Keener, Sophia M; Koutchma, Tatiana

2014-08-01

Trade in food and food ingredients among the nations of the world is rapidly expanding and, with this expansion, new supply chain partners, from globally disparate geographic regions, are being enrolled. Food and food ingredients are progressively sourced more from lesser developed nations. Food safety incidents in the USA and Canada show a high unfavorable correlation between illness outbreaks and imported foods. In the USA, for example, foodborne disease outbreaks caused by imported food appeared to rise in 2009 and 2010, and nearly half of the outbreaks, associated with imported food, implicated foods imported from areas which previously had not been associated with outbreaks. Projecting supply chains into new geographical regions raises serious questions about the capacity of the new supply chain partners to provide the requisite regulatory framework and sufficiently robust public health measures for ensuring the safety of the foods and foodstuffs offered for international trade. The laws, regulation and legislation among the many nations participating in the global food trade are, at best, inconsistent. These inconsistencies frequently give rise to trade disputes and cause large quantities of food to be at risk of destruction on the often dubious pretext that they are not safe. Food safety is often viewed through a political or normative lens. Often as not, this lens has been wrought absent scientific precision. Harmonization of food safety legislation around sound scientific principles, as advocated by the US Food Safety Modernization Act (FSMA), would ultimately promote trade and likely provide for incremental improvement in public health. Among the priority roles of most national governments are the advancement of commerce and trade, preservation of public health and ensuring domestic tranquility. Achieving these priorities is fundamental to creating and preserving the wealth of nations. Countries such as the Netherlands, Canada, Germany, Japan and the USA

75 FR 36288 - Amended Safety Zone and Regulated Navigation Area, Chicago Sanitary and Ship Canal, Romeoville, IL

Science.gov (United States)

2010-06-25

...The Coast Guard is revising its safety zone and Regulated Navigation Area (RNA) on the Chicago Sanitary and Ship Canal (CSSC) near Romeoville, IL. This revised temporary interim rule reduces the areas covered by the safety zone and RNA, and places additional restrictions on vessels that may transit the RNA.

What is new in the Act on Nuclear Safety

International Nuclear Information System (INIS)

Novosel, N.

2005-01-01

The Act on Nuclear Safety was passed by the Croatian Parliament on 15 October 2003, and published in Narodne novine (official journal) No. 173/03. This Act regulates safety measures for using nuclear materials and equipment, regulates nuclear activities, and establishes the National Office for Nuclear Safety. The new act supersedes the Act on Protective Measures Against Ionising Radiation and Safety in the Use of Nuclear Facilities and Installations (Narodne novine No. 18/81) and the Act on Protection against Ionising Radiation and Special Safety Measures in Using Nuclear Energy (Narodne novine No. 53/91). Regulations based on the latter Act shall apply until they are replaced by new regulations based on the Act on Nuclear Safety. Provisions of this Act apply for nuclear activities, nuclear materials and specified equipment. Croatia does not have nuclear facilities on its territory, but a Croatian power utility company owns 50% of the Nuclear Power Plant Krsko on the territory of Slovenia. In that respect, Croatia has assumed responsibilities defined by the Agreement between the Government of the Republic of Slovenia and the Government of the Republic of Croatia on the Regulation of the Status and Other Legal Relationships, Connected with Investments in the Krsko Nuclear Power Plant, its Exploitation and Decommissioning (Narodne novine No. 9/02, International Agreements). Having accessioned international conventions and agreements, Croatia has also assumed the responsibility to implement their provisions. In the process of European and international integrations, Croatia has to harmonize with the European and international standards in nuclear safety.(author)

Encouraging Maternal Sacrifice: How Regulations Governing the Consumption of Pharmaceuticals During Pregnancy Prioritize Fetal Safety over Maternal Health and Autonomy.

Science.gov (United States)

Donley, Greer

Pregnant women are routinely faced with the stressful decision of whether to consume needed medications during their pregnancies. Because the risks associated with pharmaceutical drug consumption during pregnancy are largely unknown, pregnant women both inadvertently consume dangerous medications and avoid needed drugs. Both outcomes are harmful to pregnant women and their fetuses. This unparalleled lack of drug safety information is a result of ill-conceived, paternalistic regulations in two areas of the law: regulations governing ethical research in human subjects and regulations that dictate the required labels on drugs. The former categorizes pregnant women as "vulnerable" and thus precludes them from most medical research. The result is that ninety-one percent of drugs lack any reliable safety information for pregnant consumers. The latter currently requires all drug labels to encourage drug avoidance during pregnancy, despite ample evidence that avoiding needed medications can harm pregnant women. On June 30, 2015, new pregnancy labeling regulations took effect. Though these regulations make important improvements, they continue to treat pregnant women unlike any population, including other unique subpopulations, such as children. As a result, the new regulations do not fix the problem of over-warning pregnant women about the risks of drug consumption. This article questions the legitimacy of both regulations and suggests three reforms for how to improve access to vital safety information: (1) amend the regulations governing ethical research in human subjects to reclassify pregnant women as non-vulnerable adults; (2) create incentives to generate safety data in pregnant women by granting a period of market exclusivity for drug companies that invest in this research; and (3) make the FDA pregnancy labeling regulations consistent with the routine FDA practice of requiring the display of balanced, human data on risk.

Revised technical regulations on radiation protection and safety of 30 September 1975

International Nuclear Information System (INIS)

1975-01-01

These revised technical regulations were made in implementation of Section 4 of Decree No 7/9038 of 30 November 1974 on radiation health and safety and lay down in detail the requirements to be met in Turkey for the use of all types of radiation sources. They set out protection plans and specify the protective equipment to be used as well as the controlled areas, i.e. areas in which radiation sources are used and which must be subject to special safety measures. Finally to obtain a license, users of radiation sources must fill in forms, the models of which are provided, giving their particulars and the specifications of the intended use and activity of the sources. (NEA) [fr

Safety research activities for Japanese regulations of spent fuel interim storage facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Japan Nuclear Energy Safety Organization (JNES) carries out (a) preparation of technical documents, (b) technical evaluations of standards (prepared by academic societies), etc. and (c) other R and D activities, to support Nuclear Regulation Authority (NRA: which controls the regulations for Spent Fuel Interim Storage Facilities). In 2012 fiscal year, JNES carried out dynamic test of spent fuel to examine the integrity of spent fuel under cask drop accidents, and preparation for PWR spent fuel storage test to prove long term integrity of spent fuel and cask itself. Some of these tests will be also carried out in 2013 fiscal year and after. (author)

Leadership and Safety Culture: Leadership for Safety

International Nuclear Information System (INIS)

Fischer, E.

2016-01-01

Following the challenge to operate Nuclear Power Plants towards operational excellence, a highly skilled and motivated organization is needed. Therefore, leadership is a valuable success factor. On the other hand a well-engineered safety orientated design of NPP’s is necessary. Once built, an NPP constantly requires maintenance, ageing management and lifetime modifications. E.ON tries to keep the nuclear units as close as possible to the state of the art of science and technology. Not at least a requirement followed by our German regulation. As a consequence of this we are continuously challenged to improve our units and the working processes using national and international operational experiences too. A lot of modifications are driven by our self and by regulators. That why these institutions — authorities and independent examiners—contribute significantly to the safety success. Not that it is easy all the day. The relationship between the regulatory body, examiners and the utilities should be challenging but also cooperative and trustful within a permanent dialog. To reach the common goal of highest standards regarding nuclear safety all parties have to secure a living safety culture. Without this attitude there is a higher risk that safety relevant aspects may stay undetected and room for improvement is not used. Nuclear operators should always be sensitized and follow each single deviation. Leaders in an NPP-organization are challenged to create a safety-, working-, and performance culture based on clear common values and behaviours, repeated and lived along all of our days to create a least a strong identity in the staffs mind to the value of safety, common culture and overall performance. (author)

White paper on nuclear safety in 2009

International Nuclear Information System (INIS)

2009-06-01

It deals with a general introduction of nuclear safety like general safety, safety regulation and system law and standard. It indicates of nuclear energy facility safety about general safety, safety regulation of operating nuclear power plant safety regulation under constructing nuclear power plant. It deals with radiation facility safety, monitoring of environmental radiation, radiation protection, radiation control, international cooperating on nuclear energy safety and establishment of safety regulation.

Safety evaluation for the prototype Fast Breeder Reactor MONJU as a Japanese TSO

International Nuclear Information System (INIS)

Endo, Hiroshi

2010-01-01

In the safety field of fast breeder reactors (FBRs), JNES is conducting an evaluation work of the safety regulation by Nuclear and Industry Safety Agency (NISA) for the re-start of a prototype FBR MONJU. MONJU has been stopped over 14 years since 1995 due to a sodium leakage accident at a secondary heat transport system, and is now reached to the criticality on 8th of May, 2010. JNES is supporting the safety regulation work conducted by NISA based on the following activities: i) Support of the technical evaluation of the application for the establishment license prepared by Japan Atomic Energy Agency (JAEA), ii) Support of the description of the safety review report by NISA based on independent safety analyses for the major accident events such as unprotected loss-of-flow (ULOF) by employing the latest findings on the study of core disruptive accidents (CDAs) independently conducted by JNES, iii) Support of the risk-informed-regulation (RIR) such as an accident management (AM) review, iv), and Consideration on the safety regulation policy from the points of severe accidents and source-term behaviors including the cesium (Cs). The objective of this paper is to introduce the major activities of JNES in the safety domain of MONJU regulations. (author)

A fresh start of nuclear safety regulation and international perspective

International Nuclear Information System (INIS)

Oshima, Kenzo

2013-01-01

It should be explained more to the outside modestly the Fukushima nuclear accident would be a man-made complex disaster, which might be reluctant to do but not be neglected. Utmost efforts to change inward-looking attitude and reform safety culture should be done so as to prevent superficial reflection of the Fukushima nuclear accident. Since all nuclear regulatory functions ('3S': safety, security, safeguards) were integrated in Nuclear Regulation Authority (NRA), NRA and secretariat of NRA became more responsible for international response, and strengthening of organization system and human resources development would be an urgent necessity. This article described present stage of NRA focusing on international dimension including personal views. Overseas strong concern over the Fukushima nuclear accident and international communications were reviewed. The Fukushima nuclear accident started from natural disaster and enlarged as a man-made complex disaster with many human factors (mainly inaction, wilful negligence) overlapping and safety culture flawed. Examples of overseas and Japanese action plan to learn and absorb lessons from the Fukushima accident were introduced. NRA's started activities on inviting IAEA's IRRS and OPPAS as soon as ready, strengthening nuclear security measures, safeguards to prevent nuclear proliferation, bilateral cooperation and international advisors were also presented. (T. Tanaka)

Use of risk information to safety regulation. Reprocessing facilities

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

A procedure of probabilistic risk assessment (PRA) for a reprocessing facility has been under the development aiming to utilize risk information for safety regulations in this project. Activities in the fiscal year 2012 are summarized in the paper. A major activity is a fundamental study on a concept of serious accidents, requirements of serious accident management, and a policy of utilizing risk information for fabrication and reprocessing facilities. Other than the activity a study on release and transport of aerial radioactive materials at a serious accident in a reprocessing facility has been conducted. The outline and results are provided in the chapter 1 and 2 respectively. (author)

Facilities management and industrial safety

International Nuclear Information System (INIS)

2003-06-01

This book lists occupation safety and health acts with purpose, definition and management system of safety and health, enforcement ordinance of occupation safety and health acts and enforcement regulations such as general rules, safety and health cover, system of management on safety and health, regulation of management on safety and health, regulations of harmfulness and protection of danger, heath management for workers, supervisor and command and inspection of machine and equipment.

CANDU reactors, their regulation in Canada, and the identification of relevant NRC safety issues

International Nuclear Information System (INIS)

Charak, I.; Kier, P.H.

1995-04-01

Atomic Energy of Canada, Limited (AECL) and its subsidiary in the US, are considering submitting the CANDU 3 design for standard design certification under 10 CFR Part 52. CANDU reactors are pressurized heavy water power reactors. They have some substantially different safety responses and safety systems than the LWRs that the commercial power reactor licensing regulations of the US Nuclear Regulatory Commission (NRC) have been developed to deal with. In this report, the authors discuss the basic design characteristics of CANDU reactors, specifically of the CANDU 3 where possible, and some safety-related consequences of these characteristics. The authors also discuss the Canadian regulatory provisions, and the CANDU safety systems that have evolved to satisfy the Canadian regulatory requirements as of December 1992. Finally, the authors identify NRC regulations, mainly in 10 CFR Parts 50 and 100, with issues for CANDU 3 reactor designs. In all, eleven such regulatory issues are identified. They are: (1) the ATWS rule (section 50.62); (2) station blackout (section 50.63); (3) conformance with Standard Review Plan (SRP); (4) appropriateness of the source term (section 50.34(f) and section 100.11); (5) applicability of reactor coolant pressure boundary (RCPB) requirements (section 50.55a, etc); (6) ECCS acceptance criteria (section 50.46)(b); (7) combustible gas control (section 50.44, etc); (8) power coefficient of reactivity (GDC 11); (9) seismic design (Part 100); (10) environmental impacts of the fuel cycle (section 51.51); and (11) (standards section 50.55a)

Influence of safety vlave pressure on gelled electrolyte valve-regulated lead/acid batteries under deep cycling applications

International Nuclear Information System (INIS)

Oh, Sang Hyub; Kim, Myung Soo; Lee, Jin Bok; Lee, Heung Lark

2002-01-01

Cycle life tests have been carried out to evaluate the influence of safety valve pressure on vlave regulated lead/acid batteries under deep cycling applications. Batteries were cycled at 5 hour rates at 100 % DOD, and safety valve pressure was set to 1.08 and 2.00 bar, respectively. The batteries lost 248.3 g of water for each case after about 1,200 cycles, but the cyclic performances of the batteries were comparable. Most of the gas of the battery during discharging was hydrogen, and the oxygen concentration increased to 18 % after 3 hours of charging. The micro structure of the positive active materials was completely changed and the corrosion layer of the positive grid was less than 50 μm, regardless of the pressure of the safety valve after cycle life tests. The cause of discharge capacity decrease was found to water loss and the shedding of the positive active materials. The pressure of safety valve does not give little effect to the cyclic performance and the failure modes of the gelled electrolyte valve-regulated lead acid batteries

Compliance strategy for statistically based neutron overpower protection safety analysis methodology

International Nuclear Information System (INIS)

Holliday, E.; Phan, B.; Nainer, O.

2009-01-01

The methodology employed in the safety analysis of the slow Loss of Regulation (LOR) event in the OPG and Bruce Power CANDU reactors, referred to as Neutron Overpower Protection (NOP) analysis, is a statistically based methodology. Further enhancement to this methodology includes the use of Extreme Value Statistics (EVS) for the explicit treatment of aleatory and epistemic uncertainties, and probabilistic weighting of the initial core states. A key aspect of this enhanced NOP methodology is to demonstrate adherence, or compliance, with the analysis basis. This paper outlines a compliance strategy capable of accounting for the statistical nature of the enhanced NOP methodology. (author)

Performance-based regulation. Panel Discussion

International Nuclear Information System (INIS)

Youngblood, Robert; Bier, Vicki M.; Bukowski, Richard W.; Prasad Kadambi, N.; Koonce, James F.

2001-01-01

Full text of publication follows: Performance-based regulation is a part of the NRC's Strategic Plan and is realizing steady progress in conceptual development for actual applications. For example, high-level, conceptual guidelines have been proposed that would apply to reactors, materials, and waste areas. Performance-based approaches are also being applied in other regulated industries such as FAA and OSHA. The discussion will include comments from speakers from different parts of the nuclear industry and other industries regarding benefits and weaknesses of performance-based regulation. (authors)

International laser-safety regulations: a status update

Science.gov (United States)

Weiner, Robert M.

1990-07-01

There is an increase in international laser safety requirements as part of the emphasis on world-wide standardization of products and regulations. In particular the documents which will evolve from the 1992 consolidation efforts of the European Community (EC) will impact both laser manufacturers and users. This paper provides a discussion of the current status of the various laser radiation standards. NORTH AMERICAN REQUIREMENTS United States Requirements on manufacturers from the Food and Drug Administration (FDA) have been in effect since 1975. The Center for Devices and Radiological Health (CDRH) within that agency ensures that these mandatory requirements [1] are satisfied. The CDRH regulations include the division of products into classes depending on their potential for hazard criteria for power measurement and requirements for product features labels and manuals and records and reports. Manufacturers must test products and certify that they comply with the CDRH requirements. User requirements are found in a standard published by the American National Standards Institute (ANSI) and in requirements from several individual states. Specific ANSI standards have also been published for fiber communications systems [34] and for lasers in medical applications [35]. Please note that the Appendix includes additional information on the standards discussed in this paper including sources for obtaining the documents. Canada In the past Canada has had requirements for two specified product categories (bar code scanners and educational lasers) [26 These will be replaced

Resolution No. 6/04 Regulations for the recognition of the competence of services for radiation safety

International Nuclear Information System (INIS)

2004-01-01

This Regulation aims to establish the rules that govern the process to recognize the competence of services for radiation safety, they are no authorized under Resolution No. 25, dated May 29, 1998, the Ministry of Science, Technology and Environment, A uthorization Regulation Practices Associated with Use of Ionizing Radiation , in order to ensure that services that are related to the practices associated with the use of nuclear energy, with the requisite expertise. This Regulation applies to all natural or legal persons performing or purporting to perform service activities for radiation safety in the country. These services are: 2.1. Individual Radiation Monitoring Services, in one or more of the following areas: 2.1.1. Control of external exposure a) Electromagnetic Radiation. b) beta radiation. c) neutron radiation. 2.1.2. Control of internal contamination a) Determination of internal contamination by direct measurements. b) Determination of internal contamination by analysis of biological samples. c) Monitoring of air, personal and total. 2.2. Service environmental measurements and samples. 2.3. Service control radioactive contamination in foods. 2.4. Service measuring dose rate, surface contamination and air pollution. 2.5. Calibration and verification of equipment. 2.6. Service courses in radio-logical protection. 2.7. Consultancy services in radiation protection. 2.8. Service control radioactive contamination in scrap. 2.9. Service quality control equipment that is used in the practices associated with the use of ionizing radiation. 2.10. Any other service in the field of radiation safety in scope and interest of end-National Center for Nuclear Safety.

Studying the Safety Impact of Autonomous Vehicles Using Simulation-Based Surrogate Safety Measures

OpenAIRE

Morando, Mark Mario; Tian, Qingyun; Truong, Long T.; Vu, Hai L.

2018-01-01

Autonomous vehicle (AV) technology has advanced rapidly in recent years with some automated features already available in vehicles on the market. AVs are expected to reduce traffic crashes as the majority of crashes are related to driver errors, fatigue, alcohol, or drugs. However, very little research has been conducted to estimate the safety impact of AVs. This paper aims to investigate the safety impacts of AVs using a simulation-based surrogate safety measure approach. To this end, safety...

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material. Safety Guide (Spanish Edition)

International Nuclear Information System (INIS)

2010-01-01

This Safety Guide provides recommendations on achieving and demonstrating compliance with IAEA Safety Standards Series No. TS-R-1, Regulations for the Safe Transport of Radioactive Material, 2005 Edition, establishing safety requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material; these include the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit and receipt at the final destination of packages. This publication supersedes IAEA Safety Series No. TS-G-1.1, 2002 Edition

Analysis co-regulation model of safety of fishery products in Morocco through the example of “histamine”, “parasites” and “sulphites” dangers

Directory of Open Access Journals (Sweden)

S. Dahani

2018-01-01

Full Text Available Co-regulation in food safety represents the shared responsibility between food business operators and the competent authority (CA to ensure food safety and to comply with the health requirements of importing countries. The evolution of food regulation on one hand and the quality assurance of the veterinary services of the ONSSA according to the ISO 17020 standard on the other hand, need studying the regulation model adopted at national level. The objective of this work is to analyze the main health risks associated with fishery products from a co-regulatory perspective. The hazards targeted by this study are histamine, parasites and sulfites. The approach is based on structured interviews with fishery products professionals and veterinary inspectors responsible for control and certification. The main hazards are controlled by adopting health control plans (PMS by the professionals within the establishments as well as the official control carried out by the inspecting veterinarians. The PMS implementation can produce conflicting injunctions for the veterinary inspectors of the competent authority.

Accidents and Apathy: The Construction of the 'Robens Philosophy' of Occupational Safety and Health Regulation in Britain, 1961-1974.

Science.gov (United States)

Sirrs, Christopher

2016-02-01

The 1972 Robens Report is widely regarded to have provided the underlying rationale for the 'modern' system of occupational health and safety regulation in Britain, embodied in the Health and Safety at Work Act (HSW Act) 1974. The HSW Act advanced a new, more flexible system of regulation, premised on the ideal of self-regulation by industry. This article advances a more nuanced historical understanding of the Report and its ethos-the 'Robens philosophy'-than hitherto developed, situating its assumptions about accidents, regulation and the role of the state in the social, economic and political context of Britain in the 1960s and early 1970s. Highlighting the interaction between these trends and long-established regulatory practices, the article argues that the turn to 'self-regulation' heralded by the Robens Report was highly convincing from a political and regulatory perspective at the time it was promulgated.

Methods for formulation of design basis accidents within a risk-informed approach to safety regulation of new nuclear power plants

International Nuclear Information System (INIS)

Beer, B.C.; Apostolakis, G.E.; Golay, M.W.

2000-01-01

Within a project sponsored by the U.S. Department of Energy (DOE) an investigation is being conducted into creating a risk-informed safety regulatory framework and design process based upon the use of probabilistic risk assessment (PRA). In conjunction with efforts to formulate an overall regulatory framework (i.e., reported in PSAM 5 by F. Duran, A. Camp, G. Apostolakis and M. Golay, 'A Framework for Regulatory Requirements and Industry Standards for New Nuclear Power Plants'), this paper addresses the potential role(s) of Design Basis Accidents (DBAs) within this new framework. Currently that role, if any, is unclear. In previous nuclear safety regulatory treatments, DBAs have been of great practical value for both designers and regulators. However, they have suffered from being inconsistently formulated, and lacking fundamental justification. Any DBA set is likely to be formulated uniquely for a specific reactor concept. The staff of any nuclear power plant (NPP) in the U.S. routinely calculates the likelihood of core damage, the likelihood of radioactive release and the likelihood of adverse health effects due to radioactive release. As the accuracy of such estimates improves industry-wide, safety regulators consider weighing these calculated risks more heavily than strict adherence to the prescriptive conservatisms of existing regulations, hence risk-informed regulation. DBAs, despite their prescriptive nature, can remain useful tools for regulators and designers in a risk-informed regulatory framework, providing that they can be formulated in a fashion consistent with the risk profiles of a plant. DBAs also offer the opportunity to take into account factors of uncertainty not captured in a PRA, which are typically addressed via defense-in-depth features and subjective judgements. Designers seeking only to create a plant having a calculated risk below a certain value, while minimizing cost, may find themselves in an inefficient trial-and-error process as they

Composition, labelling, and safety of food supplements based on bee products in the legislative framework of the European Union - Croatian experiences.

Science.gov (United States)

Vujić, Mario; Pollak, Lea

2015-12-01

The European Union market is overflown by food supplements and an increasing number of consumers prefer those where bee products play an important part in their composition. This paper deals with complex European Union legislation concerning food supplements based on bee products, placing a special emphasis on their composition, labelling, and safety. Correct labelling of food supplements also represents a great challenge since, in spite of legal regulations in force, there are still open issues regarding the statements on the amount of propolis, which is not clearly defined by the legal framework. One of the key issues are the labels containing health claims from the EU positive list approved by the European Food Safety Authority. Emphasis will also be placed on informing consumers about food, as statements which imply the healing properties of food supplements and their capacity to cure diseases are forbidden. One of the key elements of product safety is HACCP based on the EU Regulations EC 178/02 and 852/2004. Health safety analyses of food supplements with bee products used as raw materials, which are standardised by legal regulations will also be discussed. In the future, attention should also be paid to establishing the European Union "nutrivigilance" system. Croatian experiences in addressing challenges faced by producers, supervisory entities, and regulatory and inspection bodies may serve as an example to countries aspiring to become part of the large European family.

The impact of regulations, safety considerations and physical limitations on research progress at maximum biocontainment.

Science.gov (United States)

Shurtleff, Amy C; Garza, Nicole; Lackemeyer, Matthew; Carrion, Ricardo; Griffiths, Anthony; Patterson, Jean; Edwin, Samuel S; Bavari, Sina

2012-12-01

We describe herein, limitations on research at biosafety level 4 (BSL-4) containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT) are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP) conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review.

The Impact of Regulations, Safety Considerations and Physical Limitations on Research Progress at Maximum Biocontainment

Directory of Open Access Journals (Sweden)

Jean Patterson

2012-12-01

Full Text Available We describe herein, limitations on research at biosafety level 4 (BSL-4 containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review.

The Impact of Regulations, Safety Considerations and Physical Limitations on Research Progress at Maximum Biocontainment

Science.gov (United States)

Shurtleff, Amy C.; Garza, Nicole; Lackemeyer, Matthew; Carrion, Ricardo; Griffiths, Anthony; Patterson, Jean; Edwin, Samuel S.; Bavari, Sina

2012-01-01

We describe herein, limitations on research at biosafety level 4 (BSL-4) containment laboratories, with regard to biosecurity regulations, safety considerations, research space limitations, and physical constraints in executing experimental procedures. These limitations can severely impact the number of collaborations and size of research projects investigating microbial pathogens of biodefense concern. Acquisition, use, storage, and transfer of biological select agents and toxins (BSAT) are highly regulated due to their potential to pose a severe threat to public health and safety. All federal, state, city, and local regulations must be followed to obtain and maintain registration for the institution to conduct research involving BSAT. These include initial screening and continuous monitoring of personnel, controlled access to containment laboratories, accurate and current BSAT inventory records. Safety considerations are paramount in BSL-4 containment laboratories while considering the types of research tools, workflow and time required for conducting both in vivo and in vitro experiments in limited space. Required use of a positive-pressure encapsulating suit imposes tremendous physical limitations on the researcher. Successful mitigation of these constraints requires additional time, effort, good communication, and creative solutions. Test and evaluation of novel vaccines and therapeutics conducted under good laboratory practice (GLP) conditions for FDA approval are prioritized and frequently share the same physical space with important ongoing basic research studies. The possibilities and limitations of biomedical research involving microbial pathogens of biodefense concern in BSL-4 containment laboratories are explored in this review. PMID:23342380

NRC safety research in support of regulation

International Nuclear Information System (INIS)

1994-06-01

This report, the ninth in a series of annual reports, was prepared in response to congressional inquiries concerning how nuclear regulatory research is used. It summarizes the accomplishments of the Office of Nuclear Regulatory Research during FY 1993. A special emphasis on accomplishments in nuclear power plant aging research reflects recognition that number of plants are entering the final portion of their original 40-year operating licenses and that, in addition to current aging effects, a focus on safety considerations for license renewal becomes timely. The primary purpose of performing regulatory research is to develop and provide the Commission and its staff with sound technical bases for regulatory decisions on the safe operation of licensed nuclear reactors and facilities, to find unknown or unexpected safety problems, and to develop data and related information for the purpose of revising the Commission's rules, regulatory guides, or other guidance

A web-based tool for the Comprehensive Unit-based Safety Program (CUSP).

Science.gov (United States)

Pronovost, Peter J; King, Jay; Holzmueller, Christine G; Sawyer, Melinda; Bivens, Shauna; Michael, Michelle; Haig, Kathy; Paine, Lori; Moore, Dana; Miller, Marlene

2006-03-01

An organization's ability to change is driven by its culture, which in turn has a significant impact on safety. The six-step Comprehensive Unit-Based Safety Program (CUSP) is intended to improve local culture and safety. A Web-based project management tool for CUSP was developed and then pilot tested at two hospitals. HOW ECUSP WORKS: Once a patient safety concern is identified (step 3), a unit-level interdisciplinary safety committee determines issue criticality and starts up the projects (step 4), which are managed using project management tools within eCUSP (step 5). On a project's completion, the results are disseminated through a shared story (step 6). OSF St. Joseph's Medical Center-The Medical Birthing Center (Bloomington, Illinois), identified 11 safety issues, implemented 11 projects, and created 9 shared stories--including one for its Armband Project. The Johns Hopkins Hospital (Baltimore) Medical Progressive Care (MPC4) Unit identified 5 safety issues and implemented 4 ongoing projects, including the intravenous (IV) Tubing Compliance Project. The eCUSP tool's success depends on an organizational commitment to creating a culture of safety.

Regulating nuclear and radiation safety in the frame of the Chernobyl shelter Implementation Plan

Energy Technology Data Exchange (ETDEWEB)

Bykov, V.; Demchyuk, A.; Kilochitska, T.; Redko, V. [State Nuclear Regulatory Committee of Ukraine, SNRCU, Arsenalna St. 9/11, Kyiv (Ukraine); Bogorinski, P. [GRS/IPSN-RISKAUDIT, Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH, Koeln (Germany); Vasilchenko, V.; Erickson, L.; Kadkin, E.; Kondratyev, S.; Kutina, L.; Smyshliaeva, S. [SSTC NRS, Stusa St. 35-37, 03142, Kyiv (Ukraine)

2003-07-01

Since 1998 the Shelter Implementation Plan (SIP) has been carried out on the Chernobyl NPP Unit 4 (the object Shelter - OS). The State Nuclear Regulatory Committee of Ukraine (SNRCU) recognizes the exceptional importance of successful and efficient SIP implementation and acts accordingly in regulation, licensing, and inspection. Technical support of the SNRCU in SIP licensing are provided by the State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC) and the SIP Licensing Consultant (LC) representing RISKAUDIT IPSN/GRS International and SCIENTECH, Inc. Support of the SNRCU is also provided by the International Consultative Committee of Regulatory Bodies (ICCRB). ICCRB members represent regulatory authorities from nine European countries, Canada and the U.S. Summarizing the information above, it can be stated that a sound basis has been created for the licensing process for SIP. The approach for using the regulatory base has been determined. It ensures the establishment of safety objectives and gives ChNPP the freedom of optimal choice of specific technical decisions. The License has been issued for OS-related activities and a number of documents have been developed to conduct an effective and high quality authorization process: the Licensing Process; Recommendations on single SSR, Licensing Plan for SIP. The Order of State Safety Supervision for SIP has been approved. Working groups are functioning, whose purposes are to coordinate actions of participants in authorization activities, including ChNPP, SNRCU, and other RA.

Regulating nuclear and radiation safety in the frame of the Chernobyl shelter Implementation Plan

International Nuclear Information System (INIS)

Bykov, V.; Demchyuk, A.; Kilochitska, T.; Redko, V.; Bogorinski, P.; Vasilchenko, V.; Erickson, L.; Kadkin, E.; Kondratyev, S.; Kutina, L.; Smyshliaeva, S.

2003-01-01

Since 1998 the Shelter Implementation Plan (SIP) has been carried out on the Chernobyl NPP Unit 4 (the object Shelter - OS). The State Nuclear Regulatory Committee of Ukraine (SNRCU) recognizes the exceptional importance of successful and efficient SIP implementation and acts accordingly in regulation, licensing, and inspection. Technical support of the SNRCU in SIP licensing are provided by the State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC) and the SIP Licensing Consultant (LC) representing RISKAUDIT IPSN/GRS International and SCIENTECH, Inc. Support of the SNRCU is also provided by the International Consultative Committee of Regulatory Bodies (ICCRB). ICCRB members represent regulatory authorities from nine European countries, Canada and the U.S. Summarizing the information above, it can be stated that a sound basis has been created for the licensing process for SIP. The approach for using the regulatory base has been determined. It ensures the establishment of safety objectives and gives ChNPP the freedom of optimal choice of specific technical decisions. The License has been issued for OS-related activities and a number of documents have been developed to conduct an effective and high quality authorization process: the Licensing Process; Recommendations on single SSR, Licensing Plan for SIP. The Order of State Safety Supervision for SIP has been approved. Working groups are functioning, whose purposes are to coordinate actions of participants in authorization activities, including ChNPP, SNRCU, and other RA

Applying Sensor-Based Technology to Improve Construction Safety Management.

Science.gov (United States)

Zhang, Mingyuan; Cao, Tianzhuo; Zhao, Xuefeng

2017-08-11

Construction sites are dynamic and complicated systems. The movement and interaction of people, goods and energy make construction safety management extremely difficult. Due to the ever-increasing amount of information, traditional construction safety management has operated under difficult circumstances. As an effective way to collect, identify and process information, sensor-based technology is deemed to provide new generation of methods for advancing construction safety management. It makes the real-time construction safety management with high efficiency and accuracy a reality and provides a solid foundation for facilitating its modernization, and informatization. Nowadays, various sensor-based technologies have been adopted for construction safety management, including locating sensor-based technology, vision-based sensing and wireless sensor networks. This paper provides a systematic and comprehensive review of previous studies in this field to acknowledge useful findings, identify the research gaps and point out future research directions.

For improvements of issues behind food safety regulations implemented following the Fukushima nuclear accident

International Nuclear Information System (INIS)

Hamada, Nobuyuki; Ogino, Haruyuki

2011-01-01

The great quake and a subsequent tsunami seriously damaged the Fukushima nuclear power plants on 11 March 2011, followed by radionuclide releases outside the crippled reactors. Regulatory limits stipulated as 'provisional regulation values' were set to minimize internal exposure via ingestion of contaminated food and drink. Tap water, raw milk, vegetables, seafood and tea exceeded the limit, and distribution and/or consumption of these stuffs were temporality restricted. It took 7 and 11 days to set the provisional regulation values and to order the first restriction after the declaration of nuclear emergency situations, respectively. All restrictions began within 25 days after the first excess in each item, but the commencement of restrictions was concomitant with the social dislocations. All restrictions for tap water were withdrawn within 51 days, but restrictions for food have yet to be lifted. Among all items, maximum levels were detected in leafy vegetables (54,100 Bq/kg of 131 I, 82,000 Bq/kg of 134 Cs and 137 Cs). Most provisional regulation values were adopted from the preexisting 'index values'. Index values were logically designed and practically convenient. However, food and radionuclides were not comprehensively covered, and the same value was given to emergency and existing exposure situations. Also, different provisional regulation values were set for infants and others. In this respect, we here propose the concept of the 'graded triphasic reference level system' to optimize food safety regulations in early, intermediate and late phases following the accident, where each example phase-specific reference level value is provided. This paper focuses on the logic and issues behind such food safety regulations. The food monitoring data of 24,685 samples and the enforced restrictions shall also be outlined predicated on the information available as of 12 June 2011. (author)

Operating experience: safety perspective

International Nuclear Information System (INIS)

Piplani, Vivek; Krishnamurthy, P.R.; Kumar, Neeraj; Upadhyay, Devendra

2015-01-01

Operating Experience (OE) provides valuable information for improving NPP safety. This may include events, precursors, deviations, deficiencies, problems, new insights to safety, good practices, lessons and corrective actions. As per INSAG-10, an OE program caters as a fundamental means for enhancing the defence-in-depth at NPPs and hence should be viewed as ‘Continuous Safety Performance Improvement Tool’. The ‘Convention on Nuclear Safety’ also recognizes the OE as a tool of high importance for enhancing the NPP safety and its Article 19 mandates each contracting party to establish an effective OE program at operating NPPs. The lessons drawn from major accidents at Three Mile Island, Chernobyl and Fukushima Daiichi NPPs had prompted nuclear stalwarts to change their safety perspective towards NPPs and to frame sound policies on issues like safety culture, severe accident prevention and mitigation. An effective OE program, besides correcting current/potential problems, help in proactively improving the NPP design, operating and maintenance procedures, practices, training, etc., and thus plays vital role in ensuring safe and efficient operation of NPPs. Further it enhances knowledge with regard to equipment operating characteristics, system performance trends and provides data for quantitative and qualitative safety analysis. Besides all above, an OE program inculcates a learning culture in the organisation and thus helps in continuously enhancing the expertise, technical competency and knowledge base of its staff. Nuclear and Radiation Facilities in India are regulated by Atomic Energy Regulatory Board (AERB). Operating Plants Safety Division (OPSD) of AERB is involved in managing operating experience activities. This paper provides insights about the operating experience program of OPSD, AERB (including its on-line data base namely OPSD STAR) and its utilisation in improving the regulations and safety at Indian NPPs/projects. (author)

Science and regulation 50 years hand in hand in radiation safety work in Finland

International Nuclear Information System (INIS)

Laaksonen, Jukka; Mustonen, Raimo; Ikaheimonen, Tarja

2008-01-01

The first predecessor of the present Nuclear and Radiation Safety Authority of Finland (STUK) was founded in 1958 to regulate the use of radiation and to study artificial radiation in the environment. In those days radiation was used only in medical and industrial applications and there were also first indications that atmospheric nuclear tests might cause significant exposure to radiation, especially in the Northern Finland. Focusing activities of the new Institute of Radiation Physics, as STUK was called in those days, to these two activities laid foundation for the operations culture where regulators and scientists work together to achieve the optimum level of safety. Since those early days STUK has continued this operations model and developed it to include also other activities. Today STUK is the national regulatory body for both radiation protection and nuclear safety, but at the same time it is a research organisation and an expert body, supporting for instance the national emergency preparedness for nuclear and radiation accidents. This has brought great synergy benefits and given STUK an opportunity to use the limited national resources in the most effective way. This paper describes the main functions of STUK in its fifty years' operation and highlights the arguments favouring to keep regulatory and research activities as close to each other as possible. In today's world nuclear safety, radiation protection, and radiological preparedness and security issues are so closely connected with each other that organisations dealing with them should have comprehensive knowledge about all of them. (author)

Nuclear safety policy statement in korea

International Nuclear Information System (INIS)

Kim, W.S.; Kim, H.J.; Choi, K.S.; Choi, Y.S.; Park, D.K.

2006-01-01

Full text: Wide varieties of programs to enhance nuclear safety have been established and implemented by the Korean government in accordance with the Nuclear Safety Policy Statement announced in September 1994. The policy statement was intended to set the long-term policy goals for maintaining and achieving high-level of nuclear safety and also help the public understand the national policy and a strong will of the government toward nuclear safety. It has been recognized as very effective in developing safety culture in nuclear-related organizations and also enhancing nuclear safety in Korea. However, ageing of operating nuclear power plants and increasing of new nuclear facilities have demanded a new comprehensive national safety policy to cover the coming decade, taking the implementation results of the policy statement of 1994 and the changing environment of nuclear industries into consideration. Therefore, the results of safety policy implementation have been reviewed and, considering changing environment and future prospects, a new nuclear safety policy statement as a highest level national policy has been developed. The implementation results of 11 regulatory policy directions such as the use of Probabilistic Safety Assessment, introduction of Periodic Safety Review, strengthening of safety research, introduction of Risk Based Regulation stipulated in the safety policy statement of 1994 were reviewed and measures taken after various symposia on nuclear safety held in Nuclear Safety Days since 1995 were evaluated. The changing international and domestic environment of nuclear industry were analysed and future prospects were explored. Based on the analysis and review results, a draft of new nuclear safety policy statement was developed. The draft was finalized after the review of many prominent experts in Korea. Considering changing environment and future prospects, new policy statement that will show government's persistent will for nuclear safety has been

Nuclear safety in Slovak Republic. Safety analysis reports for WWER 440 reactors

International Nuclear Information System (INIS)

Rohar, S.

1999-01-01

Implementation of nuclear power program is connected to establishment of regulatory body for safe regulation of siting, construction, operation and decommissioning of nuclear installations. Licensing being one of the most important regulatory surveillance activity is based on independent regulatory review and assessment of information on nuclear safety for particular nuclear facility. Documents required to be submitted to the regulatory body by the licensee in Slovakia for the review and assessment usually named Safety Analysis Report (SAR) are presented in detail in this paper. Current status of Safety Analysis Reports for Bohunice V-1, Bohunice V-2 and Mochovce NPP is shown

Barriers to Construction Health and Safety Self-regulation: A Scoping Case of Nigeria

Directory of Open Access Journals (Sweden)

Umeokafor Nnedinma

2017-03-01

Full Text Available This scoping study builds on the recent uncovering that in terms of health and safety (H&S, the Nigerian construction industry is self-regulated in various forms, not unregulated and that the size of company can further explain H&S self-regulation. Consequently, the barriers identified through literature review were assessed using questionnaires. Analysis of the data collected from construction practitioners in Nigeria shows that ‘economic factors’ mostly explains the barriers to construction H&S self-regulation. This is followed by the ‘ability to self-regulate’ and ‘lack of awareness’. Furthermore, the results show significant differences among small, medium and large construction contractors on seven factors of which include ‘normative case’ factors, ‘H&S is a duty’, ‘H&S is the right thing’ and ‘unfair H&S standards or legislation’. Although a scoping study, the study draws attention to the barriers to construction H&S self-regulation in Nigeria and demonstrates an alternative to state regulation of H&S.

Model-based safety architecture framework for complex systems

NARCIS (Netherlands)

Schuitemaker, Katja; Rajabali Nejad, Mohammadreza; Braakhuis, J.G.; Podofillini, Luca; Sudret, Bruno; Stojadinovic, Bozidar; Zio, Enrico; Kröger, Wolfgang

2015-01-01

The shift to transparency and rising need of the general public for safety, together with the increasing complexity and interdisciplinarity of modern safety-critical Systems of Systems (SoS) have resulted in a Model-Based Safety Architecture Framework (MBSAF) for capturing and sharing architectural

Mines Safety Control (Radiation Protection) Regulations (Northern Territory) No. 30 of 25 September 1981

International Nuclear Information System (INIS)

1981-01-01

These Regulations, pursuant to the Mines Safety Control Act, are intended to prevent or limit the radiation risk to persons involved in the mining or milling of radioactive ores. The duties and responsibilities imposed by the Regulations on owners, managers and employees of the mines are identical with those set forth in the 1980 Code of Practice on Radiation Protection in the Mining and Milling of Radioactive Ores which establishes radiation standards and exposure limits, requires health surveillance of employees and provides for the management of radioactive wastes. (NEA) [fr

New Approach for Nuclear Safety and Regulation - Application of Complexity Theory and System Dynamics

International Nuclear Information System (INIS)

Choi, Kwang Sik; Choi, Young Sung; Han, Kyu Hyun; Kim, Do Hyoung

2007-01-01

The methodology being used today for assuring nuclear safety is based on analytic approaches. In the 21st century, holistic approaches are increasingly used over traditional analytic method that is based on reductionism. Presently, it leads to interest in complexity theory or system dynamics. In this paper, we review global academic trends, social environments, concept of nuclear safety and regulatory frameworks for nuclear safety. We propose a new safety paradigm and also regulatory approach using holistic approach and system dynamics now in fashion

Regulation and safety implementation of nanotechnology for chemical enterprises in the Central Europe Space

Science.gov (United States)

Falk, A.; Hartl, S.; Sinner, F.

2013-04-01

As result of the gradually increasing nanotechnology sector there is the necessity of a contemporary analysis of the present regulations used for nanomaterials, to outline the current situation of the nanotechnology sector, to promote international cooperation and research's coordination to overcome disciplinary boundaries, to fill the gap between more and less experienced regions and to turn investments in R&D in industrial innovations. The general objective of the Central Europe project NANOFORCE, which is developed by national and regional chemistry associations and R&D Centres of the Central Europe area, is to foster the innovative nanotechnology-sector networks across Central Europe regions by bringing together public and private organizations to carry out collaborative and interdisciplinary researches on nanomaterials (in the frame of REACH Regulation) and to turn the most promising laboratory results into innovative industrial applications. To build up a legal advisory board for chemical enterprises starting in nanotechnology, a state of the art report on existing safety procedures and nanotech related regulations was produced to give an overview on currently available regulations used by chemical industries and manufacturing companies within the European region to secure their products. The main emphasis was placed on REACH regulation to search for relevant sections concentrating on nanomaterials which are applicable for nanotechnology. In addition, all relevant directives and amendments of REACH were screened with regard to identify gaps where action is still needed and give possible recommendations for the European Commission. Beyond literature research a questionnaire for producers, users, researchers and financiers was developed with the goal to collect information about the nanotechnology sector in the CE region concerning development, financial status, and international cooperation within joint ventures, safety and nanotoxicology.

Safety factors for neutron fluences in NPP safety assessment

International Nuclear Information System (INIS)

Demekhin, V.L.; Bukanov, V.N.; Il'kovich, V.V.; Pugach, A.M.

2016-01-01

In accordance with global practice and a number of existing regulations, the use of conservative approach is required for the calculations related to nuclear safety assessment of NPP. It implies the need to consider the determination of neutron fluence errors that is rather complicated. It is proposed to carry out the consideration by the way of multiplying the neutron fluences obtained with transport calculations by safety factors. The safety factor values are calculated by the developed technique based on the theory of errors, features of the neutron transport calculation code and the results obtained with the code. It is shown that the safety factor value is equal 1.18 with the confidence level of not less than 0.95 for the majority of VVER-1000 reactor places where neutron fluences are determined by MCPV code, and its maximum value is 1.25

New Safety rules

CERN Multimedia

Safety Commission

2008-01-01

The revision of CERN Safety rules is in progress and the following new Safety rules have been issued on 15-04-2008: Safety Procedure SP-R1 Establishing, Updating and Publishing CERN Safety rules: http://cern.ch/safety-rules/SP-R1.htm; Safety Regulation SR-S Smoking at CERN: http://cern.ch/safety-rules/SR-S.htm; Safety Regulation SR-M Mechanical Equipment: http://cern.ch/safety-rules/SR-M.htm; General Safety Instruction GSI-M1 Standard Lifting Equipment: http://cern.ch/safety-rules/GSI-M1.htm; General Safety Instruction GSI-M2 Standard Pressure Equipment: http://cern.ch/safety-rules/GSI-M2.htm; General Safety Instruction GSI-M3 Special Mechanical Equipment: http://cern.ch/safety-rules/GSI-M3.htm. These documents apply to all persons under the Director General’s authority. All Safety rules are available at the web page: http://www.cern.ch/safety-rules The Safety Commission

Cerebrospinal fluid protein and glucose examinations and tuberculosis:
Will laboratory safety regulations force a change of practice?

Science.gov (United States)

Tormey, William P; O'Hagan, Christopher

2015-01-01

Cerebrospinal fluid (CSF) protein and glucose examinations are usually performed in chemical pathology departments on autoanalysers. Tuberculosis (TB) is a group 3 biological agent under Directive 2000/54/EC of the European Parliament but in the biochemistry laboratory, no extra precautions are taken in its analysis in possible TB cases. The issue of laboratory practice and safety in the biochemical analyses of CSF specimens, when tuberculosis infection is in question is addressed in the context of ambiguity in the implementation of current national and international health and safety regulations. Additional protective measures for laboratory staff during the analysis of CSF TB samples should force a change in current laboratory practice and become a regulatory issue under ISO 15189. Annual Mantoux skin test or an interferon-γ release assay for TB should be mandatory for relevant staff. This manuscript addresses the issue of biochemistry laboratory practice and safety in the biochemical analyses of CSF specimens when tuberculosis infection is in question in the context of the ambiguity of statutory health and safety regulations.

Improving versus maintaining nuclear safety

International Nuclear Information System (INIS)

2002-01-01

The concept of improving nuclear safety versus maintaining it has been discussed at a number of nuclear regulators meetings in recent years. National reports have indicated that there are philosophical differences between NEA member countries about whether their regulatory approaches require licensees to continuously improve nuclear safety or to continuously maintain it. It has been concluded that, while the actual level of safety achieved in all member countries is probably much the same, this is difficult to prove in a quantitative way. In practice, all regulatory approaches require improvements to be made to correct deficiencies and when otherwise warranted. Based on contributions from members of the NEA Committee on Nuclear Regulatory Activities (CNRA), this publication provides an overview of current nuclear regulatory philosophies and approaches, as well as insights into a selection of public perception issues. This publication's intended audience is primarily nuclear safety regulators, but government authorities, nuclear power plant operators and the general public may also be interested. (author)

A formal safety analysis for PLC software-based safety critical system using Z

International Nuclear Information System (INIS)

Koh, Jung Soo

1997-02-01

This paper describes a formal safety analysis technique which is demonstrated by performing empirical formal safety analysis with the case study of beamline hutch door Interlock system that is developed by using PLC (Programmable Logic Controller) systems at the Pohang Accelerator Laboratory. In order to perform formal safety analysis, we have built the Z formal specifications representation from user requirement written in ambiguous natural language and target PLC ladder logic, respectively. We have also studied the effective method to express typical PLC timer component by using specific Z formal notation which is supported by temporal history. We present a formal proof technique specifying and verifying that the hazardous states are not introduced into ladder logic in the PLC-based safety critical system. And also, we have found that some errors or mismatches in user requirement and final implemented PLC ladder logic while analyzing the process of the consistency and completeness of Z translated formal specifications. In the case of relatively small systems like Beamline hutch door interlock system, a formal safety analysis including explicit proof is highly recommended so that the safety of PLC-based critical system may be enhanced and guaranteed. It also provides a helpful benefits enough to comprehend user requirement expressed by ambiguous natural language

Duty and role of Nuclear Regulation Authority facing a crucial moment

International Nuclear Information System (INIS)

Asaoka, Mie

2013-01-01

Duty of Nuclear Regulation Authority (NRA) was to restore public trust on nuclear regulation spoiled by the Fukushima nuclear accident. How applied such regulation as mandatory back-fitting based on latest knowledge and 40 year operational limit in principle became of great concern. Active faults issue on existing nuclear power station could be a touchstone. Safety side judgment and electric utilities side's proof responsibilities were required as more stringent criteria for active faults. The expert group had been working on assessment of fracture zones under the field survey. Reform of safety regulations should be done based on three important standpoints: (1) not business easiness but public safety was first (2) NRA keeping stance to judge its own safety standard and how NRA ought to be and (3) importance of public disclosure of information and participation in decision-making judging from greatness of public effects caused by nuclear disaster. (T. Tanaka)

Control of Nuclear Materials and Special Equipment (Nuclear Safety Regulations)

International Nuclear Information System (INIS)

Cizmek, A.; Prah, M.; Medakovic, S.; Ilijas, B.

2008-01-01

Based on Nuclear Safety Act (OG 173/03) the State Office for Nuclear Safety (SONS) in 2008 adopted beside Ordinance on performing nuclear activities (OG 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (OG 74/06) the new Ordinance on the control of nuclear material and special equipment (OG 15/08). Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a license to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance also lays down the manner in which nuclear material records have to be kept, the procedure for notifying the State administration organization (regulatory body) responsible for nuclear safety by the nuclear material user, and the keeping of registers of nuclear activities, nuclear material and special equipment by the State administration organization (regulatory body) responsible for nuclear safety, as well as the form and content of official nuclear safety inspector identification card and badge.(author)

French PWR Safety Philosophy

International Nuclear Information System (INIS)

Conte, M. M.

1986-01-01

The first 900 MWe units, built under the American Westinghouse licence and with reference to the U. S. regulation, were followed by 28 standardized units, C P1 and C P2 series. Increasing knowledge and lessons learned from starting and operating experience of French nuclear power plants, completed by the experience learned from the operation of foreign reactors, has contributed to the improvement of French PWR design and safety philosophy. As early as 1976, this experience was taken into account by French Safety organisms to discuss, with Electricite de France, the safety options for the planned 1300 MWe units, P4 and P4 series. In 1983, the new reactor scheduled, Ni4 series 1400 MWe, is a totally French design which satisfies the French regulations and other French standards and codes. Based on a deterministic approach, the French safety analysis was progressively completed by a probabilistic approach each of them having possibilities and limits. Increasing knowledge and lessons learned from operating experience have contributed to the French safety philosophy improvement. The methodology now applied to safety evaluation develops a new facet of the in depth defense concept by taking highly unlikely events into consideration, by developing the search of safety consistency of the design, and by completing the deterministic approach by the probabilistic one

Nature-Based Strategies for Improving Urban Health and Safety.

Science.gov (United States)

Kondo, Michelle C; South, Eugenia C; Branas, Charles C

2015-10-01

Place-based programs are being noticed as key opportunities to prevent disease and promote public health and safety for populations at-large. As one key type of place-based intervention, nature-based and green space strategies can play an especially large role in improving health and safety for dwellers in urban environments such as US legacy cities that lack nature and greenery. In this paper, we describe the current understanding of place-based influences on public health and safety. We focus on nonchemical environmental factors, many of which are related to urban abandonment and blight. We then review findings from studies of nature-based interventions regarding impacts on health, perceptions of safety, and crime. Based on our findings, we suggest that further research in this area will require (1) refined measures of green space, nature, and health and safety for cities, (2) interdisciplinary science and cross-sector policy collaboration, (3) observational studies as well as randomized controlled experiments and natural experiments using appropriate spatial counterfactuals and mixed methods, and (4) return-on-investment calculations of potential economic, social, and health costs and benefits of urban greening initiatives.

Guide to Radiation Safety regulations and guidelines (SSMFS 2012:3) on the management of contaminated ash

International Nuclear Information System (INIS)

Moere, Hans

2012-06-01

Energy producers burning peat or wood fuel can obtain ash that is contaminated with cesium-137 from Tjernobyl accident or naturally occurring uranium, thorium and potassium, from some peat bogs. Regulations (SSMFS 2012:3) have been developed which regulates how the contaminated ash should be handled. The regulations affect all who handle contaminated ash in incinerators, landfills, public works, ash recycling, transportation or recycling of ash in other ways. Radiation Safety regulations and guidelines (SSMFS 2012:3) on the management of contaminated ash will apply from 1 September 2012. At that time Regulations (SSMFS 2008:16) on the management of ash that is contaminated with cesium-137, ceases to apply. The contents have been incorporated into the new regulations. This report provides explanations and guidance to the Regulations in order to facilitate the practical application. This guidance is not legally binding

Mining Behavior Based Safety Data to Predict Safety Performance

Energy Technology Data Exchange (ETDEWEB)

Jeffrey C. Joe

2010-06-01

The Idaho National Laboratory (INL) operates a behavior based safety program called Safety Observations Achieve Results (SOAR). This peer-to-peer observation program encourages employees to perform in-field observations of each other's work practices and habits (i.e., behaviors). The underlying premise of conducting these observations is that more serious accidents are prevented from occurring because lower level “at risk” behaviors are identified and corrected before they can propagate into culturally accepted “unsafe” behaviors that result in injuries or fatalities. Although the approach increases employee involvement in safety, the premise of the program has not been subject to sufficient empirical evaluation. The INL now has a significant amount of SOAR data on these lower level “at risk” behaviors. This paper describes the use of data mining techniques to analyze these data to determine whether they can predict if and when a more serious accident will occur.

After the Fukushima Daiichi Accident, Extending the Human and Organizational Factors (HOF) Framework to Safety Regulation

International Nuclear Information System (INIS)

Chanton, O.; Mangeon, M.; Jeffroy, F.

2016-01-01

The accident of Fukushima-Daichi is regarded as a product of multiple failures of the nuclear risks regulation system in Japan and more particularly as a failure of the regulatory system (authorities, regulator and operator) to take into account seismic risks and flood risks caused by tsunamis. This statement conducted the French institute for radiological protection and nuclear safety (IRSN) to develop a research program dedicated to the study of the way the French nuclear regulatory system developed and addresses flood risks. A regulatory system rests upon a number of institutional and organizational devices and upon normative tools, such as technical standards or guidelines. The aim of these normative tools is to guide NPP operators during both stages of risks identification and characterisation and of the design of protections against risks. These instruments have profound and multiple effects on the stakeholders involved. They affect the design of nuclear facilities, significantly influence the safety demonstration of a plant, but also the manner in which the actions implemented by the operator are evaluated and their reality controlled by the regulator.

Building patient safety in intensive care nursing : Patient safety culture, team performance and simulation-based training

OpenAIRE

Ballangrud, Randi

2013-01-01

Aim: The overall aim of the thesis was to investigate patient safety culture, team performance and the use of simulation-based team training for building patient safety in intensive care nursing. Methods: Quantitative and qualitative methods were used. In Study I, 220 RNs from ten ICUs responded to a patient safety culture questionnaire analysed with statistics. Studies II-IV were based on an evaluation of a simulation-based team training programme. Studies II-III included 53 RNs from seven I...

On safety management and nuclear safety - A frame of reference for studies of safety management with examples from non-nuclear contects of relevance for nuclear safety

International Nuclear Information System (INIS)

Svenson, O.; Allwin, P.; Salo, I.

2004-03-01

The report includes three case studies of safety management. The studies are presented as chapters, but are written in a format that makes them easy to read separately. Two of the studies cover regulators (the Swedish Civil Aviation Safety Authority, Luftfartsinspektionen) and the Norwegian Petroleum Directorate) and one a regulated activity/industry (a car manufacturer, Volvo Car). The introduction outlines a living system framework and relates this to concepts used in organizational management. The report concludes with some findings with potential relevance for safety management in the nuclear power domain. In the next phase of the work, the regulated counterparts of the regulators here will be investigated in addition to a fourth case study of a regulated activity/industry. (au)

[Does simulator-based team training improve patient safety?].

Science.gov (United States)

Trentzsch, H; Urban, B; Sandmeyer, B; Hammer, T; Strohm, P C; Lazarovici, M

2013-10-01

Patient safety became paramount in medicine as well as in emergency medicine after it was recognized that preventable, adverse events significantly contributed to morbidity and mortality during hospital stay. The underlying errors cannot usually be explained by medical technical inadequacies only but are more due to difficulties in the transition of theoretical knowledge into tasks under the conditions of clinical reality. Crew Resource Management and Human Factors which determine safety and efficiency of humans in complex situations are suitable to control such sources of error. Simulation significantly improved safety in high reliability organizations, such as the aerospace industry.Thus, simulator-based team training has also been proposed for medical areas. As such training is consuming in cost, time and human resources, the question of the cost-benefit ratio obviously arises. This review outlines the effects of simulator-based team training on patient safety. Such course formats are not only capable of creating awareness and improvements in safety culture but also improve technical team performance and emphasize team performance as a clinical competence. A few studies even indicated improvement of patient-centered outcome, such as a reduced rate of adverse events but further studies are required in this respect. In summary, simulator-based team training should be accepted as a suitable strategy to improve patient safety.

V and V based Fault Estimation Method for Safety-Critical Software using BNs

International Nuclear Information System (INIS)

Eom, Heung Seop; Park, Gee Yong; Jang, Seung Cheol; Kang, Hyun Gook

2011-01-01

Quantitative software reliability measurement approaches have severe limitations in demonstrating the proper level of reliability for safety-critical software. These limitations can be overcome by using some other means of assessment. One of the promising candidates is based on the quality of the software development. Particularly in the nuclear industry, regulatory bodies in most countries do not accept the concept of quantitative goals as a sole means of meeting their regulations for the reliability of digital computers in NPPs, and use deterministic criteria for both hardware and software. The point of deterministic criteria is to assess the whole development process and its related activities during the software development life cycle for the acceptance of safety-critical software, and software V and V plays an important role in this process. In this light, we studied a V and V based fault estimation method using Bayesian Nets (BNs) to assess the reliability of safety-critical software, especially reactor protection system software in a NPP. The BNs in the study were made for an estimation of software faults and were based on the V and V frame, which governs the development of safety-critical software in the nuclear field. A case study was carried out for a reactor protection system that was developed as a part of the Korea Nuclear Instrumentation and Control System. The insight from the case study is that some important factors affecting the fault number of the target software include the residual faults in the system specification, maximum number of faults introduced in the development phase, ratio between process/function characteristic, uncertainty sizing, and fault elimination rate by inspection activities

Resolution 12/2004 Guideline for implementation of safety regulations in the practice of industrial radiography

International Nuclear Information System (INIS)

2004-01-01

1. This guide is intended to clarify, in relation to its application in practice Industrial Radiography, the provisions of: a) Joint Resolution CITMA-MINSAP, of December 15, 2002, Regulation: B asic Radiation Safety Standards , hereinafter Regulation NBS; b) Resolution No. 25/98 of CITMA Regulation. A uthorization Practices Associated with the use of ionizing radiation , hereinafter Resolution 25/98; c) Resolution 121/2000 CITMA Regulation: F or the Safe Transport of Radioactive materials , hereinafter Resolution 121/2000; and in d) Joint Resolution CITMA-MINSAP, Regulation: S election, Training and Authorization of personnel performing Employment Practices Associated Radiation Ionizing . 2. For the purposes of applying this Guide considers the practice of Industrial Radiography includes the following techniques: a) Industrial Radiography with use of gamma radiation sources; b) crawler radiography equipment; and c) Industrial Radiography with X-rays

International regulations on labour health and safety applied to fishing and maritime transport sectors. Are maritime workers under-protected.

Science.gov (United States)

Rodríguez, Julio Louro; Portela, Rosa Mary de la Campa; Pardo, Guadalupe Martín

2012-01-01

The work activity developed on board is of great importance in our nearby environment, and it has a series of peculiarities that determine the service rendering of sea workers. On the other hand, work at sea is developed on an international basis. Nowadays such work becomes a completely globalised industrial sector in relation to the elements that make up the ship's operation, including manpower. For that reason several relevant international organisations have paid attention to this industrial sector and have adopted a broad regulation on this matter. In the case of the European Union, the Community procedure emphasises enormous interest in providing specific and comprehensive training to seafarers, as well as in regulating working time on board with the aim of minimising the safety problems caused by fatigue. In the present article a schematic presentation of regulations on workers' health and occupational safety protection derived from the European Union, the International Maritime Organisation, and the International Labour Organisation has been done. Also it shows what parts of these regulations are not applicable to the work on board, and it reveals how the workers of fishing and maritime transport sectors are under-protected with regard to the guarantee of their health and occupational safety compared to workers in other sectors.

Safety Regulation Implemented by Gosatomnadzor of Russia

International Nuclear Information System (INIS)

Gutsalov, A.T.; Bukrinsky, A.M.

2001-01-01

The principles and approaches used by Gosatomnadzor of Russia in establishing safety goals are described. The link between safety goals and safety culture is demonstrated. Information on nuclear regulatory activities in Russia is also presented

Risk based limits for Operational Safety Requirements

International Nuclear Information System (INIS)

Cappucci, A.J. Jr.

1993-01-01

OSR limits are designed to protect the assumptions made in the facility safety analysis in order to preserve the safety envelope during facility operation. Normally, limits are set based on ''worst case conditions'' without regard to the likelihood (frequency) of a credible event occurring. In special cases where the accident analyses are based on ''time at risk'' arguments, it may be desirable to control the time at which the facility is at risk. A methodology has been developed to use OSR limits to control the source terms and the times these source terms would be available, thus controlling the acceptable risk to a nuclear process facility. The methodology defines a new term ''gram-days''. This term represents the area under a source term (inventory) vs time curve which represents the risk to the facility. Using the concept of gram-days (normalized to one year) allows the use of an accounting scheme to control the risk under the inventory vs time curve. The methodology results in at least three OSR limits: (1) control of the maximum inventory or source term, (2) control of the maximum gram-days for the period based on a source term weighted average, and (3) control of the maximum gram-days at the individual source term levels. Basing OSR limits on risk based safety analysis is feasible, and a basis for development of risk based limits is defensible. However, monitoring inventories and the frequencies required to maintain facility operation within the safety envelope may be complex and time consuming

What Can We Learn about Workplace Heat Stress Management from a Safety Regulator Complaints Database?

Science.gov (United States)

Hansen, Alana; Pisaniello, Dino; Varghese, Blesson; Rowett, Shelley; Hanson-Easey, Scott; Bi, Peng; Nitschke, Monika

2018-03-06

Heat exposure can be a health hazard for many Australian workers in both outdoor and indoor situations. With many heat-related incidents left unreported, it is often difficult to determine the underlying causal factors. This study aims to provide insights into perceptions of potentially unsafe or uncomfortably hot working conditions that can affect occupational health and safety using information provided by the public and workers to the safety regulator in South Australia (SafeWork SA). Details of complaints regarding heat exposure to the regulator's "Help Centre" were assembled in a dataset and the textual data analysed thematically. The findings showed that the majority of calls relate to indoor work environments such as kitchens, factories, and warehouses. The main themes identified were work environment, health effects, and organisational issues. Impacts of hot working conditions ranged from discomfort to serious heat-related illnesses. Poor management practices and inflexibility of supervisors featured strongly amongst callers' concerns. With temperatures predicted to increase and energy prices escalating, this timely study, using naturalistic data, highlights accounts of hot working conditions that can compromise workers' health and safety and the need for suitable measures to prevent heat stress. These could include risk assessments to assess the likelihood of heat stress in workplaces where excessively hot conditions prevail.

A regulator's viewpoint on the use of AI in the nuclear industry

International Nuclear Information System (INIS)

Wainwright, N.

1995-01-01

The regulatory position within the UK places the responsibility for safety on a nuclear site with the licensee. The licensee must produce a safety case that demonstrates that the plant is safe. Assessment of this safety case is performed by the regulator in the Health and Safety Executive (HSE) using HSE's published Safety Assessment Principles. This paper presents the personal views of a regulator on the use of artificial intelligence (AI) in the nuclear industry. The AI-based system considered are restricted to expert systems, neural networks and fuzzy logic. Some of the safety issues are discussed. The particular concerns associated with software-based systems are compounded by some of the inherent problems of AI-based systems. Such is the nature of these concerns that an acceptable safety case will be difficult to mount for safety systems and post-accident monitoring systems. However, given the present maturity of the technology, acceptable safety cases might be formulated in the areas of operator advisory systems designed to reduce accident frequencies, and robotics where dose reduction is important. There are also arguments that suggests that suitable safety cases could be formulated for AI-based plant control systems. Nevertheless, AI-based systems should be treated with caution - further research is required into suitable designs and safety demonstration techniques. (author)

Regulation and safety implementation of nanotechnology for chemical enterprises in the Central Europe Space

International Nuclear Information System (INIS)

Falk, A; Hartl, S; Sinner, F

2013-01-01

As result of the gradually increasing nanotechnology sector there is the necessity of a contemporary analysis of the present regulations used for nanomaterials, to outline the current situation of the nanotechnology sector, to promote international cooperation and research's coordination to overcome disciplinary boundaries, to fill the gap between more and less experienced regions and to turn investments in R and D in industrial innovations. The general objective of the Central Europe project NANOFORCE, which is developed by national and regional chemistry associations and R and D Centres of the Central Europe area, is to foster the innovative nanotechnology-sector networks across Central Europe regions by bringing together public and private organizations to carry out collaborative and interdisciplinary researches on nanomaterials (in the frame of REACH Regulation) and to turn the most promising laboratory results into innovative industrial applications. To build up a legal advisory board for chemical enterprises starting in nanotechnology, a state of the art report on existing safety procedures and nanotech related regulations was produced to give an overview on currently available regulations used by chemical industries and manufacturing companies within the European region to secure their products. The main emphasis was placed on REACH regulation to search for relevant sections concentrating on nanomaterials which are applicable for nanotechnology. In addition, all relevant directives and amendments of REACH were screened with regard to identify gaps where action is still needed and give possible recommendations for the European Commission. Beyond literature research a questionnaire for producers, users, researchers and financiers was developed with the goal to collect information about the nanotechnology sector in the CE region concerning development, financial status, and international cooperation within joint ventures, safety and nanotoxicology.

Regulation of occupational health and safety in the semiconductor industry: enforcement problems and solutions.

Science.gov (United States)

Watterson, Andrew

2006-01-01

Reports of high incidences of occupational illnesses in the semiconductor industry should have triggered global investigations and rigorous inspection of the industry. Yet semiconductor plants remain essentially unregulated. Health and safety standards are inadequate and enforcement is lax. Roles for stakeholders in laying down good practice, monitoring, and regulating are proposed, and obstacles are described. Effective regulation has advantages for the industry as well as workers. Conditions for best practice include education at all levels, protection and support for labor inspectors, government commitment to enforcing laws, recognition of the right of workers to organize, and recognition of their rights.

Aspects of the state safety regulation dealing with management of radioactive wastes from nuclear vessels

International Nuclear Information System (INIS)

Markarov, Valentin G.

1999-01-01

According to this presentation, the Constitution of the Russian Federation states that nuclear power engineering and fissile materials are under the jurisdiction of the Russian Federation. But there is no federal law with detailed directions for radioactive waste (RW) management, which thus comes under the Federal law ''On Use of Atomic Energy''. This law defines the legal basis and principles of regulating the relations occurring during RW management and sets some general requirements. RW management safety is regulated by the federal norms and rules (1) Radiation Safety Norms (NRB-96), Basic Sanitary Rules (OSP-72, 87) and (3) Sanitary Rules for RW Management (SPORO-85), etc. A number of normative documents on RW management will be put in force in 1999. For work in the field of RW management, licence must in general be obtained from Gozatomnazdor of Russia. The conditions for receiving a license for the management of RW from vessels are presented

Development of an FPGA-based controller for safety critical application

International Nuclear Information System (INIS)

Xing, A.; De Grosbois, J.; Sklyar, V.; Archer, P.; Awwal, A.

2011-01-01

In implementing safety functions, Field Programmable Gate Arrays (FPGA) technology offers a distinct combination of benefits and advantages over microprocessor-based systems. FPGAs can be designed such that the final product is purely hardware, without any overhead runtime software, bringing the design closer to a conventional hardware-based solution. On the other hand, FPGAs can implement more complex safety logic that would generally require microprocessor-based safety systems. There are now qualified FPGA-based platforms available on the market with a credible use history in safety applications in nuclear power plants. Atomic Energy of Canada (AECL), in collaboration with RPC Radiy, has initiated a development program to define a vigorous FPGA engineering process suitable for implementing safety critical functions at the application development level. This paper provides an update on the FPGA development program along with the proposed design model using function block diagrams for the development of safety controllers in CANDU applications. (author)

Software important to safety in nuclear power plants

International Nuclear Information System (INIS)

1994-01-01

The report provides guidance on current practices, documenting their strengths and weaknesses for dealing with the important issues of software engineering that nuclear power plant system designers, software producers and regulators are facing. The focus of the report is on safety critical applications of general purpose processors controlled by custom developed software; however, it should also have application in safety related applications and for other types of computers. In addition to system designers, software producers and regulators, the intended readership of this report includes users of software based systems, who should be aware of the relevant issues in specifying and obtaining software for systems important to safety. Refs, 1 fig., tabs

Role of systems safety in maintaining affordable safety in the 1980's

International Nuclear Information System (INIS)

Hollister, H.; Trauth, C.A. Jr.

1979-01-01

Historically, the Department of Energy and its predecessors have used and supported the development of systems safety programs, practices, and principles, finding them by and large adequate, effective, and managerially efficient. Today, attempts are bing made to resolve increasingly complex environmental, safety, and health problems by turning to increasingly complex and detailed regulation as the primary governmental answer. It is increasingly doubtful that such an approach will provide management of these issues and problems that is either effective or efficient. Challenge is issued to those in systems safety to develop and apply systems safety principles and practices more broadly to total operational systems and not just to hardware and to environmental and health protection and not just to safety, so that the total universe of environmental, safety, and health can be managed effectively and efficiently with encouragement of innovation and creativity, using a relatively brief and concise, but adequate, regulatory base

The Swedish Nuclear Power Inspectorate's Regulations concerning Safety in connection with the Disposal of Nuclear Material and Nuclear Waste. General Recommendations concerning the Application of the Swedish Nuclear Power Inspectorate's Regulations above

International Nuclear Information System (INIS)

2002-06-01

An english translation of the original Swedish regulations concerning the safety in disposal of nuclear wastes is published in this booklet, together with recommendations on how these regulations can be applied

Formal model-based development for safety-critical embedded software

International Nuclear Information System (INIS)

Kim, Jin Hyun; Choi, Jin Young

2005-01-01

Safety-critical embedded software for nuclear I and C system is developed under the safety and reliability regulation. Programmable logic controller(PLC) is a computer system for instrumentation and control (I and C) system of nuclear power plants. PLC consists of various I and C logics in software, including real-time operating system (RTOS). Hence, errors related with RTOS should be detected and eliminated in development processes. Practically, the verification and validation for errors in RTOS is performed in test procedure, in which a lot of tasks for testing are embedded in RTOS and are running under a test environments. But the test process can not be enough to guarantee the safety and reliability of RTOS. Therefore, in this paper, we introduce to applying formal methods with the development of software for the PLC. We particularity apply formal methods to a development of RTOS for PLC, which is a safety critical level. In this development, we use the state charts of I-Logix to specify and verification and model checking to verify the specification

Formal model-based development for safety-critical embedded software

Energy Technology Data Exchange (ETDEWEB)

Kim, Jin Hyun; Choi, Jin Young [Korea University, seoul (Korea, Republic of)

2005-11-15

Safety-critical embedded software for nuclear I and C system is developed under the safety and reliability regulation. Programmable logic controller(PLC) is a computer system for instrumentation and control (I and C) system of nuclear power plants. PLC consists of various I and C logics in software, including real-time operating system (RTOS). Hence, errors related with RTOS should be detected and eliminated in development processes. Practically, the verification and validation for errors in RTOS is performed in test procedure, in which a lot of tasks for testing are embedded in RTOS and are running under a test environments. But the test process can not be enough to guarantee the safety and reliability of RTOS. Therefore, in this paper, we introduce to applying formal methods with the development of software for the PLC. We particularity apply formal methods to a development of RTOS for PLC, which is a safety critical level. In this development, we use the state charts of I-Logix to specify and verification and model checking to verify the specification.

Commentary: Europe needs a central, transparent, and evidence based regulation process for devices

DEFF Research Database (Denmark)

Eikermaan, Michaela; Gluud, Christian; Perleth, Matthias

2013-01-01

Last September, the European Commission published proposals to update regulations for medical devices in order to improve patient safety.1 The proposals are being discussed by the European parliament where critical debate is being led by the Committee on Environment, Public Health and Food Safety...

76 FR 80850 - Special Local Regulations and Safety Zones; Recurring Events in Northern New England

Science.gov (United States)

2011-12-27

..., design, or operation; test methods; sampling procedures; and related management systems practices) that... safety of life or property. (f) For all power boat races listed, vessels operating within the regulated... that will not interfere with the progress of the event. (g) For all regattas and boat parades listed...

77 FR 15323 - Special Local Regulations and Safety Zone; War of 1812 Bicentennial Commemorations, Chesapeake...

Science.gov (United States)

2012-03-15

... National Technology Transfer and Advancement Act (NTTAA) (15 U.S.C. 272 note) directs agencies to use...] RIN 1625-AA08, AA00 Special Local Regulations and Safety Zone; War of 1812 Bicentennial Commemorations... Chesapeake Bay and Port of Baltimore, Maryland for War of 1812 Bicentennial Commemorations activities. This...

33 CFR 165.1319 - Safety Zone Regulations, Seafair Blue Angels Air Show Performance, Seattle, WA.

Science.gov (United States)

2010-07-01

... Blue Angels Air Show Performance, Seattle, WA. 165.1319 Section 165.1319 Navigation and Navigable... Thirteenth Coast Guard District § 165.1319 Safety Zone Regulations, Seafair Blue Angels Air Show Performance... Peninsula; thence northerly along the shore of Mercer Island to the point of origin. [Datum: NAD 1983] (c...

Adolescents' Attitudes towards E-cigarette Ingredients, Safety, Addictive Properties, Social Norms, and Regulation

OpenAIRE

Gorukanti, Anuradha; Delucchi, Kevin; Ling, Pamela; Fisher-Travis, Raymond; Halpern-Felsher, Bonnie

2016-01-01

E-cigarette use has dramatically increased. While studies have examined adolescents’ attitudes towards smoking, few have extended this research to adolescents’ attitudes towards e-cigarettes. The goal of this study was to examine adolescents' attitudes regarding e-cigarette ingredients, safety, addictive properties, social norms, accessibility, price, and regulation; and determine whether attitudes differ by past cigarette/e-cigarette use. Participants were 786 9th and 12th graders from Calif...

A hybrid approach to quantify software reliability in nuclear safety systems

International Nuclear Information System (INIS)

Arun Babu, P.; Senthil Kumar, C.; Murali, N.

2012-01-01

Highlights: ► A novel method to quantify software reliability using software verification and mutation testing in nuclear safety systems. ► Contributing factors that influence software reliability estimate. ► Approach to help regulators verify the reliability of safety critical software system during software licensing process. -- Abstract: Technological advancements have led to the use of computer based systems in safety critical applications. As computer based systems are being introduced in nuclear power plants, effective and efficient methods are needed to ensure dependability and compliance to high reliability requirements of systems important to safety. Even after several years of research, quantification of software reliability remains controversial and unresolved issue. Also, existing approaches have assumptions and limitations, which are not acceptable for safety applications. This paper proposes a theoretical approach combining software verification and mutation testing to quantify the software reliability in nuclear safety systems. The theoretical results obtained suggest that the software reliability depends on three factors: the test adequacy, the amount of software verification carried out and the reusability of verified code in the software. The proposed approach may help regulators in licensing computer based safety systems in nuclear reactors.

Evaluation of Safety Culture Implementation and Socialization Results

International Nuclear Information System (INIS)

Situmorang, Johnny

2003-01-01

Evaluation of safety culture implementation and socialization results has been perform. Evaluation is carried out with specifying safety culture indicators, namely: Meeting between management and employee, system for incidents analysis, training activities related to improving safety, meeting with regulator, contractors, surveys on behavioural attitudes, and resources allocated to promote safety culture. Evaluation is based on observation and visiting the facilities to show the compliance indicator in term of good practices in the frame of safety culture implementation. For three facilities of research reactors, Kartini Yogyakarta, TRIGA Mark II Bandung and MPR-GAS Serpong, implementation of safety culture is considered good enough and progressive. Furthermore some indicator should be considered more intensive, for example the allocated resources, self assesment based on own questionnaire in the frame of improving the safety culture implementation. (author)

The blameworthiness of health and safety rule violations

NARCIS (Netherlands)

P. Mascini (Peter)

2006-01-01

textabstractMan-made disasters usually lead to the tightening of safety regulations, because rule breaking is seen as a major cause of them. This reaction is based on the presumptions that the safety rules are good and that the rule-breakers are wrong. The reasons the personnel of a coke factory

The Blameworthiness of Health and Safety Rule Violations

NARCIS (Netherlands)

P. Mascini (Peter)

2005-01-01

textabstractMan-made disasters usually lead to the tightening of safety regulations, because rule breaking is seen as a major cause of them. This reaction is based on the assumptions that the safety rules are good and that the rule-breakers are wrong. The reasons the personnel of a coke factory

Review of the regulation and safety assessment of food substances in various countries and jurisdictions

Science.gov (United States)

Magnuson, Bernadene; Munro, Ian; Abbot, Peter; Baldwin, Nigel; Lopez-Garcia, Rebeca; Ly, Karen; McGirr, Larry; Roberts, Ashley; Socolovsky, Susan

2013-01-01

This review compares the regulations, definitions and approval processes for substances intentionally added to or unintentionally present in human food in the following specific countries/jurisdictions: Argentina, Australia, Brazil, Canada, China, the European Union, Japan, Mexico, New Zealand, and the United States. This includes direct food additives, food ingredients, flavouring agents, food enzymes and/or processing aids, food contact materials, novel foods, and nanoscale materials for food applications. The regulatory authority of each target jurisdiction/country uses its own regulatory framework and although the definitions, regulations and approval processes may vary among all target countries, in general there are many similarities. In all cases, the main purpose of each authority is to establish a regulatory framework and maintain/enforce regulations to ensure that food consumed and sold within its respective countries is safe. There is a move towards harmonisation of food regulations, as illustrated by Australia and New Zealand and by Mercosur. The European Union has also established regulations, which are applicable for all member states, to establish a common authorisation procedure for direct food additives, flavourings and enzymes. Although the path for approval of different categories of food additives varies from jurisdiction to jurisdiction, there are many commonalities in terms of the data requirements and considerations for assessment of the safety of use of food additives, including the use of positive lists of approved substances, pre-market approval, and a separation between science and policy decisions. The principles applied are largely reflective of the early work by the Joint FAO/WHO Expert Committee on Food Additives (JECFA) committees and JECFA assessments of the safety of food additives for human and animal foods. PMID:23781843

Cryogenic Safety Rules and Guidelines at CERN

CERN Multimedia

CERN. Geneva

2016-01-01

CERN defines and implements a Safety Policy that sets out the general principles governing safety at CERN. As an intergovernmental organisation, CERN further establishes its own Safety Rules as necessary for its proper functioning. In this process, it takes into account the laws and regulation of the Host States (France and Switzerland), EU regulations and directives, as well as international regulations, standards and directives. For the safety of cryogenic equipment, this is primarily covered by the Safety Regulation for Mechanical Equipment and the General Safety Instruction for Cryogenic Equipment. In addition, CERN has also developed Safety Guidelines to support the implementation of these safety rules, covering cryogenic equipment and oxygen deficiency hazard assessment and mitigation. An overview of the cryogenic safety rules and these safety guidelines will be presented.

Establishment of safety goal and its quantification based on risk assessment

International Nuclear Information System (INIS)

Miyano, Hiroshi; Muramatsu, Ken

2017-01-01

We must clarify the safety objectives sought by society in securing the safety of nuclear reactors and nuclear power plants. For that purpose, it is useful to utilize risk assessment. Quantitative methods including probabilistic risk assessment (PRA) are superior in terms of scientific rationality and quantitative performance compared with conventional deterministic methods, and able to indicate an objective numerical value of safety level. Consequently, quantitative methods can enhance the transparency, consistency, compliance, predictability, and explanatory power of regulatory decisions toward business operators and citizens. Business operators can explain the validity of their own safety assurance activities to regulators and citizens. The goal to be secured becomes clear by incorporating the safety goal into the specific performance goal required for the nuclear power plant from the viewpoint of deep safeguard, and it becomes easy to evaluate the effectiveness of the safety measures. It helps us greatly in judging and selecting the appropriateness of safety measures. It should be noted: the fact that the result of implementing the PRA satisfies the safety goal is not a sufficient condition in the sense of guaranteeing complete safety but a necessary condition. The nuclear power field is a region with large uncertainty, and research/efforts for accuracy improvement and evaluation validity will be required continuously. (A.O.)

United States import safety, environmental health, and food safety regulation in China.

Science.gov (United States)

Nyambok, Edward O; Kastner, Justin J

2012-01-01

China boasts a rapidly growing economy and is a leading food exporter. Since China has dominated world export markets in food, electronics, and toys, many safety concerns about Chinese exports have emerged. For example, many countries have had problems with Chinese food products and food-processing ingredients. Factors behind food safety and environmental health problems in China include poor industrial waste management, the use of counterfeit agricultural inputs, inadequate training of farmers on good farm management practices, and weak food safety laws and poor enforcement. In the face of rising import safety problems, the U.S. is now requiring certification of products and foreign importers, pursuing providing incentives to importers who uphold good safety practices, and considering publicizing the names of certified importers.

Development of fusion safety standards

International Nuclear Information System (INIS)

Longhurst, G.R.; Petti, D.A.; Dinneen, G.A.; Herring, J.S.; DeLooper, J.; Levine, J.D.; Gouge, M.J.

1996-01-01

Two new U.S. Department of Energy (DOE) standards have been prepared to assist in the design and regulation of magnetic fusion facilities. They are DOE-STD-6002-96, 'Safety of Magnetic Fusion Facilities - Requirements,' and DOE-STD-6003-96 'Safety of Magnetic Fusion Facilities - Guidance.' The first standard sets forth requirements, mostly based on the Code of Federal Regulations, deemed necessary for the safe design and operation of fusion facilities and a set of safety principles to use in the design. The second standard provides guidance on how to meet the requirements identified in DOE-STD-6002-96. It is written specifically for a facility such as the International Thermonuclear Experimental Reactor (ITER) in the DOE regulatory environment. As technical standards, they are applicable only to the extent that compliance with these standards is included in the contracts of the developers. 7 refs., 1 fig

A Nuclear Safety System based on Industrial Computer

International Nuclear Information System (INIS)

Kim, Ji Hyeon; Oh, Do Young; Lee, Nam Hoon; Kim, Chang Ho; Kim, Jae Hack

2011-01-01

The Plant Protection System(PPS), a nuclear safety Instrumentation and Control (I and C) system for Nuclear Power Plants(NPPs), generates reactor trip on abnormal reactor condition. The Core Protection Calculator System (CPCS) is a safety system that generates and transmits the channel trip signal to the PPS on an abnormal condition. Currently, these systems are designed on the Programmable Logic Controller(PLC) based system and it is necessary to consider a new system platform to adapt simpler system configuration and improved software development process. The CPCS was the first implementation using a micro computer in a nuclear power plant safety protection system in 1980 which have been deployed in Ulchin units 3,4,5,6 and Younggwang units 3,4,5,6. The CPCS software was developed in the Concurrent Micro5 minicomputer using assembly language and embedded into the Concurrent 3205 computer. Following the micro computer based CPCS, PLC based Common-Q platform has been used for the ShinKori/ShinWolsong units 1,2 PPS and CPCS, and the POSAFE-Q PLC platform is used for the ShinUlchin units 1,2 PPS and CPCS. In developing the next generation safety system platform, several factors (e.g., hardware/software reliability, flexibility, licensibility and industrial support) can be considered. This paper suggests an Industrial Computer(IC) based protection system that can be developed with improved flexibility without losing system reliability. The IC based system has the advantage of a simple system configuration with optimized processor boards because of improved processor performance and unlimited interoperability between the target system and development system that use commercial CASE tools. This paper presents the background to selecting the IC based system with a case study design of the CPCS. Eventually, this kind of platform can be used for nuclear power plant safety systems like the PPS, CPCS, Qualified Indication and Alarm . Pami(QIAS-P), and Engineering Safety

A Nuclear Safety System based on Industrial Computer

Energy Technology Data Exchange (ETDEWEB)

Kim, Ji Hyeon; Oh, Do Young; Lee, Nam Hoon; Kim, Chang Ho; Kim, Jae Hack [Korea Electric Power Corporation Engineering and Construction, Daejeon (Korea, Republic of)

2011-05-15

The Plant Protection System(PPS), a nuclear safety Instrumentation and Control (I and C) system for Nuclear Power Plants(NPPs), generates reactor trip on abnormal reactor condition. The Core Protection Calculator System (CPCS) is a safety system that generates and transmits the channel trip signal to the PPS on an abnormal condition. Currently, these systems are designed on the Programmable Logic Controller(PLC) based system and it is necessary to consider a new system platform to adapt simpler system configuration and improved software development process. The CPCS was the first implementation using a micro computer in a nuclear power plant safety protection system in 1980 which have been deployed in Ulchin units 3,4,5,6 and Younggwang units 3,4,5,6. The CPCS software was developed in the Concurrent Micro5 minicomputer using assembly language and embedded into the Concurrent 3205 computer. Following the micro computer based CPCS, PLC based Common-Q platform has been used for the ShinKori/ShinWolsong units 1,2 PPS and CPCS, and the POSAFE-Q PLC platform is used for the ShinUlchin units 1,2 PPS and CPCS. In developing the next generation safety system platform, several factors (e.g., hardware/software reliability, flexibility, licensibility and industrial support) can be considered. This paper suggests an Industrial Computer(IC) based protection system that can be developed with improved flexibility without losing system reliability. The IC based system has the advantage of a simple system configuration with optimized processor boards because of improved processor performance and unlimited interoperability between the target system and development system that use commercial CASE tools. This paper presents the background to selecting the IC based system with a case study design of the CPCS. Eventually, this kind of platform can be used for nuclear power plant safety systems like the PPS, CPCS, Qualified Indication and Alarm . Pami(QIAS-P), and Engineering Safety

U.S. Nuclear Regulatory Commission Safety Culture Oversight

International Nuclear Information System (INIS)

Sieracki, D. J.

2016-01-01

The NRC recognises that it is important for all organizations performing or overseeing regulated activities to establish and maintain a positive safety culture commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The NRC’s approach to safety culture is based on the premise that licencees bear the primary responsibility for safety. The NRC provides oversight of safety culture through expectations detailed in policy statements, safety culture assessor training for NRC inspectors, the oversight process, and the Allegations and Enforcement Programs. The NRC’s Safety Culture Policy Statement (SCPS) sets forth the Commission’s expectation that individuals and organizations establish and maintain a positive safety culture commensurate with the safety and security significance of their activities and the nature and complexity of their organizations and functions. The SCPS is not a regulation. It applies to all licencees, certificate holders, permit holders, authorisation holders, holders of quality assurance program approvals, vendors and suppliers of safety-related components, and applicants for a licence, certificate, permit, authorisation, or quality assurance program approval, subject to NRC authority.

Nature-based strategies for improving urban health and safety

Science.gov (United States)

Michelle C. Kondo; Eugenia C. South; Charles C. Branas

2015-01-01

Place-based programs are being noticed as key opportunities to prevent disease and promote public health and safety for populations at-large. As one key type of place-based intervention, nature-based and green space strategies can play an especially large role in improving health and safety for dwellers in urban environments such as US legacy cities that lack nature...

Reliability analysis of software based safety functions

International Nuclear Information System (INIS)

Pulkkinen, U.

1993-05-01

The methods applicable in the reliability analysis of software based safety functions are described in the report. Although the safety functions also include other components, the main emphasis in the report is on the reliability analysis of software. The check list type qualitative reliability analysis methods, such as failure mode and effects analysis (FMEA), are described, as well as the software fault tree analysis. The safety analysis based on the Petri nets is discussed. The most essential concepts and models of quantitative software reliability analysis are described. The most common software metrics and their combined use with software reliability models are discussed. The application of software reliability models in PSA is evaluated; it is observed that the recent software reliability models do not produce the estimates needed in PSA directly. As a result from the study some recommendations and conclusions are drawn. The need of formal methods in the analysis and development of software based systems, the applicability of qualitative reliability engineering methods in connection to PSA and the need to make more precise the requirements for software based systems and their analyses in the regulatory guides should be mentioned. (orig.). (46 refs., 13 figs., 1 tab.)

THE FLUORBOARD A STATISTICALLY BASED DASHBOARD METHOD FOR IMPROVING SAFETY

International Nuclear Information System (INIS)

PREVETTE, S.S.

2005-01-01

The FluorBoard is a statistically based dashboard method for improving safety. Fluor Hanford has achieved significant safety improvements--including more than a 80% reduction in OSHA cases per 200,000 hours, during its work at the US Department of Energy's Hanford Site in Washington state. The massive project on the former nuclear materials production site is considered one of the largest environmental cleanup projects in the world. Fluor Hanford's safety improvements were achieved by a committed partnering of workers, managers, and statistical methodology. Safety achievements at the site have been due to a systematic approach to safety. This includes excellent cooperation between the field workers, the safety professionals, and management through OSHA Voluntary Protection Program principles. Fluor corporate values are centered around safety, and safety excellence is important for every manager in every project. In addition, Fluor Hanford has utilized a rigorous approach to using its safety statistics, based upon Dr. Shewhart's control charts, and Dr. Deming's management and quality methods

Overview of Risk Mitigation for Safety-Critical Computer-Based Systems

Science.gov (United States)

Torres-Pomales, Wilfredo

2015-01-01

This report presents a high-level overview of a general strategy to mitigate the risks from threats to safety-critical computer-based systems. In this context, a safety threat is a process or phenomenon that can cause operational safety hazards in the form of computational system failures. This report is intended to provide insight into the safety-risk mitigation problem and the characteristics of potential solutions. The limitations of the general risk mitigation strategy are discussed and some options to overcome these limitations are provided. This work is part of an ongoing effort to enable well-founded assurance of safety-related properties of complex safety-critical computer-based aircraft systems by developing an effective capability to model and reason about the safety implications of system requirements and design.

Why does Safety Culture Matter?

International Nuclear Information System (INIS)

Dahlgren-Persson, Kerstin

2008-01-01

Dr. Kerstin Dahlgren-Persson, from the IAEA presented a plenary paper on 'Why does safety culture matter?'. The paper discussed the main conclusions of a 1998 IAEA conference on shortcomings in safety management. The conference included case studies of TVA, Cooper, Peach Bottom, Millstone, Ontario Hydro, Barsebaeck and Oskarshamn. Common symptoms included insularity; disproportionate focus on technical issues, high initial performance, lack of corporate oversight, changing management direction and cost cutting, repeat problems, and regulatory dissatisfaction. Behind these symptoms was lack of senior utility leadership with the insight, knowledge and ability to manage the unique interaction between the technology, economics, human factors and safety in a changing nuclear environment. Shortcomings relating to the regulator included lack of criteria for when regulatory actions should be taken in response to degradations in safety management, and the inability of some regulators to influence at the senior utility management level. The paper also made the following key points: - Human error is not always symptomatic of a poor safety culture. Effective root cause analysis (such as that carried out for the Columbia accident investigation) is essential to correctly differentiate between situational issues at a point in time and those rooted in organizational culture. - Leaders change culture by holding different assumptions and by making them visible through their words and action. - Regulators should consider how their regulatory strategy influences licensees. For example, a prescriptive strategy can foster a compliance based approach

Prescribing safety, negotiating expertise. Building of nuclear safety human factors expertise

International Nuclear Information System (INIS)

Rolina, Gregory

2008-01-01

This Ph.D thesis is dedicated to a specific type of expertise, the safety of nuclear installations in the field of human and organisational factors. Empirical work is at the foundation of this thesis: the monitoring of experts 'in action', allowed a detailed reconstruction of three cases they were examining. The analysis, at the core of which lies the definition of what an efficient expertise can be, emphasizes the incompleteness of the knowledge that links together the nuclear facilities' organisational characteristics and their safety. This leads us to identify the expert's three ranges of actions (rhetorical, cognitive, operative). Defined from objectives and constraints likely to influence the expert's behaviour, those three ranges each require specific skills. A conception of expertise based on these ranges seems adaptable to other sectors and allows an enrichment of models of expertise cited in literature. Historical elements from French institutions of nuclear safety are also called upon to take into consideration some of the determinants of the expertise; its efficiency relies on the upholding of a continuous dialogue between the regulators (the experts and the control authority) and the regulated (the operators). This type of historically inherited regulation makes up a specificity of the French system of external control of nuclear risks. (author) [fr

Safety assessment of food and feed from biotechnology-derived crops employing RNA-mediated gene regulation to achieve desired traits: a scientific review.