National report of Brazil: nuclear safety convention - September 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

National report of Brazil: nuclear safety convention - September 1998

International Nuclear Information System (INIS)

1998-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The last chapter describes plans and future activities to further enhance the safety of nuclear installations in Brazil

Second review meeting of the Contracting Parties to the Convention on Nuclear Safety

International Nuclear Information System (INIS)

Rafferty, Barbara

2002-01-01

identified that require special attention, particularly, with regard to safety management, safety culture, plant ageing, upgrading and effectiveness of regulatory practices, as well as maintaining competence and knowledge in the industry, regulatory bodies and research institutions. The review process highlighted factors and circumstances, external to nuclear safety as such, which nevertheless may impact on nuclear safety. Contracting Parties were invited to provide further information in their next national reports on maintaining competence and motivation of staff needed for safe regulation and operation of nuclear installation. Since the 1999 Review Meeting, several Contracting Parties have restructured their regulatory bodies and adopted new legislation or improved existing legislation to more closely meet the requirements of the Convention. Examples of areas of new legislation are: establishing independent regulatory bodies; emergency preparedness; decommissioning; and radiation protection provisions consistent with the International Commission on Radiological Protection's 1990 Recommendations (ICRP 60) and the International Basic Safety Standards published by the IAEA (BSS). Full implementation of the ICRP 60 recommendations and BSS is not complete in some countries. Contracting Parties reported on their individual national regulatory strategies. Some Contracting Parties use probabilistic safety assessment (PSA) as an additional tool in optimizing their regulatory or inspection activities, and some use performance indicators, whether they be quantitative or qualitative, to monitor the safety of their nuclear installations. In discussions, comparison was made of the advantages and disadvantages of regulations that are detailed and prescriptive in nature as compared to less prescriptive, goal-oriented approaches and the complementary use of risk assessments. Contracting Parties agreed to review their experience and report at the next Review Meeting. All Contracting

Clear progress in nuclear safety worldwide: Convention on nuclear safety concludes

International Nuclear Information System (INIS)

2002-01-01

It has been concluded that a significant progress has been observed in a number of key areas, such as strengthened legislation, regulatory independence, the availability of financial resources, enhanced emergency preparedness and safety improvements at nuclear power plants built to earlier standards. The objective of the Convention is to achieve and maintain a high level of nuclear safety worldwide. During the two week Review Meeting, parties engaged in a 'peer review' process in which the National Reports from individual States were collectively examined and discussed, with written replies provided to all the questions raised. Clear improvement was noted in the quality of the National Reports, the number of questions and the openness and quality of discussion and answers. The Contracting Parties praised the IAEA's various safety review missions and services, which they use widely to help enhance the effectiveness of their national safety arrangements. Forty-six contracting parties participated at the Review Meeting with over 400 delegates attending, including many heads and senior officers from regulatory bodies and experts from industry. To date, the Convention has been signed by sixty-five States and ratified by fifty-four, representing 428 of the 448 nuclear power reactors worldwide

Sweden's first national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2003-01-01

This report is issued according to Article 32 of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Sweden signed the Joint Convention September 29, 1997 and the Joint Convention entered into force on June 18, 2001. The areas covered by the Joint Convention have been incorporated in the Swedish system for spent fuel and radioactive waste management for a long time. The Swedish Government considered at the time of signing of the Joint Convention that the safety philosophy, legislation and the safety work conducted by the licensees and the authorities in Sweden complied with the obligations of the Convention. This is confirmed in the present report. The Swedish Government directed the Swedish Nuclear Power Inspectorate (SKI) to prepare this report in co-operation with the Swedish Radiation Protection Authority (SSI). A working group of five persons, with representatives from SKI, SSI and the Swedish Nuclear Fuel and Waste Management Co. (SKB), has prepared this report. The report has been discussed in the boards of SKI and SSI. The Swedish Government adopted the report in April 2003. Section A of this report provides an overview of the Swedish nuclear waste programme, including a brief historical review, in order to give the reader a background to the current programme for the management of spent fuel and radioactive waste. Sections B to J provide information on which the conclusions are drawn about the compliance with the obligations of the Joint Convention. By necessity this information is rather brief and strongly focused on those aspects which are addressed in the articles. Too many details and additional information would over-load the report and make the review process difficult. The goal has been to provide enough details to make the Swedish practices understandable. Data that might be missing will be added on request as a part of the review process. Article 32 of the Joint Convention calls for a self

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. Fourth National Report on Compliance with the Joint Convention Obligations. France

International Nuclear Information System (INIS)

2011-09-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. This report is the fourth of its kind. It is published in accordance with Article 32 of the Joint Convention and presents the measures taken by France to meet each of her obligations set out in the Convention. The facilities and radioactive materials covered by the Joint Convention are much diversified in nature and are controlled in France by different regulatory authorities (see Section E). Over and above a specific threshold of radioactive content, a facility is referred to as a 'basic nuclear facility' (installation nucleaire de base - INB) and placed under the control of the French Nuclear Safety Authority (Autorite de surete nucleaire - ASN). Below that threshold and provided that the facility involved falls under a category of the nomenclature of classified facilities for other purposes than their radioactive materials, any facility may be considered as a 'classified facility on environmental-protection grounds' (installation classee pour la protection de l'environnement - ICPE) and placed under the control of the Ministry for the

Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

International Nuclear Information System (INIS)

1997-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 5 September 1997 by a Diplomatic Conference convened by the IAEA from 1 to 5 September 1997. The Joint Convention was opened for signature at Vienna on 29 September 1997 during the forty-first session of the General Conference of the IAEA. This document reproduces the text of the Convention

Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-12-24

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management was adopted on 5 September 1997 by a Diplomatic Conference convened by the IAEA from 1 to 5 September 1997. The Joint Convention was opened for signature at Vienna on 29 September 1997 during the forty-first session of the General Conference of the IAEA. This document reproduces the text of the Convention.

Atomic Information Technology Safety and Economy of Nuclear Power Plants

CERN Document Server

Woo, Taeho

2012-01-01

Atomic Information Technology revaluates current conceptions of the information technology aspects of the nuclear industry. Economic and safety research in the nuclear energy sector are explored, considering statistical methods which incorporate Monte-Carlo simulations for practical applications. Divided into three sections, Atomic Information Technology covers: • Atomic economics and management, • Atomic safety and reliability, and • Atomic safeguarding and security. Either as a standalone volume or as a companion to conventional nuclear safety and reliability books, Atomic Information Technology acts as a concise and thorough reference on statistical assessment technology in the nuclear industry. Students and industry professionals alike will find this a key tool in expanding and updating their understanding of this industry and the applications of information technology within it.

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Risoluti, P.

2004-01-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management (the Joint Convention) is the only legally binding international treaty in the area of radioactive waste management. It was adopted by a Diplomatic Conference in September 1997 and opened for signature on 29 September 1997. The Convention entered into force on 18 June 1998, and to date (September 04) has been signed by 42 States, of which 34 have formally ratified, thus becoming Contracting Parties. The Joint Convention applies to spent fuel and radioactive waste resulting from civilian application. Its principal aim is to achieve and maintain a high degree of safety in their management worldwide. The Convention is an incentive instrument, not designed to ensure fulfillment of obligations through control and sanction, but by a peer pressure. The obligations of the Contracting Parties are mainly based on the international safety standards developed by the IAEA in past decades. The Convention is intended for all countries generating radioactive waste. Therefore it is relevant not only for those using nuclear power, but for any country where application of nuclear energy in medicine, conventional industry and research is currently used. Obligations of Contracting Parties include attending periodic Review Meetings and prepare National Reports for review by the other Contracting Parties. The National Reports should describe how the country is complying with the requirements of the Articles of the Convention. The first such meeting was held at the IAEA headquarters in November 2003. This paper will describe the origin of the Convention, present its content, the expected outcome for the worldwide safety, and the benefits for a country to be part of it

Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Third national report on the implementation of obligations of the Joint Convention

International Nuclear Information System (INIS)

2008-09-01

This report is published in compliance with the Joint Convention and presents the measures implemented by France to comply with each of the obligations defined by this convention. The structure of the report refers to the articles of the Convention. Therefore, after a presentation of the main evolutions since France's previous report, the following themes are addressed: policies and practices, scope of application, inventories and lists, legislative and regulatory system, other general safety provisions, safety of spent fuel management, trans-boundary movement, disused sealed sources, and planned activities to improve safety

National report of the Slovak Republic. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. 2005

International Nuclear Information System (INIS)

Hekel, P.; Ivan, J.; Lukacovic, K.; Parimucha, F.; Suss, J; Tomek, J.; Jurina, V.; Kobzova, D.; Konecny, L.; Homola, J.; Zavazanova, A.; Metke, E.; Turner, M.; Vaclav, J.; Ziakova, M.; Pospisil, M.; Petrik, T.

2005-09-01

The National Report (Compiled in terms of the Joint Convention - September 2005) contains information how each of the obligations of the Joint Convention have been implemented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) and other Slovak organisations are presented. These activities are reported under the headings: (A) Introduction; (B) Spent fuel and radioactive waste management; C) Scope of application; (D) Inventories and lists; (E) Legislation and regulation; (F) Other general safety provisions; (G) Safety of spent fuel management; (H) Safety of RAW management; (I) Transboundary movement of SF and RAW; (J) Disused sealed sources; (K) planned activiries to improve safety; (L) Annexes

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

These Guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 of the Convention and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views. [fr

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

These Guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 of the Convention and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views.

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

These Guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 of the Convention and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views. [es

Guidelines regarding National Reports under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2013-01-01

These Guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention on Nuclear Safety (hereinafter called the Convention), are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties regarding material that may be useful to include in the National Reports required under Article 5 of the Convention and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention.

Convention on nuclear safety. Rules of procedure and financial rules

International Nuclear Information System (INIS)

1999-01-01

The document is the first revision of the Rules of Procedures and Financial Rules that apply mutatis mutandis to any meetings of the Contracting Parties to the Convention on Nuclear Safety (INFCIRC/573), convened in accordance with the Chapter 3 of the Convention

Convention on Nuclear Safety. Rules of procedure and financial rules

International Nuclear Information System (INIS)

2002-01-01

The document is the second revision of the Rules of Procedures and Financial Rules that apply mutatis mutandis to any meetings of the Contracting Parties to the Convention on Nuclear Safety (INFCIRC/573), convened in accordance with the Chapter 3 of the Convention

France - Convention on Nuclear Safety. Sixth National report for the 2014 review meeting

International Nuclear Information System (INIS)

2013-07-01

The Convention on Nuclear Safety, hereinafter referred to as 'the Convention', is one of the results of international discussions initiated in 1992 in order to contribute to maintaining a high level of nuclear safety worldwide. The convention sets a number of nuclear safety objectives and defines measures to meet them. France signed the Convention on 20 September 1994, the date on which it was opened for signature during the IAEA General Conference, and approved it on 13 September 1995. The Convention entered into force on 24 October 1996. For many years France has been participating actively in international initiatives to enhance nuclear safety. It considers the Convention on Nuclear Safety to be an important instrument for achieving this aim. The areas covered by the Convention have long been part of the French approach to nuclear safety. The purpose of this sixth report, which was drafted pursuant to Article 5 of the Convention and which covers the period 2010 to mid-2013, is to present the measures taken by France in order to fulfil each of its obligations as specified in the said Convention. Since the Convention applies to all nuclear-power generating reactors most of this report is dedicated to the measures taken in order to ensure their safety. However, as in previous reports, France has decided in this sixth report also to present the measures that were taken for all research reactors. First of all, research reactors are actually subject to the same overall regulations as nuclear-power reactors with regard to safety and radiation protection. Then, within the framework of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, to which France is a Contracting Party, an account was made of the measures taken in those respective fields with regard to research reactors. Lastly, the Board of Governors of the International Atomic Energy Agency (IAEA), of which France is a member, in March 2004 approved the Code

Implementation of the obligations of the Convention on Nuclear Safety. The first Swiss report in accordance with Article 5

International Nuclear Information System (INIS)

1998-09-01

This report is issued according to Article 5 of the International Convention on Nuclear Safety. It has been produced by the Swiss Federal Nuclear Safety Inspectorate. Before submission to the Federal Department of Environment, Transport, Energy and Communication, the report has been commented by the Federal Office of Energy (BFE/OFEN), the Swiss Federal Nuclear Safety Commission (KSA/CSA), and the Swiss nuclear power plants of Beznau, Leibstadt and Muehleberg. The Goesgen nuclear power plant has chosen not to comment on the report. The introduction to the report provides general information about Switzerland, a brief political history of nuclear power and an overview of the nuclear facilities in Switzerland. In the subsequent sections, numbered after the Articles 6 to 19 of the Convention on Nuclear Safety, key aspects are commented on in such a way as to give a clear indication on how the various duties imposed by the Convention are fulfilled in Switzerland

Implementation of the obligations of the Convention on Nuclear Safety. The first Swiss report in accordance with Article 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This report is issued according to Article 5 of the International Convention on Nuclear Safety. It has been produced by the Swiss Federal Nuclear Safety Inspectorate. Before submission to the Federal Department of Environment, Transport, Energy and Communication, the report has been commented by the Federal Office of Energy (BFE/OFEN), the Swiss Federal Nuclear Safety Commission (KSA/CSA), and the Swiss nuclear power plants of Beznau, Leibstadt and Muehleberg. The Goesgen nuclear power plant has chosen not to comment on the report. The introduction to the report provides general information about Switzerland, a brief political history of nuclear power and an overview of the nuclear facilities in Switzerland. In the subsequent sections, numbered after the Articles 6 to 19 of the Convention on Nuclear Safety, key aspects are commented on in such a way as to give a clear indication on how the various duties imposed by the Convention are fulfilled in Switzerland.

Second Meeting for Evaluation of the Nuclear Safety Convention

International Nuclear Information System (INIS)

2002-01-01

This report presents the results of the Second Meeting for Evaluation of the Nuclear Safety Convention. the CSN. as the only competent Government organism on nuclear safety, represented Spain in the preparation of the national report and at the Review Meeting, acquiring a set of obligations for the next three years, until the holding of third meeting. (Author)

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views [fr

Guidelines regarding the review process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2002-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views

Guidelines regarding the review process under the convention on nuclear safety

International Nuclear Information System (INIS)

1998-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing national reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of national reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views

Guidelines regarding the review process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

1999-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing national reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of national reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views

Guidelines regarding the Review Process under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties on the process for reviewing National Reports submitted in accordance with Article 5 and thereby to facilitate the efficient review of implementation by the Contracting Parties of their obligations under the Convention. The aim of the review process should be to achieve a thorough examination of National Reports submitted in accordance with Article 5 of the Convention, so that Contracting Parties can learn from each other's solutions to common and individual nuclear safety problems and, above all, contribute to improving nuclear safety worldwide through a constructive exchange of views [es

Sweden's second national report under the Convention on nuclear safety. Swedish implementation of the obligations of the Convention

International Nuclear Information System (INIS)

2001-01-01

The National Reports to the Review Meetings according to Article 5 of the Convention call for a self-assessment of each Contracting Party with regard to compliance with the obligations of the Convention. For Sweden this self-assessment has demonstrated full compliance with all the obligations of the Convention, as shown in detail in part B of this National Report. Sweden wishes to emphasise the incentive character of the Convention. In the opinion of Sweden, the Convention implies a commitment to continuous learning from experience and a proactive approach to safety improvement. Therefore, Sweden has found it important that a National Report highlights strong features in national nuclear practices as well as areas where special attention to the further development are needed. Since the first report to the Convention was issued, three major events have been experienced in the Swedish nuclear programme: Phase out of nuclear power started by the closing of one unit of a twin unit plant on 30 November 1999. The full effects of deregulation of the electricity market have been experienced. Together with increasing taxes on nuclear power, this has strongly affected the production economy of the nuclear industry resulting in efforts to reduce production costs and leaving less room for investments. The new general safety regulations came into force 1 July 1999, resulting in a more structured approach to inspection and safety assessment. These changes have created new challenges for the safety work of the licensees as well as for the regulatory bodies during the last three years. However, the generally positive impression reported to the first review meeting under the Convention still stands. Therefore, Sweden would like to point out the following as strong features in its national nuclear practice: The responsibility for safety is very well defined in the Swedish legal framework. In order not to dilute the responsibility of the licence holders, the Swedish regulations are

The IAEA nuclear safety conventions: an example of successful ''treaty management''?

International Nuclear Information System (INIS)

Handl, G.

2003-01-01

The nuclear safety conventions represent an advance in bringing national nuclear power activities within the ambition of international legal safety norms. They introduce a novel measure of international legal accountability for the safety of commercial nuclear power operations. But whether this system represents a successful example of treaty management defies an easy answer. Certainly, it is beyond doubt that the peer review process combines aspects of law application(enforcement/control of implementation and compliance) with lawmaking. The nuclear safety convention bear the characteristics of a political compromise that affects effectiveness. For the time being it remains unclear whether this compromise will prove acceptable in the long run or how the tension between the two contending perspectives is likely to resolve itself. (N.C.)

Results of 6th Review Meeting and Perspective of the 7th Review Meeting of the Convention on Nuclear Safety

International Nuclear Information System (INIS)

Lee, Sukho; Kim, Manwoong; You, Jeongwon; Lee, Youngeal

2017-01-01

This paper highlighted the objective and role of the Convention on Nuclear Safety organized by the IAEA. The Convention provides Member States to demonstrate and share how to maintain and improve the level of nuclear safety. The results of the 6 th review meeting were implemented for safety improvements and to prepare for 7 th national report. Seven and a half months before the 7 th Review Meeting, the National Report has submitted on steps and measures taken to implement Convention obligations. The Contracting Parties reviewed each other’s reports, and exchanged written questions, written answers and comments. The discussions in the Country Group sessions were generally good with a lively and frank exchange of information. The Country Groups noted the significant measures taken by Contracting Parties to improve nuclear safety and identified a number of good practices to be shared with all Contracting Parties.

Guidelines regarding National Reports under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention on Nuclear Safety (hereinafter called the Convention), are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties regarding material that it may be useful to include in the National Reports required under Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention [es

Guidelines regarding National Reports under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2011-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention on Nuclear Safety (hereinafter called the Convention), are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties regarding material that it may be useful to include in the National Reports required under Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention

Achievements and Perspectives of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Louvat, D.; Lacoste, A.C.

2006-01-01

The Joint Convention on the Safety of Spent Fuel management and on the Safety of Radioactive Waste Management is the first legal instrument to directly address the safety of spent fuel and radioactive waste management on a global scale. The Joint Convention entered into force in 2001. This paper describes its process and its main achievements to date. The perspectives to establish of a Global Waste Safety Regime based on the Joint Convention are also discussed. (authors)

Sweden's fourth national report under the Joint Convention on the safety of spent fuel management and the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2011-01-01

Sweden signed Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) September 29, 1997. Sweden ratified the Joint Convention about two years later and is a Contracting Party to the Joint Convention since July 29, 1999. The Joint Convention entered into force on June 18, 2001. Each member nation having ratified the Joint Convention (Contracting Party) is obligated to prepare a National Report covering the scope of the Joint Convention and subject it to review by other Contracting Parties at Review Meetings held in Vienna, Austria. Sweden participated in the First Review Meeting in November 2003, the Second Review Meeting in May 2006 and the Third Review Meeting in May 2009. This report is the fourth Swedish National Report under the Joint Convention. This report satisfies the requirements of the Joint Convention for reporting on the status of safety at spent fuel and radioactive waste management facilities within Sweden. It constitutes an updated document with basically the same structure as the previous national reports under the terms of the Joint Convention and reflects developments in Sweden through December 2010. It will be subject to review at the Fourth Review Meeting of the Contracting Parties in Vienna, Austria, in May 2012

Second national report of Brazil for the nuclear safety convention - September 2001

International Nuclear Information System (INIS)

2001-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The chapter 6 describes plans and future activities to further enhance the safety of nuclear installations in Brazil

Second national report of Brazil for the nuclear safety convention - September 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

This National Report was prepared by a group composed of representatives of the various Brazilian organizations with responsibilities in the field of nuclear safety, aiming the fulfilling the Convention of Nuclear Energy obligations. The Report contains a description of the Brazilian policy and programme on the safety of nuclear installations, and an article by article description of the measures Brazil is undertaking in order to implement the obligations described in the Convention. The chapter 6 describes plans and future activities to further enhance the safety of nuclear installations in Brazil.

National nuclear safety report 2005. Convention on nuclear safety

International Nuclear Information System (INIS)

2006-01-01

This National Nuclear Safety Report was presented at the 3rd. Review meeting. In general the information contained in the report are: Highlights / Themes; Follow-up from 2nd. Review meeting; Challenges, achievements and good practices; Planned measures to improve safety; Updates to National report to 3rd. Review meeting; Questions from peer review of National Report; and Conclusions

Convention on nuclear safety. Questions posted to Switzerland in 2008

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

Switzerland signed the Convention on Nuclear Safety (CNS) on 31 October 1995. It ratified the Convention on 12 September 1996, which came into force on 11 December 1996. In accordance with Article 5 of the Convention, Switzerland has prepared and submitted 4 country reports for Review Meetings of Contracting Parties organised in 1999, 2002, 2005 and 2006. These meetings at the IAEA headquarters in Vienna were attended by a Swiss delegation. Most of the requirements of the articles of the Convention were already standard practice in Switzerland. In the last years, all Swiss nuclear power plants (NPPs) as well as the Swiss Federal Nuclear Safety Inspectorate (HSK) built up documented quality management systems. The independence of HSK from licensing authorities is fulfilled on a technical level. In 2005, a new Nuclear Energy Act came into force requiring formal independence of the supervisory authorities from the licensing authorities. A separate act to legally settle the Inspectorate's fully independent status was adopted by Parliament. HSK participates in international co-operation and is represented in numerous nuclear safety working groups in order to ensure the exchange of scientific, technical and regulatory know-how. The regulatory processes applied to the licensing and safety surveillance of nuclear installations and their operation are up to date with the current state of science and technology. Deterministic and probabilistic safety evaluations guide and prioritise inspections and provide the basis for a graded approach to safety review and assessment. The surveillance of the NPPs' operating, control and safety systems, their component performance and integrity, their organisational and human aspects as well as the management, conditioning and interim storage of radioactive waste are permanent features of the supervisory authority's activities. Within the frame of a new integrated oversight process there is an annual systematic assessment of

Convention on nuclear safety. Questions posted to Switzerland in 2008

International Nuclear Information System (INIS)

2008-01-01

Switzerland signed the Convention on Nuclear Safety (CNS) on 31 October 1995. It ratified the Convention on 12 September 1996, which came into force on 11 December 1996. In accordance with Article 5 of the Convention, Switzerland has prepared and submitted 4 country reports for Review Meetings of Contracting Parties organised in 1999, 2002, 2005 and 2006. These meetings at the IAEA headquarters in Vienna were attended by a Swiss delegation. Most of the requirements of the articles of the Convention were already standard practice in Switzerland. In the last years, all Swiss nuclear power plants (NPPs) as well as the Swiss Federal Nuclear Safety Inspectorate (HSK) built up documented quality management systems. The independence of HSK from licensing authorities is fulfilled on a technical level. In 2005, a new Nuclear Energy Act came into force requiring formal independence of the supervisory authorities from the licensing authorities. A separate act to legally settle the Inspectorate's fully independent status was adopted by Parliament. HSK participates in international co-operation and is represented in numerous nuclear safety working groups in order to ensure the exchange of scientific, technical and regulatory know-how. The regulatory processes applied to the licensing and safety surveillance of nuclear installations and their operation are up to date with the current state of science and technology. Deterministic and probabilistic safety evaluations guide and prioritise inspections and provide the basis for a graded approach to safety review and assessment. The surveillance of the NPPs' operating, control and safety systems, their component performance and integrity, their organisational and human aspects as well as the management, conditioning and interim storage of radioactive waste are permanent features of the supervisory authority's activities. Within the frame of a new integrated oversight process there is an annual systematic assessment of nuclear safety

Convention on nuclear safety. Rules of procedure and financial rules

International Nuclear Information System (INIS)

1998-01-01

The document presents the Rules of Procedure and Financial Rules that apply mutatis mutandis to any meeting of the Contracting Parties to the Convention on Nuclear Safety (INFCIRC/449) convened in accordance with Chapter 3 of the Convention. It includes four parts: General provisions, Preparatory process for review meetings, Review meetings, and Amendment and interpretation of rules

Convention on Nuclear Safety. Second National Report, October 2001

International Nuclear Information System (INIS)

2001-01-01

The present document is the second Spanish national report prepared in order to comply with the obligations deriving from the convention on Nuclear Safety, made in Vienna on 20th September 1994. This convention was signed by Spain on 15th October 1994 and ratified by way of an instrument issued by the Ministry of Foreign Affairs, signed by H. M. the King on 19th June 1995. The convention, which entered into force on 24th October 1996, following ratification by a minimum number of countries, as set out in articles 20, 21 and 22 includes 51 countries and Euratom, in addition to Spain. The first review meeting, organised in accordance with chapter 3 of the Convention, was held in vienna in April 1999. Spain was represented by the CSN, the State organisation solely responsible for nuclear safety, both for the drawing up of the national report and for participation in the meeting held between the parties. In accordance with article 21, the second review meeting has been scheduled for April 2002, also in Vienna. At the review meeting, the countries party to the Convention review the national reports required by article 5, Spain submitted its first national report in September 1998. The present document is an update of that first report, and is to be submitted by 15th October 2001, as agreed on during the first review meeting. This report will be reviewed by the interested countries, which will forward their comments and questions. In April 2002, the Spanish report and the questions received will be subjected to the review process contemplated by the convention, along with the reports submitted by the other countries

Analysis of the Convention on Nuclear Safety and Suggestions for Improvement

International Nuclear Information System (INIS)

Choi, K. S.; Viet, Phuong Nguyen

2013-01-01

The innovative approach of the Convention, which is based on incentive after than legal binding, had been considered successful in strengthening the nuclear safety worldwide. However, the nuclear accident at the Fukushima Dai-ichi Nuclear Power Plant (Japan) in March 2011 has exposed a number of weaknesses of the Convention. Given that context, this paper will analyse the characteristics of the CNS in order to understand the advantages and disadvantages of the Convention, and finally to suggest some possible improvements. The analysis in this paper shows that the incentive approach of the CNS has succeeded in facilitating the active roles of its Contracting Parties in making the National Reports and participating in the peer review of these reports. However, the incoherent quality of the National Reports, the different level of participation in the peer review process by different Contracting Parties, and the lack of transparency of the peer review have undermined the effectiveness of the Convention in strengthening the international safety regime as well as preventing serious regulatory errors that had happened in Japan before the Fukushima accident. Therefore, the peer review process should be reformed into a more transparent and independent direction, while an advisory group of regulators within the CNS might also be useful in improving the effectiveness of the Convention as already proven by the good practice in the European Union. Only with such effective change, the CNS can maintain its pivotal role in the international safety regime

Animal Product Safety Information

Science.gov (United States)

... Home Animal & Veterinary Safety & Health Product Safety Information Product Safety Information Share Tweet Linkedin Pin it More ... to report adverse experiences with veterinary drugs. Additional Product Information Questions and Answers: Evanger’s Dog and Cat ...

Stakeholder involvement in international conventions governing civil nuclear activities

International Nuclear Information System (INIS)

Emmerechts, Sam

2017-01-01

Mr Emmerechts explained that international conventions have varying positions on stakeholders and their involvement depending upon the intent of the legislator and the field they cover, ranging from a narrow to a broad interpretation. He addressed stakeholder involvement in two other international conventions governing civil nuclear activities, namely the Convention on Nuclear Safety, and the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention), both concluded under the auspices of the International Atomic Energy Agency (IAEA). He noted that the Convention on Nuclear Safety remains a 'traditional' international legal instrument, focusing on governments and governmental bodies as the main stakeholders and limiting obligations regarding the involvement of the public and intergovernmental organisations to their receiving information and observing. Likewise, the Joint Convention limits obligations regarding public involvement to access to information, notably as to the siting of proposed facilities. However, he noted that in the European Union, the Directive on Nuclear Safety (2014/87/Euratom) and the Directive for the Safe Management of Spent Fuel and Radioactive Waste (2011/70/Euratom) have more advanced public participation requirements in nuclear decision making. Mr Emmerechts explained that the substantial differences between nuclear legislation and the Aarhus and Espoo Conventions with regards to public involvement requirements could partly be explained by the technicality of nuclear information and by issues related to nuclear security

France - Convention on Nuclear Safety. Fourth National Report Issued for the 2008 Peer Review Meeting

International Nuclear Information System (INIS)

2007-01-01

The Convention on Nuclear Safety, hereinafter referred to as 'the Convention', is one of the results of international discussions initiated in 1992 with the aim of proposing binding international obligations regarding nuclear safety. France signed the Convention on 20 September 1994, the date on which it was opened for signature during the IAEA's General Conference, and approved it on 13 September 1995. The Convention entered into force on 24 October 1996. For many years France has been participating actively in international initiatives to enhance nuclear safety, and it considers the Convention on Nuclear Safety to be an important instrument for achieving this aim. The areas covered by the Convention have long been part of the French approach to nuclear safety. This report, the fourth of its kind, is issued in compliance with Article 5 of the Convention on Nuclear Safety and presents the measures taken by France to fulfil each of the obligations of the Convention. As such, the Convention on Nuclear Safety applies to nuclear power reactors, and so most of this report deals with measures taken to ensure their safety. However, in this fourth report, as in the third, France has decided to include the measures taken concerning all research reactors, with a graded approach tailored to their size where appropriate. First of all, research reactors are subject to the same general regulations as nuclear power reactors with regard to nuclear safety and radiation protection. Furthermore, the most powerful research reactor also generates electricity. Secondly, in the reports under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, to which France is a party, the measures taken for research reactors in these areas have been described. Finally, in March 2004 the IAEA Board of Governors, on which France has a seat, approved the Code of Conduct on the Safety of Research Reactors, which incorporates most of the

France - convention on nuclear safety. Fifth national report for the 2011 peer review meeting

International Nuclear Information System (INIS)

2010-01-01

The Convention on Nuclear Safety, hereinafter referred to as 'the Convention', is one of the results of international discussions initiated in 1992 in order to contribute maintaining a high level of nuclear safety worldwide. The convention aims to propose binding international obligations regarding nuclear safety. France signed the Convention on 20 September 1994, the date on which it was opened for signature during the IAEA's General Conference, and approved it on 13 September 1995. The Convention entered into force on 24 October 1996. For many years France has been participating actively in international initiatives to enhance nuclear safety, and it considers the Convention on Nuclear Safety to be an important instrument for achieving this aim. The areas covered by the Convention have long been part of the French approach to nuclear safety. The purpose of this fifth report, which was drafted pursuant to Article 5 of the Convention on Nuclear Safety, is to present the measures taken by France in order to fulfil each of her obligations as specified in the said Convention. Since the Convention applies to all nuclear-power generating reactors, most of this report is dedicated to the measures taken in order to ensure their safety. However, as in previous reports, France has decided to present also in this fifth report, the measures that were taken for all research reactors, together with a graduated approach, if need be, for taking their size into account. First of all, research reactors are actually submitted to the same overall regulations as nuclear-power reactors with regard to safety and radiation protection. It should be noted that the most powerful French research reactor, called Phenix, which also used to produce electricity, was disconnected from the grid in March 2009, but continued to run an 'ultimate-test programme' until 1 February 2010. Later, in the framework of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive

Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Second national report on implementation by France of its obligations under the convention

International Nuclear Information System (INIS)

2005-09-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions which took place following adoption of the Convention on Nuclear Safety in 1994. France signed the Joint Convention on 29 September 1997, the first day on which it was opened for signature, during the General Conference of the International Atomic Energy Agency (IAEA). France approved it on 22 February 2000 and deposited the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in international action to reinforce nuclear safety and it considers the Joint Convention to be a key step in this direction. The fields it covers have for a long time been part of the French approach to nuclear safety. This report, which is the second of its kind, is published in accordance with article 32 of the Joint Convention and presents the measures taken by France to meet each of the obligations set out in the Convention. The facilities and radioactive materials which are the subject of this Convention are of widely differing types and in France are covered by different regulatory authorities, as explained in section E of this report. Above a certain radioactive content threshold, a facility is referred to as a 'basic nuclear installation' (BNI) and is placed under the authority of the Nuclear Safety Authority. This category includes in particular all facilities receiving spent fuel (reactors, reprocessing plants, storage facilities, etc.), most of the facilities whose 'main purpose is management of radioactive waste' as defined by this Convention, and a large number of facilities containing radioactive waste, even if management of the waste is not their primary objective: the total number of all types of BNIs is about 125 facilities. Below this threshold, an

Implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Stewart, L.; Tonkay, D.

2004-01-01

This paper discusses the implementation of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The Joint Convention: establishes a commitment with respect to safe management of spent nuclear fuel and radioactive waste; requires the Parties to ''take appropriate steps'' to ensure the safety of their spent fuel and waste management activities, but does not delineate standards the Parties must meet; and seeks to attain, through its Contracting Parties, a higher level of safety with respect to management of their spent nuclear fuel, disused sealed sources, and radioactive waste

National report of Brazil on nuclear safety convention - introduction

International Nuclear Information System (INIS)

1998-01-01

This document was prepared for fulfilling the Brazilian obligations under the Convention on Nuclear Safety. Chapter 1 presents some historical aspects of the Brazilian nuclear policy, targets to be attained for increasing the nuclear energy contribution for the national production of electric energy

47 CFR 80.305 - Watch requirements of the Communications Act and the Safety Convention.

Science.gov (United States)

2010-10-01

... and the Safety Convention. 80.305 Section 80.305 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES STATIONS IN THE MARITIME SERVICES Safety Watch Requirements and Procedures Ship Station Safety Watches § 80.305 Watch requirements of the Communications Act and the Safety...

The impact of the future Nuclear Safety Convention on the Spanish licensing system

International Nuclear Information System (INIS)

Ripol Carulla, S.

1995-01-01

The adoption of the 1994 Nuclear Safety Convention should not affect Spanish law. Nevertheless, the coming into force of the Nuclear Safety Convention in Spain will represent an opportunity for Spanish nuclear authorities to clarify one of the aspects of the Spanish nuclear legislation that has become oldfashioned. It would be important to adopt a general rule on nuclear safety which, at the highest level, would clearly establish the prerequisites which have to be fulfilled in order to get a licence as well as the competences of the supervision authorities, including the (criminal and) administrative penalties that can be imposed. (orig./HP)

Implementation of the obligations of the joint Convention on the safety of spent fuel management and on the safety of radioactive waste management - Sixth national report of Switzerland in accordance with article 32 of the Convention

International Nuclear Information System (INIS)

2017-10-01

This comprehensive, illustrated Sixth Swiss National Report in accordance with Article 32 of the Convention on Nuclear Safety reports on Swiss policies and practices with respect to the management of various categories of radioactive waste. The scope of application is looked at. This includes reprocessing and the processing of naturally occurring radioactive materials. Further sections of the report present notes on inventories and lists, along with a review of legislative and regulatory systems. Other general safety provisions discussed include the responsibility of licence holders, human and financial resources, quality assurance, operational radiation protection, emergency preparedness and decommissioning. Safety aspects of spent fuel management and the design, location and operation of disposal facilities are discussed. General efforts to improve safety are looked at, as is the global transport of wastes. An annex provides information on national laws, regulations and associated guidelines

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. National Report from Norway

International Nuclear Information System (INIS)

2006-05-01

This report is the Norwegian report to the second review meeting to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. The comments, questions and remarks given to Norway's initial national report and Norway's presentation given at the first review meeting have been incorporated in this report. The second report is a full revision of the first report. This report concludes that Norway meets the obligations of the Joint Convention. However, Norwegian authorities will aim for development in the waste management policy and Norway will continue to improve its existing systems to further enhance safety, in line with the aims of the Joint Convention

National report of the Slovak Republic. Compiled in terms of the convention on nuclear safety. May 2007

International Nuclear Information System (INIS)

Balaj, J.; Konecny, L.; Rovny, J.; Metke, E.; Zemanova, D.; Turner, M.; Pospisil, M.; Jurina, V.; Rivny, I.; Soltes, L.; Petrik, T.; Petrovic, J.; Fazekasova, H.; Kobzova, D.; Trcka, T.; Maudry, J.; Betak, A.; Capkovic, J.

2007-05-01

A brief national safety report of the Slovak Republic compiled in terms of the joint convention on nuclear safety in 2007 is presented. This safety report consists of following chapters: (1) Introduction; (2) Nuclear installations in the Slovak Republic in terms of the Convention; (C) Scope of application; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; (6) Annexes

Treatment of Passive Component Reliability in Risk-Informed Safety Margin Characterization FY 2010 Report

Energy Technology Data Exchange (ETDEWEB)

Robert W Youngblood

2010-09-01

The Risk-Informed Safety Margin Characterization (RISMC) pathway is a set of activities defined under the U.S. Department of Energy (DOE) Light Water Reactor Sustainability Program. The overarching objective of RISMC is to support plant life-extension decision-making by providing a state-of-knowledge characterization of safety margins in key systems, structures, and components (SSCs). A technical challenge at the core of this effort is to establish the conceptual and technical feasibility of analyzing safety margin in a risk-informed way, which, unlike conventionally defined deterministic margin analysis, is founded on probabilistic characterizations of SSC performance.

Announcement of the Ministry of Foreign Affairs of the Slovak Republic. Convention on nuclear safety

International Nuclear Information System (INIS)

1997-01-01

Ministry of Foreign Affairs of the Slovak Republic has been announcemented that from September 20, 1994 up to acquirement of its validity was opened in Vienna for signature Convention on nuclear safety. Instead of Slovak Republic the convention September 20, 1994 was signed. National Council of the Slovak Republic with the convention expressed the consent by its resolution No. 75 from January 25, 1995 and the president of the Slovak Republic February 23, 1995 its ratified. Ratification document at the depository of this convention was deposited, the director general of the International Agency for Atomic Energy, March 7, 1995. The validity of the Convention October 24, 1996, on the article section 1, was acquired. The text of the Convention on nuclear safety continued [sk

Sweden's third national report under the the Convention on Nuclear Safety. Swedish implementation of the obligations of the Convention

International Nuclear Information System (INIS)

2004-01-01

The national reports to the review meetings according to Article 5 of the Convention call for a self-assessment of each Contracting Party with regard to compliance with the obligations of the Convention. For Sweden this self-assessment has demonstrated full compliance with all the obligations of the Convention, as shown in detail in part B of this national report. There is an open and constructive dialogue between the regulatory bodies and the licensees. The owner companies are well established with good corporate financial records. They demonstrate a commitment to maintain a high level of safety in their nuclear power plants. Not withstanding the increased competition, the licensees continue to co-operate in solving important safety issues. The regulators in Sweden are assessed as well qualified for their tasks and their resources have been maintained. The international co-operation networks of both regulators and utilities are well developed. From the safety and environmental impact point of view, the Swedish nuclear power plants are competitive internationally. However, Sweden would like to point out the following issues, where further development should be given special attention in relation to the obligations under the Convention: The compatibility of the Act on Nuclear Activities with the Environmental Code needs to be followed up in order to assure that the licensing process is fully consistent. The future supply of radiation protection specialists needs to be further investigated and measures may need to be taken, as has been done to ensure the supply or nuclear safety specialists. The ongoing concentration of vendors and service companies needs to be assessed, from the safety and availability point of view, and the licensees may need to implement their own joint solutions if the market can not supply the necessary services at acceptable conditions. The operating organisations need to assess their consolidation after several organisational changes following

The evolution and future direction of the Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management

International Nuclear Information System (INIS)

Siraky, Gabriela

2008-01-01

Full text: The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, namely the Joint Convention, had been established in 1997. The objective of the Convention is to achieve and maintain a high level of safety worldwide in that fields to ensure that there are effective defenses against potential hazards so that individuals, society and the environment are protected from the harmful effects of ionizing radiation and to prevent accidents with radiological consequences and to mitigate their consequences. The Parties to the Convention intend to achieve this objective by international cooperation, peer reviews of each other's performance, assistance when needed for states with less developed programmes and capabilities and the use of internationally accepted standards of safety. The Joint Convention is rooted in the discussions held previously to the establishment of the Convention of the Nuclear Safety that had taken place in the period 1993-1994. The idea of a Convention on the Safety of waste management evolved since then, getting its final status in November 1997 after seven meetings of a specially appointed working group of outstanding specialists on the subject. After that, it was needed three years more until the number of the ratifying States, that then became Contracting Parties, to get the condition that let the Convention to enter into force: ninety days after the date of deposit with the Depository of the twenty-fifth instrument of ratification, acceptance or approval, including the instruments of fifteen States having an operational nuclear power plant. The First Review Meeting was held three years after it entered into force, in November 2003, with the attendance of 33 Parties that presented their National Reports. The second review meeting was held in May 2006. Forty-one Contracting Parties participated in the Second Review Meeting. There is then, a constant evolution in the number of Contracting Parties

Effects and practices on nuclear safety convention promoting nuclear safety in China

International Nuclear Information System (INIS)

Zhang Wei; Cheng Jianxiu; Chen Maosong

2010-01-01

By the means of peer review and self-review, the Contracting Parties are reviewed on obligations under the Convention. In order to implementation these, the State Department established the specific group, under the efforts of departments together, the China fulfilled the obligations successfully. The international society affirmed the good practices on nuclear safety in China, at the same time, they pointed out some fields that China pay close attention to. On the basis of analyzing questions, we point out some aspects which are combined the common questions put forward by the International Atomic Energy Agency on the 4th reviewing meeting that the Chinese government pay close attention to on the next review meeting. Meanwhile, we also put forward some suggestions on how to do better on fulfilling the convention. (authors)

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management. National Report of the Kingdom of the Netherlands

International Nuclear Information System (INIS)

2005-10-01

On 10 March 1999, the Netherlands signed the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, which was subsequently formally ratified on 26 April 2000 and entered into force on 18 June 2001. The Joint Convention obliges each contracting party to apply widely recognized principles and tools in order to achieve and maintain high standards of safety during management of spent fuel and radioactive waste. The Joint Convention also requires each party to report on the national implementation of these principles to review meetings of the parties to this Convention. This report describes the manner in which the Netherlands is fulfilling its obligations under the Joint Convention

Introduction to the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management and Canada's participation

International Nuclear Information System (INIS)

Mecke, J.L.

2011-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) is the first and the only legally binding international instrument to address safety issues concerning the management of spent fuel and radioactive waste on a global scale. It entered into force on June 18, 2001. The Government of Canada strongly supported international efforts to bring into force the Joint Convention and was the second country to ratify it. The Joint Convention is an 'incentive instrument' that is based on peer review (similar in that respect to the Convention on Nuclear Safety) and devised to encourage countries that are Contracting Parties to report and to foster open and frank discussions on the safety of spent fuel and radioactive waste management. Being an incentive convention, it is not designed to mandate Contracting Parties to fulfill its obligation through control and sanction, but it is based on the common objectives of Contracting Parties to achieve and maintain a high level of safety in spent fuel and radioactive waste management, protect individuals, society and the environment from ionizing radiation and prevent accidents and if necessary mitigating the consequences of such accidents. The following paper will provide an introduction to the Joint Convention and provide a summary of Canada's peer review at the most recent Review Meeting which was held on May 11-20, 2009, at the International Atomic Energy Agency (IAEA) headquarters in Vienna, Austria. (author)

Safety campaigns. TIS Launches New Safety Information Campaign

CERN Multimedia

2001-01-01

Need to start a new installation and worried about safety aspects? Or are you newly responsible for safety matters in a CERN building? Perhaps you're simply interested in how to make the working environment safer for yourself and your colleagues. Whatever the case, a new information campaign launched by TIS this week can help. The most visible aspects of the new campaign will be posters distributed around the Laboratory treating a different subject each month. The Web site - http://safety.cern.ch/ - which provides all safety related information. But these are not the only aspects of the new campaign. Members of the TIS/GS group, whose contact details can be found on the safety web site, are available to give information and advice on a one-to-one basis at any time. The campaign's launch has been timed to coincide with European Safety Week, organized by the European Agency for Safety and Health at Work and the subject treated in the first posters is safety inspection. This particular topic only concerns thos...

France - Convention on nuclear safety. Fourth national report established in view of the 2008 examination meeting

International Nuclear Information System (INIS)

2007-07-01

This report is the fourth one established in compliance with the article 5 of the international Convention on nuclear safety, and presents measures implemented by France to meet each of the Convention requirements. It addresses electro-nuclear reactors as well as research reactors. After an overview of the main evolutions since the third French report, and a general presentation of the French national nuclear policy, the report addresses the different articles of the Convention. These articles deal with general arrangements (application arrangements, presentation of reports, existing nuclear installations with their safety assessments and main safety improvements brought to the different nuclear reactors), law and regulation (legal and regulatory framework, regulation bodies, responsibility of an authorization holder), general safety considerations (priority for safety, human and financial resources, human factors, quality insurance, safety assessment and verification, radiation protection, organisation in case of emergency), and installation safety (site selection, design and construction, exploitation, activities planned to improve safety). Appendices propose a list and locations of French nuclear reactors, a list of the main legal and regulatory texts, presentations of nuclear reactor operators (EDF, CEA, ILL), and an overview of practices of control of the environment

NIF conventional facilities construction health and safety plan

International Nuclear Information System (INIS)

Benjamin, D W

1998-01-01

The purpose of this Plan is to outline the minimum health and safety requirements to which all participating Lawrence Livermore National Laboratory (LLNL) and non-LLNL employees (excluding National Ignition Facility [NIF] specific contractors and subcontractors covered under the construction subcontract packages (e.g., CSP-9)-see Construction Safety Program for the National Ignition Facility [CSP] Section I.B. ''NIF Construction Contractors and Subcontractors'' for specifics) shall adhere to for preventing job-related injuries and illnesses during Conventional Facilities construction activities at the NIF Project. For the purpose of this Plan, the term ''LLNL and non-LLNL employees'' includes LLNL employees, LLNL Plant Operations staff and their contractors, supplemental labor, contract labor, labor-only contractors, vendors, DOE representatives, personnel matrixed/assigned from other National Laboratories, participating guests, and others such as visitors, students, consultants etc., performing on-site work or services in support of the NIF Project. Based upon an activity level determination explained in Section 1.2.18, in this document, these organizations or individuals may be required by site management to prepare their own NIF site-specific safety plan. LLNL employees will normally not be expected to prepare a site-specific safety plan. This Plan also outlines job-specific exposures and construction site safety activities with which LLNL and non-LLNL employees shall comply

Sweden's fourth national report under the Convention on Nuclear Safety. Swedish implementation of the obligations of the Convention

International Nuclear Information System (INIS)

2007-01-01

The national reports to the review meetings according to Article 5 of the Convention call for a self-assessment of each Contracting Party with regard to compliance with the obligations of the Convention. For Sweden this self-assessment has demonstrated compliance with all the obligations of the Convention, as shown in part B of this national report. The Swedish existing nuclear power programme is currently under strong development since a few years. Large amounts are being invested in the 10 remaining operating reactors to prepare for long term operation. The licensees as well as the regulatory bodies have also been challenged over the last years by events, especially the Forsmark event in July 2006, demonstrating the importance of having strong safety management in place and maintaining of a vital safety culture. Of particular importance is not only to develop good formal management systems, but also to monitor and follow up how the systems function in the daily work at the plants. The need for this attention is reinforced by the major programmes going on during a limited time period to upgrade and uprate the plants. These programmes will require a full effort of the operating organisations as well as of the regulatory bodies. An additional challenge is, during the same time period, to manage the transfer of knowledge to a new generation of engineers and specialists. A large number of key staff is due to retire within the next 10 years. The generally positive impression reported to earlier review meetings under the Convention still stands. Therefore, Sweden would like to point out the following as strong features in its national nuclear practice: The Swedish legal framework is well developed and the responsibility for safety is very well defined. The nuclear law also provides for public insight into the activities of the licensees. The regulatory bodies have maintained and increased their resources and are further developing their regulatory practices. There is an

Safety Information System Guide

International Nuclear Information System (INIS)

Bullock, M.G.

1977-03-01

This Guide provides guidelines for the design and evaluation of a working safety information system. For the relatively few safety professionals who have already adopted computer-based programs, this Guide may aid them in the evaluation of their present system. To those who intend to develop an information system, it will, hopefully, inspire new thinking and encourage steps towards systems safety management. For the line manager who is working where the action is, this Guide may provide insight on the importance of accident facts as a tool for moving ideas up the communication ladder where they will be heard and acted upon; where what he has to say will influence beneficial changes among those who plan and control his operations. In the design of a safety information system, it is suggested that the safety manager make friends with a computer expert or someone on the management team who has some feeling for, and understanding of, the art of information storage and retrieval as a new and better means for communication

Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management

International Nuclear Information System (INIS)

2011-11-01

This report contains the national report from Norway to the fourth review meeting of the JointConvention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14-23 May 2012. (Author)

Flu Vaccine Safety Information

Science.gov (United States)

... Influenza Types Seasonal Avian Swine Variant Pandemic Other Flu Vaccine Safety Information Questions & Answers Language: English (US) ... safety of flu vaccines monitored? Egg Allergy Are flu vaccines safe? Flu vaccines have good safety record. ...

Implementation of the obligations of the convention on nuclear safety. Fifth Swiss report in accordance with Article 5

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-15

Switzerland signed the Convention on Nuclear Safety (CNS). In accordance with Article 5 of CNS, Switzerland has submitted 4 country reports for Review Meetings of Contracting Parties. This 5{sup th} report by the Swiss Federal Nuclear Safety Inspectorate (ENSI) provides an update on compliance with CNS obligations. The report attempts to give appropriate consideration to issues that aroused particular interest at the 4{sup th} Review Meeting. It starts with general political information on Switzerland, a brief history of nuclear power and an overview of Swiss nuclear facilities. This is followed by a comprehensive overview of the status of nuclear safety in Switzerland (as of July 2010) which indicates how Switzerland complies with the key obligations of the Convention. ENSI updated a substantial proportion of its guidelines which are harmonised with the safety requirements of the Western European Nuclear Regulators Association (WENRA) based on IAEA Safety Standards. On 1{sup st} January 2009, ENSI became formally independent of the Swiss Federal Office of Energy. It is now a stand-alone organisation controlled by its own management board. Switzerland recently started a process to select a site for the disposal of radioactive waste in deep geological formations. The first generation of NPPs in Switzerland has been the subject of progressive back-fitting. The second generation of NPPs incorporated various safety and operating improvements in their initial design. All Swiss NPPs have undergone the safety review process required under the Convention and have incorporated the improvements identified in the respective safety review reports. The Swiss policy of continuous improvements to NPPs ensures a high level of safety. The legislation and regulatory framework for nuclear installations is well established. It provides the formal basis for the supervision and the continuous improvement of nuclear installations. The Nuclear Energy Act and its ordinance came into force

Implementation of the obligations of the convention on nuclear safety. Fifth Swiss report in accordance with Article 5

International Nuclear Information System (INIS)

2010-07-01

Switzerland signed the Convention on Nuclear Safety (CNS). In accordance with Article 5 of CNS, Switzerland has submitted 4 country reports for Review Meetings of Contracting Parties. This 5 th report by the Swiss Federal Nuclear Safety Inspectorate (ENSI) provides an update on compliance with CNS obligations. The report attempts to give appropriate consideration to issues that aroused particular interest at the 4 th Review Meeting. It starts with general political information on Switzerland, a brief history of nuclear power and an overview of Swiss nuclear facilities. This is followed by a comprehensive overview of the status of nuclear safety in Switzerland (as of July 2010) which indicates how Switzerland complies with the key obligations of the Convention. ENSI updated a substantial proportion of its guidelines which are harmonised with the safety requirements of the Western European Nuclear Regulators Association (WENRA) based on IAEA Safety Standards. On 1 st January 2009, ENSI became formally independent of the Swiss Federal Office of Energy. It is now a stand-alone organisation controlled by its own management board. Switzerland recently started a process to select a site for the disposal of radioactive waste in deep geological formations. The first generation of NPPs in Switzerland has been the subject of progressive back-fitting. The second generation of NPPs incorporated various safety and operating improvements in their initial design. All Swiss NPPs have undergone the safety review process required under the Convention and have incorporated the improvements identified in the respective safety review reports. The Swiss policy of continuous improvements to NPPs ensures a high level of safety. The legislation and regulatory framework for nuclear installations is well established. It provides the formal basis for the supervision and the continuous improvement of nuclear installations. The Nuclear Energy Act and its ordinance came into force in 2005

Second national report of Brazil for the nuclear safety convention - introduction

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

This document was prepared for fulfilling the Brazilian obligations under the Convention on Nuclear Safety. Chapter 1 presents some historical aspects of the Brazilian nuclear policy, targets to be attained for increasing the nuclear energy contribution for the national production of electric energy.

Second national report of Brazil for the nuclear safety convention - introduction

International Nuclear Information System (INIS)

2001-01-01

This document was prepared for fulfilling the Brazilian obligations under the Convention on Nuclear Safety. Chapter 1 presents some historical aspects of the Brazilian nuclear policy, targets to be attained for increasing the nuclear energy contribution for the national production of electric energy

The Commodity Form of Safety Information

Directory of Open Access Journals (Sweden)

Rodrigo Finkelstein

2015-10-01

Full Text Available The production of safety information is deemed a vital resource to protect human lives at the work site. The injury rate, lost days, incapacity rate, and fatality rate, are key indicators to prop up labour risk awareness and identify job hazards. However, safety information gets highly distorted because it does not only measure risk but serves as a means of exchange. It determines the amount of money to be swapped between Workers’ Compensation Boards and their client corporations. Moreover, as a depository of exchange value, safety information tends to exert pressure over social reality rather than just being a passive reflection of it. This paper discloses the commodity form of safety information. Based on a political economy of information framework, it identifies, describes, and analyses the safety information commodity in its active role of organizing safety and labour health.

Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Third review meeting. Questions asked to France and answers

International Nuclear Information System (INIS)

2009-01-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. For his third report, France presented a document reflecting the viewpoints of the various stakeholders (regulatory authorities and operators). Thus, for each of the chapters in which the regulatory authority is not the only party to express its point of view, a three-stage structure was adopted: first of all a description by the regulatory authority of the regulations, followed by a presentation by the operators of the steps taken to meet the regulations and finally, an analysis by the regulatory authority of the steps taken by the operators. This third report was distributed in October 2008 to all Contracting Parties who asked 213 questions on the French report. France answered each of them in the present document

A proposal for an international convention on radiation safety

International Nuclear Information System (INIS)

Ahmed, J.U.

1998-01-01

One century has passed since harmful effects of radiation on living tissues were recognized. Organized efforts to reduce radiation hazards began in early 1920s. Major efforts by the ICRP since 1928, aided by ICRU, greatly helped in formulating principles, policies and guidance for radiation protection. The WHO formally recognized ICRP in 1956 and began implementing ICRP recommendations and guidance throughout the world. The IAEA, after it took office in 1957, began to establish or adopt standards of safety based on ICRP recommendations and provide for application of these standards in the field of atomic energy. Later on, other pertinent international organizations joined IAEA in establishing the Basic Safety Standards on radiation safety. The IAEA has issued, until now, nearly couple of hundred safety related documents on radiation safety and waste management. However, in spite of all such international efforts for three quarter of a century, there has been no effective universal control in radiation safety. Problems exist at the user, national, international and manufacturers and suppliers levels. Other problems are management of spent sources and smuggling of sources across international borders. Although, radiation and radionuclides are used by all countries of the world, regulatory and technical control measures in many countries are either lacking or inadequate. The recommendations and technical guidance provided by the international organizations are only advisory and carry no mandatory force to oblige countries to apply them. Member States approve IAEA safety standards and guides at the technical meetings and General Conference, but many of them do not apply these. An International Convention is, therefore, essential to establish international instrument to ensure universal application of radiation safety. (author)

High committee for nuclear safety transparency and information. March 17, 2009 meeting

International Nuclear Information System (INIS)

2009-03-01

The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 9 main topics: 1 - presentation by the French nuclear safety authority (ASN) of a dismantling strategy for nuclear facilities, in particular taking into account a final state for the site and the information of populations; 2 - status of the next campaign of iodine tablets distribution; 3 - the management of ancient uranium mines and in particular the long-term environmental and health impact of mine tailings; 4 - the implementation of the high committee's recommendations; 5 - work progress of the working group on information transparency; 6 - Areva's invitation of the working group on information transparency to assist to the organisation of a Mox fuel convoy between Cherbourg and Japan; 7 - progress of the working group on the elaboration of a 'communication scale' comparable to the INES scale; 8 - presentation of the meetings organized by the ANCLI (French national association of local information commissions) about the implementation of the Aarhus convention; 9 - presentation by the IRSN (Institute of radiation protection and nuclear safety) of its communication approach towards the public. (J.S.)

Differences in safety margins between nuclear and conventional design standards with regards to seismic hazard definition and design criteria

International Nuclear Information System (INIS)

Elgohary, M.; Saudy, A.; Orbovic, N.; Dejan, D.

2006-01-01

With the surging interest in new build nuclear all over the world and a permanent interest in earthquake resistance of nuclear plants, there is a need to quantify the safety margins in nuclear buildings design in comparison to conventional buildings in order to increase the public confidence in the safety of nuclear power plants. Nuclear (CAN3-N289 series) and conventional (NBCC 2005) seismic standards have different approaches regarding the design of civil structures. The origin of the differences lays in the safety philosophy behind the seismic nuclear and conventional standards. Conventional seismic codes contain the minimal requirement destined primarily to safeguard against major structural failure and loss of life. It doesn't limit damage to a certain acceptable degree or maintain function. Nuclear seismic code requires that structures, systems and components important to safety, withstand the effects of earthquakes. The requirement states that for equipment important to safety, both integrity and functionality should be ascertained. The seismic hazard is generally defined on the basis of the annual probability of exceedence (return period). There is a major difference on the return period and the confidence level for design earthquakes between the conventional and the nuclear seismic standards. The seismic design criteria of conventional structures are based on the use of Force Modification Factors to take into account the energy dissipation by incursion in non-elastic domain and the reserve of strength. The use of such factors to lower intentionally the seismic input is consistent with the safety philosophy of the conventional seismic standard which is the 'non collapse' rather than the integrity and/or the operability of the structures or components. Nuclear seismic standard requires that the structure remain in the elastic domain; energy dissipation by incursion in non-elastic domain is not allowed for design basis earthquake conditions. This is

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security, Issue no. 10, March 2009

International Nuclear Information System (INIS)

2009-03-01

The current issue contains information about the following meetings: Application of the Code of Conduct on the Safety of Research Reactors (the 'Code'). Environmental Modelling for Radiation Safety (EMRAS II); Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention). The document also gives an overview on International Nuclear Security Advisory Service (INSServ)

Reflections on a future international convention on safety in radioactive waste management - September 1994

International Nuclear Information System (INIS)

Arias Canete, A.

1995-01-01

This probably is a suitable moment for work to begin on an international Convention in this area, although it is a difficult task. Generally speaking, the RADWASS (Radioactive Waste Safety Standards) Programme has achieved sufficient consensus, and might serve as an important basis for work in relation to the Convention. The Convention should not go into highly technical details since consensus at this level is more difficult at the present moment, although this will undoubtedly be achieved in the medium term. An important element of the Convention should be the regulation of movements of radioactive wastes at international level. (orig./HP)

Convention on Nuclear Safety. Second national report on the implementation by france of the obligations of the Convention

International Nuclear Information System (INIS)

2001-09-01

The first national report on the implementation by france of the obligation under the Convention is structured along its Articles. the french Nuclear safety Authority ensured the co ordination of the report, with contributions from other regulators and nuclear operators. this report was distributed at the middle of April 2003 to the other Contracting party (on 3 november to 14, 2003 at the IAEA headquarters. (author)

Manche storage Centre. Information report on nuclear safety and radiation protection 2015

International Nuclear Information System (INIS)

2016-01-01

After a presentation of the Manche Storage Centre (CSM), the first French center of surface storage of low- and intermediate-level radioactive wastes, of its history, its buildings and activities, of the multi-layer cover, of the water management system (installation, controls, sampling), this report then describes the measures related to nuclear safety, the management of conventional and nuclear wastes produced by the Centre, the other impacts, the control, maintenance and follow-up of installations, the radiation protection and security of the center, the incidents and accidents that occurred at the facility, and the public information and communication actions. Recommendations of the Health and safety Committee (CHSCT) are reported at the end

INFORMATION CULTURE AND INFORMATION SAFETY OF SCHOOLCHILDREN

Directory of Open Access Journals (Sweden)

E. G. Belyakova

2017-01-01

Full Text Available Introduction. The article is devoted to the problem of interaction between schoolchildren and possible informational risks transmitted on the Internet. Considering the lack of external filters on the way of harmful information streams, it is actually necessary to develop information culture of schoolchildren, their abilities to sensibly and critically interpret the information on the Internet, and choice of adequate behaviour models surfing the Web. The aim of the present research is to analyze the state of informational safety of schoolchildren while using the Internet; gaining an understanding of the role of external restrictions and opportunities of intrapersonal filtration of the harmful Internet content depending on children age. Methodology and research methods. The methodology of the research is based on modern methods aimed to consider the problem of personal socialization in modern information society. Thus, the Internet Initiatives Development Fund (IIDF questionnaire let the authors define the level of awareness of recipients on the problem under consideration. Results and scientific novelty. The theoretical analysis helped the authors predict the correlation of basic methods in order to guarantee personal safety of schoolchildren taking into account the process of maturity as well as the decrease of external filters that may stop harmful content. Empirical part of the research has enabled to reveal decrease in external control of staying of a child in network in the process of growing up against the background of restrictive attitudes prevalence among teachers and parents. Therefore, the research supposed to improve information culture of schoolchildren from the earliest ages encouraging them to sensibly and correctly interpret the information on the Internet. Practical significance. The practical recommendations to parents and teachers in order to improve informational personal safety of schoolchildren are proposed. The relevancy

Sweden's second national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2005-01-01

Article 32 of the Joint Convention calls for a self-assessment by each Contracting Party regarding compliance with the obligations of the Convention. Sweden's self-assessment has demonstrated compliance with all the obligations of the Convention, as shown in detail in sections B to K of this report. Having taken a very active part in the creation of the Joint Convention, Sweden wishes to emphasise the incentive character of the Convention. In Sweden's opinion, the Convention implies a commitment to continuous improvement of safety whenever operating experience, safety research or technical development indicates that there is room for such improvement. Continuous learning from experience and a proactive approach to safety are in fact corner stones of the current Swedish nuclear and radiation safety work, both for the industry and the regulatory bodies. Therefore, Sweden has found it important that its National Report highlights strong features in national practices, as well as areas in which improvements are justified. Implementation of such improvements should then be followed up in the National Reports to subsequent Review Meetings. The major events in the Swedish nuclear programme since the first report to the Convention was issued are: - The general safety regulations of SKI have been revised and issued as SKIFS 2004:1. - A commission of inquiry has been carried out in order to review and suggest improvements to the financing system. - The second unit of the twin nuclear power plant unit at Barsebaeck (Barsebaeck 2) was permanently shut down 31 May 2005. The first unit (Barsebaeck 1) was closed in 1999. - The research reactors R2 and R2-0 at the Studsvik site were permanently shut down 16 June 2005. - The Swedish Nuclear Fuel and Waste Management Co. (SKB) has announced its decision to take over operation of the interim storage facility for spent nuclear fuel (Clab). The operation of Clab is currently contracted out to OKG, who operates the three nuclear power

40 CFR 68.65 - Process safety information.

Science.gov (United States)

2010-07-01

... (CONTINUED) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 3 Prevention Program § 68.65 Process safety... 40 Protection of Environment 15 2010-07-01 2010-07-01 false Process safety information. 68.65... compilation of written process safety information before conducting any process hazard analysis required by...

Analysis and design on airport safety information management system

Directory of Open Access Journals (Sweden)

Yan Lin

2017-01-01

Full Text Available Airport safety information management system is the foundation of implementing safety operation, risk control, safety performance monitor, and safety management decision for the airport. The paper puts forward the architecture of airport safety information management system based on B/S model, focuses on safety information processing flow, designs the functional modules and proposes the supporting conditions for system operation. The system construction is helpful to perfecting the long effect mechanism driven by safety information, continually increasing airport safety management level and control proficiency．

The announcement of the Ministry of Foreign Affairs of the Slovak Republic about Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management

International Nuclear Information System (INIS)

2002-01-01

The Ministry of Foreign Affairs of the Slovak Republic amends that in 30 September 1997 in Vienna was undersigned the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. This Joint Convention came into force on June 18, 2001

Toward introduction of risk informed safety regulation. Nuclear Safety Commission taskforce's interim report

International Nuclear Information System (INIS)

2006-01-01

Nuclear Safety Commission's taskforce on 'Introduction of Safety Regulation Utilizing Risk Information' completed the interim report on its future subjects and directions in December 2005. Although current safety regulatory activities have been based on deterministic approach, this report shows the risk informed approach is expected to be very useful for making nuclear safety regulation and assurance activities reasonable and also for appropriate allocation of regulatory resources. For introduction of risk informed regulation, it also recommends pileups of experiences with gradual introduction and trial of the risk informed approach, improvement of plant maintenance rules and regulatory requirements utilizing risk information, and establishment of framework to assure quality of risk evaluation. (T. Tanaka)

49 CFR 211.61 - Informal safety inquiries.

Science.gov (United States)

2010-10-01

... information on selected topics relating to railroad safety. A notice of each such inquiry will be published in... 49 Transportation 4 2010-10-01 2010-10-01 false Informal safety inquiries. 211.61 Section 211.61..., DEPARTMENT OF TRANSPORTATION RULES OF PRACTICE Miscellaneous Safety-Related Proceedings and Inquiries § 211...

Radioactive wastes. Commune convention about the safety of spent fuel management and about the radioactive waste management

International Nuclear Information System (INIS)

Anon.

1997-01-01

This common convention do not give detailed safety standards but general obligations whom objective is the development of a safety culture in the world. It concerns the spent fuels (valuable and valued by the reprocessing) and radioactive wastes (matter without any later use). (N.C.)

Safety Case Development as an Information Modelling Problem

Science.gov (United States)

Lewis, Robert

This paper considers the benefits from applying information modelling as the basis for creating an electronically-based safety case. It highlights the current difficulties of developing and managing large document-based safety cases for complex systems such as those found in Air Traffic Control systems. After a review of current tools and related literature on this subject, the paper proceeds to examine the many relationships between entities that can exist within a large safety case. The paper considers the benefits to both safety case writers and readers from the future development of an ideal safety case tool that is able to exploit these information models. The paper also introduces the idea that the safety case has formal relationships between entities that directly support the safety case argument using a methodology such as GSN, and informal relationships that provide links to direct and backing evidence and to supporting information.

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)

3. French national report on implementation of the obligations of the Convention on nuclear safety - Issued for the 2005 Peer review meeting

International Nuclear Information System (INIS)

2004-01-01

The Convention on Nuclear Safety, hereinafter referred to as 'the Convention', is one of the results of international discussions initiated in 1992 with the aim of proposing binding international obligations regarding nuclear safety. France signed the Convention on 20 September 1994, on the first day it was opened for signature on the occasion of the General Conference of the IAEA. France approved the Convention on 13 September 1995 and it entered into force on 24 October 1996. For many years, France has been participating in international initiatives to enhance nuclear safety and considers the Convention on Nuclear Safety to be an important step in this direction. The areas covered by the Convention have long been part of the French approach to nuclear safety. This report, the third one of its kind, is issued in compliance with Article 5 of the Convention on Nuclear Safety and presents the measures taken by France to meet each of the obligations of the Convention. As such, the Convention on Nuclear Safety applies to nuclear power reactors and so most of this report deals with measures taken to ensure their safety. However, for this third report, a number of considerations led France also to present the measures taken concerning all research reactors, with a 'graded approach' tailored to their size where appropriate. First of all, research reactors are subject to the same general regulations as power reactors with regard to nuclear safety and radiation protection. Furthermore, the most powerful research reactor, which is also intended for producing power, was already included in the previous French report. Secondly, within the first report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management, to which France is a party, the measures taken for research reactors in these areas were already presented. Finally the IAEA Board of Governors, on which France has a seat, in March 2004 approved the Code of

State Traffic Safety Information

Data.gov (United States)

Department of Transportation — The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic...

International exchange of safety and licensing information

International Nuclear Information System (INIS)

Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

1977-01-01

A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the US Nuclear Regulatory Commission. For developing countries such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that USNRC has accumulated. USNRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the USNRC is in providing for reciprocal communication, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly discovered problem in a nuclear reactor be brought immediately to the attention of other governments that are responsible for the safety of similar reactors. Definite progress has been made in the USA in defining categories of information that USNRC can receive in confidence from foreign countries, and can protect from disclosure under the US Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of USNRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of a country building its first power reactor is described. (author)

International exchange of safety and licensing information

International Nuclear Information System (INIS)

Lafleur, J.D. Jr.; Hauber, R.D.; Chenier, D.M.

1977-01-01

A network of formal and informal bilateral arrangements for the exchange of nuclear safety information is being established by the U.S. Nuclear Regulatory Commission. For developing countries, such arrangements can provide ready access to the extensive, fully documented safety analyses and safety research results that NRC has accumulated. NRC has been receiving foreign visitors at a rate of about 500 per year, largely for discussions of safety and licensing questions related to light water reactors. Exchanges also are taking place on the safety of advanced reactors. A special interest of the NRC is in providing for reciprocal communicaion, at the earliest possible time, of important problems, decisions and other actions on nuclear safety matters. For example, it is essential that a newly-discovered problem in a nuclear reactor be brought immediately to the attention of other governments which are responsible for the safety of similar reactors. Definite progress has been made in the U.S. Freedom of Information Act. Certain exchanges have taken place on this basis. Experience in the establishment and operation of NRC's bilateral exchange arrangements is summarized. A typical exchange with the regulatory authority of country building its first power reactor is described

Auditory localisation of conventional and electric cars : laboratory results and implications for cycling safety.

NARCIS (Netherlands)

Stelling-Konczak, A. Hagenzieker, M.P. Commandeur, J.J.F. Agterberg, M.J.H. & Wee, B. van

2016-01-01

When driven at low speeds, cars operating in electric mode have been found to be quieter than conventional cars. As a result, the auditory cues which pedestrians and cyclists use to assess the presence, proximity and location oncoming traffic may be reduced, posing a safety hazard. This laboratory

Auditory localisation of conventional and electric cars: laboratory results and implications for cycling safety

NARCIS (Netherlands)

Stelling-Konczak, A.; Hagenzieker, M.P.; Commandeur, J.J.F.; Agterberg, M.J.H.; van Wee, B.

2016-01-01

When driven at low speeds, cars operating in electric mode have been found to be quieter than conventional cars. As a result, the auditory cues which pedestrians and cyclists use to assess the presence, proximity and location oncoming traffic may be reduced, posing a safety hazard. This laboratory

Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. France's answers to questions and comments received from other Contracting Parties on its second report for the JC

International Nuclear Information System (INIS)

2009-01-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. For his second report, France presented a document reflecting the viewpoints of the various stakeholders (regulatory authorities and operators). Thus, for each of the chapters in which the regulatory authority is not the only party to express its point of view, a three-stage structure was adopted: first of all a description by the regulatory authority of the regulations, followed by a presentation by the operators of the steps taken to meet the regulations and finally, an analysis by the regulatory authority of the steps taken by the operators. France received questions and comments from the other contracting parties of the joint convention and answered them in the present document

Convention on nuclear safety. Signature, ratification, acceptance, approval or accession. Status as of 17 March 1997

International Nuclear Information System (INIS)

1997-01-01

The document presents the status as of 17 March 1997 of signature, ratification, acceptance, approval or accession by Member States of the Convention on Nuclear Safety adopted on 17 June 1994 by the Diplomatic Conference convened by the IAEA at its Headquarters between 14-17 June 1994. The Convention entered into force on 24 October 1996. There are 65 signatories and 35 parties. Reservations/declarations deposited upon signature are also included

The specific tasks of RF TSO - FSUE VO 'Safety', related with Implementation of obligations under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

Potapov, V.; Kuznetsov, M.; Kapralov, E.

2010-01-01

It was more than 20 years ago that IAEA discussed the issue pertaining to the need in scientific and engineering support to the regulatory body. The Convention on Nuclear Safety being the keystone in assurance of the global nuclear safety and security regime was adopted in 1994. It is pointed out that two independent organizations supervised by Rostechnadzor have been established within the Russian TSO system, FSUE VO 'Safety' being one of them. The tasks of the organization comprise obligatory certification of equipment as well as acceptance of equipment before its delivery to the NPP both in Russia and in the countries constructing the power units based on the Russian designs. The acceptance procedure has been set forth in the new Russian document at the level of the federal rules and regulations for nuclear safety assurance. As far as its implementation decision is concerned, a task for selection and training of personnel has been set and allocated on the Training and Methodological Center of Nuclear and Radiation Safety established with the support of FSUE VO 'Safety', which provides training programmes and specific lecture courses in the wide range of the relevant topics. (author)

The incentive concept as developed in the nuclear safety conventions and its possible extension to other sectors

International Nuclear Information System (INIS)

Wright, T. de

2007-01-01

This paper seeks to analyse the incentive concept, initially adopted in the C.N.S. (convention on nuclear safety) and later developed in the Joint Convention, as the innovation credited with encouraging both participation in , and compliance with, the nuclear safety conventions. It then seeks to examine the possibilities for the introduction of that concept into other sectors of international law. In the first part of the paper, the essential features of the concept and the mechanisms used in the conventions to bring it into effect will be discussed. the second part of the paper will focus on the different aspects of the conventions which have been described as integral to the concept. The third part of the paper will identify certain apprehensions regarding the effectiveness of such 'soft' treaty provisions and explain why the ' incentive' concept may be particularly well suited to certain specific situations. The final part of the paper will address the potential application of the concept and related treaty provisions to other fields of law, particularly to international environmental law. in addition, some suggestions will be made as to how provisions implementing the incentive concept into a treaty may be slightly modified to increase their effectiveness. (N.C.)

Convention on nuclear safety 2012 extra ordinary meeting. The Swedish National Report

International Nuclear Information System (INIS)

2012-01-01

During the 5th Review Meeting of the Convention on Nuclear Safety (CNS), the Contracting Parties in attendance agreed to hold an Extraordinary Meeting in August 2012 with the aim to enhance safety through reviewing and sharing lessons learned and actions taken by Contracting Parties in response to events at TEPCO Fukushima Dai-ichi. It was agreed that a brief and concise National Report should be developed by each Contracting Party to support the Extraordinary Meeting. This report should be submitted three months prior to the meeting to the Secretariat via the Convention-secured website for peer review by other Contracting Parties. It was also agreed that the Contracting Parties should organize their reports by topics that cross the boundaries of multiple CNS Articles. Each National Report should provide specific information on these topics to address the lessons learned and activities undertaken by each Contracting Party. The National Report should include a description of the activities the Contracting Party has completed and any activities it intends to complete along with scheduled completion dates. The present report is therefore structured in accordance with the guidance given by the General Committee for CNS. In Chapter 0, a brief description of Swedish nuclear power plants is given with an emphasis on measures that have been taken gradually as a result of new knowledge and experience. The following chapters deal with the six topics, which are: 1) External events, 2) Design issues, 3) Severe accident management and recovery, 4) National organizations, 5) Emergency preparedness and response and post-accident management, and 6) International cooperation. Each chapter concludes with a table illustrating a high-level summary of the items identified. To clarify the relationship between the text and table contained in each chapter, the parts of the text appearing in the table are underlined. Furthermore, the text of some sections/subsections in different chapters

Progress toward international agreement to improve reactor safety

International Nuclear Information System (INIS)

Lieberman, J.I.; Graham, B.

1993-01-01

Representatives of nearly one-half of the 114 member states of the International Atomic Energy Agency (IAEA), including the United States, have participated in the development of an international nuclear safety conventions proposed multilateral treaty to improve civil nuclear power reactor safety. A preliminary draft of the convention has been developed (referred to as the draft convention for this report), but discussions are continuing, and when the final convention text will be completed and presented to IAEA member states for signature is uncertain. This report responds to the former and current Chairman's request that we provide information on the development of the nuclear safety convention, including a discussion of (1) the draft convention's scope and objectives, (2) how the convention will be implemented and monitored, (3) the views of selected country representatives on what provisions should be included in the draft convention, and (4) the convention's potential benefits and limitations

Waste convention regulatory impact on planning safety assessment for LILW disposal in Croatia

International Nuclear Information System (INIS)

Valcic, I.; Subasic, D.; Lokner, V.

2000-01-01

Preparations for establishment of a LILW repository in Croatia have reached a point where a preliminary safety assessment for the prospective facility is being planned. The planning is not based upon the national regulatory framework, which does not require such an assessment at this early stage, but upon the interagency BSS and the IAEA RADWASS programme recommendations because the national regulations are being revised with express purpose to conform to the most recent international standards and good practices. The Waste Convention, which Croatia has ratified in the meantime, supports this approach in principle, but does not appear to have more tangible regulatory relevance for the safety assessment planning. Its actual requirements regarding safety analyses for a repository fall short of the specific assessment concepts practiced in this decade, and could have well been met by the old Croatian regulations from the mid-eighties. (author)

The impact of health information technology on patient safety

Directory of Open Access Journals (Sweden)

Yasser K. Alotaibi

2017-12-01

Full Text Available Since the original Institute of Medicine (IOM report was published there has been an accelerated development and adoption of health information technology with varying degrees of evidence about the impact of health information technology on patient safety. This article is intended to review the current available scientific evidence on the impact of different health information technologies on improving patient safety outcomes. We conclude that health information technology improves patient’s safety by reducing medication errors, reducing adverse drug reactions, and improving compliance to practice guidelines. There should be no doubt that health information technology is an important tool for improving healthcare quality and safety. Healthcare organizations need to be selective in which technology to invest in, as literature shows that some technologies have limited evidence in improving patient safety outcomes.

The impact of health information technology on patient safety.

Science.gov (United States)

Alotaibi, Yasser K; Federico, Frank

2017-12-01

Since the original Institute of Medicine (IOM) report was published there has been an accelerated development and adoption of health information technology with varying degrees of evidence about the impact of health information technology on patient safety.  This article is intended to review the current available scientific evidence on the impact of different health information technologies on improving patient safety outcomes. We conclude that health information technology improves patient's safety by reducing medication errors, reducing adverse drug reactions, and improving compliance to practice guidelines. There should be no doubt that health information technology is an important tool for improving healthcare quality and safety. Healthcare organizations need to be selective in which technology to invest in, as literature shows that some technologies have limited evidence in improving patient safety outcomes.

National report of the Slovak Republic compiled according to the terms of the convention on nuclear safety

International Nuclear Information System (INIS)

Adamovsky, V.; Betak, A.; Balaj, J.; Bystricka, S.; Grebeciova, J.; Husarcek, J.; Metke, E.; Pospisil, M.; Smrtnik, I.; Turner, M.; Uhrik, P.; Zemanova, D.; Bulla, R.; Filip, A.; Jurina, V.; Sedlak, M.; Tomek, J.; Zimermann, M.

2013-06-01

A brief safety report of the Slovak Republic in 2013 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovak Republic in terms of the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in the Slovak Republic; ((6) Annexes; (6.1) List of nuclear installations and technical and economic indicators; (6.2) Selected generally binding legal regulations and safety guidelines in relation to nuclear and radiation safety; (6.3) List of selected national and international documents applicable to safety of nuclear installations; (6.4) Limits for radioactive discharges; (6.5) IAEA Action Plan on Nuclear Safety; (6.6) Team of authors.

40 CFR 68.48 - Safety information.

Science.gov (United States)

2010-07-01

...) CHEMICAL ACCIDENT PREVENTION PROVISIONS Program 2 Prevention Program § 68.48 Safety information. (a) The... regulated substances, processes, and equipment: (1) Material Safety Data Sheets that meet the requirements...) Equipment specifications; and (5) Codes and standards used to design, build, and operate the process. (b...

Mass-media information campaigns about road safety. [previously known as: Public information about road safety.

NARCIS (Netherlands)

2009-01-01

In the Netherlands, public information is often used as an instrument to improve road safety. The purpose of each public information campaign is a voluntary and lasting change in traffic behaviour. This requires road users to have sufficient knowledge about a problem and to adapt their behaviour.

Considerations about the impact of the Convention on Nuclear Safety on the regulatory action of the CNEN in Brazilian nuclear power plants

International Nuclear Information System (INIS)

Camargo, Claudio; Pontedeiro, Auro

1995-01-01

Preliminary discussion is conducted about the impact of the terms of the Convention on Nuclear safety, adopted by Diplomatic Conference in September 1994 in the International Atomic Energy Agency, on the regulatory action of Brazilian Nuclear Regulatory Body - CNEN. Following the Convention articles structure, the paper emphasizes technical aspects of the nuclear safety standards adopted in the licensing process of Brazilian Nuclear Power Plants. The recent experience in the issuance of Angra-1 NPP Permanent Operation Authorization is used to demonstrate that current safety standards in Brazil are in compliance with the international compromises and in agreement with what is expected by the so called Safety Culture. (author). 9 refs

Patient safety goals for the proposed Federal Health Information Technology Safety Center.

Science.gov (United States)

Sittig, Dean F; Classen, David C; Singh, Hardeep

2015-03-01

The Office of the National Coordinator for Health Information Technology is expected to oversee creation of a Health Information Technology (HIT) Safety Center. While its functions are still being defined, the center is envisioned as a public-private entity focusing on promotion of HIT related patient safety. We propose that the HIT Safety Center leverages its unique position to work with key administrative and policy stakeholders, healthcare organizations (HCOs), and HIT vendors to achieve four goals: (1) facilitate creation of a nationwide 'post-marketing' surveillance system to monitor HIT related safety events; (2) develop methods and governance structures to support investigation of major HIT related safety events; (3) create the infrastructure and methods needed to carry out random assessments of HIT related safety in complex HCOs; and (4) advocate for HIT safety with government and private entities. The convening ability of a federally supported HIT Safety Center could be critically important to our transformation to a safe and effective HIT enabled healthcare system. © The Author 2014. Published by Oxford University Press on behalf of the American Medical Informatics Association. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Aviation Safety Hotline Information System -

Data.gov (United States)

Department of Transportation — The Aviation Safety Hotline Information System (ASHIS) collects, stores, and retrieves reports submitted by pilots, mechanics, cabin crew, passengers, or the public...

A Network Diffusion Model of Food Safety Scare Behavior considering Information Transparency

Directory of Open Access Journals (Sweden)

Tingqiang Chen

2017-01-01

Full Text Available This study constructs the network diffusion model of food safety scare behavior under the effect of information transparency and examines the network topology and evolution characteristics of food safety scare behavior in a numerical simulation. The main conclusions of this study are as follows. (1 Under the effect of information transparency, the network degree distribution of food safety scare behavior diffusion demonstrates the decreasing characteristics of diminishing margins. (2 Food safety scare behavior diffusion increases with the information dissemination rate and consumer concern about food safety incidents and shows the characteristics of monotone increasing. And with the increasing of the government food safety supervision information transparency and media food safety supervision information transparency, the whole is declining characteristic of diminishing marginal. In addition, the extinction of food safety scare behavior cannot be achieved gradually given a single regulation of government food safety supervision information transparency and media food safety supervision information transparency. (3 The interaction effects between improving government food safety supervision information transparency or media food safety supervision information transparency and declining consumer concerns about food safety incidents or information transmission rate can engender the suppression of food safety scare behavior diffusion.

PSA methodology including new design, operational and safety factors, 'Level of recognition of phenomena with a presumed dominant influence upon operational safety' (failures of conventional as well as non-conventional passive components, dependent failures, influence of operator, fires and external threats, digital control, organizational factors)

International Nuclear Information System (INIS)

Jirsa, P.

2001-10-01

The document represents a specific type of discussion of existing methodologies for the creation and application of probabilistic safety assessment (PSA) in light of the EUR document summarizing requirements placed by Western European NPP operators on the future design of nuclear power plants. A partial goal of this discussion consists in mapping, from the PSA point of view, those selected design, operational and/or safety factors of future NPPs that may be entirely new or, at least, newly addressed. Therefore, the terms of reference for this stage were formulated as follows: Assess current level of knowledge and procedures in the analysis of factors and phenomena with a dominant influence upon operational safety of new generation reactors, especially in the following areas: (1) Phenomenology of failure types and mechanisms and reliability of conventional passive safety system components; (2) Phenomenology of failure types and mechanisms and reliability of non-conventional passive components of newly designed safety systems; (3) Phenomenology of types and mechanisms of dependent failures; (4) Human factor role in new generation reactors and its effect upon safety; (5) Fire safety and other external threats to new nuclear installations; (6) Reliability of the digital systems of the I and C system and their effect upon safety; and (7) Organizational factors in new nuclear installations. (P.A.)

National report of the Slovak Republic. Compiled in terms of the convention on nuclear safety. September 2004

International Nuclear Information System (INIS)

Balaj, J.; Jurina, V.; Kasana, A.

2004-09-01

A brief national safety report of the Slovak Republic in 2004 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovakia according to the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; (6) Annexes: 6.1 List of nuclear installations and technical and economic parameters; 6.2 Some generally binding legal documents concerning nuclear and radiation safety; 6.3 Limits of radioactive discharges; 6.4 Author team. Contents, list of abbreviations used as well as reference index are included

National report of the Slovak Republic. Compiled according to the terms of the convention on nuclear safety

International Nuclear Information System (INIS)

Duchac, A.; Konecny, L.; Lipar, M.; Metke, E.; Novak, S.; Rohar, S.; Turner, M.; Zemanova, D.; Zlatnansky, J.; Gies, F.; Lipar, B.; Parimucha, F.; Pospisil, P.; Tomek, J.; Toth, A.; Jurina, V.; Kmosena, M.; Marcin, S.; Silny, M.

1998-09-01

A brief safety report of the Slovak Republic in 1998 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented.These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovakia accords to the convention definition; (3) Legislation and supervision; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; ((6) Annexes; (7) Act of National Council of the Slovak Republic No. 130/1998 Coll. LL. Contents and list of abbreviations used are included

Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2014

International Nuclear Information System (INIS)

2015-01-01

Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: general considerations on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Information report on nuclear safety and radiation protection of the SOMANU site - Issue 2012

International Nuclear Information System (INIS)

2013-06-01

Published in compliance with the French code of the environment, this report first presents different aspects of the SOMANU plant which is dedicated to the maintenance of materials and equipment from nuclear installations: location and environment, history, description of activities, regulatory framework. It describes the various measures regarding nuclear safety and radiation protection: general principles of nuclear safety, organization, presentation of the Areva's nuclear safety Charter, inspections and controls, measures regarding radiation protection. The next part addresses nuclear events which occurred on this site and had to be declared. The report gives an overview of activities and measures regarding the management of releases and the control of the environment. The next part addresses waste management: generalities on radioactive waste management in France, description and classification of radioactive wastes present in the INB, management of conventional wastes. The management of other impacts is also reported. The last chapter reviews the actions undertaken in the field of transparency and information. Recommendations of the CHSCT are reported

Improving plant state information for better operational safety

International Nuclear Information System (INIS)

Girard, C.; Olivier, E.; Grimaldi, X.

1994-01-01

Nuclear Power Plant (NPP) safety is strongly dependent on components' reliability and particularly on plant state information reliability. This information, used by the plant operators in order to produce appropriate actions, have to be of a high degree of confidence, especially in accidental conditions where safety is threatened. In this perspective, FRAMATOME, EDF and CEA have started a joint research program to prospect different solutions aiming at a better reliability for critical information needed to safety operate the plant. This paper gives the main results of this program and describes the developments that have been made in order to assess reliability of different information systems used in a Nuclear Power Plant. (Author)

SACS2: Dynamic and Formal Safety Analysis Method for Complex Safety Critical System

International Nuclear Information System (INIS)

Koh, Kwang Yong; Seong, Poong Hyun

2009-01-01

Fault tree analysis (FTA) is one of the most widely used safety analysis technique in the development of safety critical systems. However, over the years, several drawbacks of the conventional FTA have become apparent. One major drawback is that conventional FTA uses only static gates and hence can not capture dynamic behaviors of the complex system precisely. Although several attempts such as dynamic fault tree (DFT), PANDORA, formal fault tree (FFT) and so on, have been made to overcome this problem, they can not still do absolute or actual time modeling because they adapt relative time concept and can capture only sequential behaviors of the system. Second drawback of conventional FTA is its lack of rigorous semantics. Because it is informal in nature, safety analysis results heavily depend on an analyst's ability and are error-prone. Finally reasoning process which is to check whether basic events really cause top events is done manually and hence very labor-intensive and timeconsuming for the complex systems. In this paper, we propose a new safety analysis method for complex safety critical system in qualitative manner. We introduce several temporal gates based on timed computational tree logic (TCTL) which can represent quantitative notion of time. Then, we translate the information of the fault trees into UPPAAL query language and the reasoning process is automatically done by UPPAAL which is the model checker for time critical system

Regulatory inspection practices for industrial safety (electrical, mechanical, material handling and conventional aspects)

International Nuclear Information System (INIS)

Agarwal, K.

2017-01-01

Regulatory Inspection (RI) of BARC facilities and projects are carried out under the guidance of BARC Safety Council (BSC) Secretariat. Basically facilities and projects have been divided into two board categories viz. radiological facilities and non-radiological facilities. The Rls of radiological facilities should be carried out under OPSRC and of non-radiological facilities under CFSRC. Periodicity of inspection shall be at least once in a year. The RI of projects is carried out under concerned DSRC. RI practices with industrial safety which includes electrical, mechanical, material handling and conventional aspect for these facilities starts with check lists. The inspection areas are prepared in the form of checklists which includes availability of approved documents, compliance status of previous RIT and various safety committee's recommendations, radiological status of facilities, prompt reporting of safety related unusual occurrences, major incident, site visit for verification of actual status of system/plant. The practices for inspection in the area of electrical safety shall include checking of maintenance procedure for all critical class IV system equipment's such as HT panel, LT panel, transformer and motors. Load testing of Class III system such as D.G. set etc. shall be carried out as technical specification surveillance schedule. Status of aviation lights, number of qualified staff, availability of qualified staff etc. shall be form of inspection

77 FR 15453 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2012-03-15

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No... information collection titled, ``Gas Pipeline Safety Program Certification and Hazardous Liquid Pipeline... collection request that PHMSA will be submitting to OMB for renewal titled, ``Gas Pipeline Safety Program...

Development of the Advanced Nuclear Safety Information Management (ANSIM) System

Energy Technology Data Exchange (ETDEWEB)

Sohn, Jae Min; Ko, Young Cheol; Song, Tai Gil [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2012-05-15

Korea has become a technically independent nuclear country and has grown into an exporter of nuclear technologies. Thus, nuclear facilities are increasing in significance at KAERI (Korea Atomic Energy Research Institute), and it is time to address the nuclear safety. The importance of nuclear safety cannot be overemphasized. Therefore, a management system is needed urgently to manage the safety of nuclear facilities and to enhance the efficiency of nuclear information. We have established ISP (Information Strategy Planning) for the Integrated Information System of nuclear facility and safety management. The purpose of this paper is to develop a management system for nuclear safety. Therefore, we developed the Advanced Nuclear Safety Information Management system (hereinafter referred to as the 'ANSIM system'). The ANSIM system has been designed and implemented to computerize nuclear safety information for standardization, integration, and sharing in real-time. Figure 1 shows the main home page of the ANSIM system. In this paper, we describe the design requirements, contents, configurations, and utilizations of the ANSIM system

Quality and safety issues of web-based information about herbal medicines in the treatment of cancer.

Science.gov (United States)

Molassiotis, Alexander; Xu, Min

2004-12-01

A number of studies have been carried out to assess health information on the internet and they all have demonstrated that, whereas the internet can be the third opinion for many patients, often contains inaccurate and misleading information. Furthermore, as herbal medicines are increasingly used by patients, it is imperative to assess the quality of information presented on the internet. Hence, the aim of this study was to assess the quality and safety of the information presented on the internet about medicinal herbs specifically in the field of cancer. Two hundred relevant websites were initially selected from a process using 10 search engines and the keywords 'herbs' and 'cancer', and 43 sites actually met all inclusion criteria. Assessment of both quality and safety indicators was carried out using the DISCERN instrument, which has been developed to enable consumers and information providers to judge the quality of health information. Readability scores of the sites were also obtained (Flesch formula). It was shown that most sites had low quality in a number of indicators, including accuracy of information, revealing sources of information, biased presentation of information or regularity of updates. The mean score for quality was 22.12 (S.D.=4.18) out of a maximum score of 50. The mean safety score was 13.26 (S.D.=2.14) out of a maximum score of 30. Commercial sites had the most inaccurate or misleading information, emphasizing only the positive aspects of the use of herbs, with little or no evidence. The only biomedical sites assessed achieved the highest score in both quality and safety. Readability of the information was equal to the school level of college (mean=44.63). Seven percent of the sites discouraged the use of conventional medicine. Results suggest that health professionals should talk about use of alternative therapies with their patients and help them find the best available information when using the internet.

Think over nuclear safety. ''Information asymmetry'' and ''comminicative action''

International Nuclear Information System (INIS)

Suzuki, Atsuyuki

2006-01-01

Nuclear safety should be fully understood not only technically but also socially. In order to think over nuclear safety socially, four different concepts were recommended to refer, which were ''procedural rationality'', information asymmetry'', ''certainty effect'' and ''communicative action'' proposed by three economists and a philosopher respectively. Risk-based communication approach for nuclear safety could be effective within the higher frequency area than safety goal, but not good for the lower frequency area than safety goal. The latter could be highly subjective and more qualitative. For this area, ''safety communication'' would be highly maintained with taking account of existence of ''information asymmetry'' and need of ''communicative action''. (T.Tanaka)

RISK-INFORMED SAFETY MARGIN CHARACTERIZATION

International Nuclear Information System (INIS)

Dinh, Nam; Szilard, Ronaldo

2009-01-01

The concept of safety margins has served as a fundamental principle in the design and operation of commercial nuclear power plants (NPPs). Defined as the minimum distance between a system's 'loading' and its 'capacity', plant design and operation is predicated on ensuring an adequate safety margin for safety-significant parameters (e.g., fuel cladding temperature, containment pressure, etc.) is provided over the spectrum of anticipated plant operating, transient and accident conditions. To meet the anticipated challenges associated with extending the operational lifetimes of the current fleet of operating NPPs, the United States Department of Energy (USDOE), the Idaho National Laboratory (INL) and the Electric Power Research Institute (EPRI) have developed a collaboration to conduct coordinated research to identify and address the technological challenges and opportunities that likely would affect the safe and economic operation of the existing NPP fleet over the postulated long-term time horizons. In this paper we describe a framework for developing and implementing a Risk-Informed Safety Margin Characterization (RISMC) approach to evaluate and manage changes in plant safety margins over long time horizons

Statement to Second Extraordinary Meeting of Contracting Parties to Convention on Nuclear Safety, 27 August 2012, Vienna, Austria

International Nuclear Information System (INIS)

Amano, Y.

2012-01-01

Full Text: I am pleased to address this Second Extraordinary Meeting of the Contracting Parties to the Convention on Nuclear Safety. This important meeting will be closely watched by the global nuclear community. I know you will make good use of this opportunity to consider further measures to strengthen nuclear safety throughout the world in the light of the lessons which we are still learning from the Fukushima Daiichi accident. One year after the adoption of the IAEA Action Plan on Nuclear Safety, significant progress has been made in several key areas. These include the assessment of safety vulnerabilities of nuclear power plants, strengthening IAEA peer review services, improving emergency preparedness and response capabilities and reviewing IAEA safety standards. Your work this week will address the request to Contracting Parties, expressed in the Action Plan, to explore mechanisms to enhance the effective implementation of Safety Conventions and to consider proposals to amend the Convention on Nuclear Safety. You will recall that last year's Ministerial Declaration stressed 'the importance of universal adherence to, and the effective implementation and continuous review of, the relevant international instruments on nuclear safety'. The Action Plan encouraged Member States to work cooperatively to maximize the lessons learned from the Fukushima Daiichi accident and to produce concrete results as soon as possible. The IAEA has reported periodically to Member States about its work to implement the Action Plan. We have also organised a number of international expert meetings to analyse technical aspects of the accident and ensure that the right lessons are learned. The results of this Extraordinary Meeting will provide an important input to future considerations of implementation of the Action Plan. Our Member States will review implementation at the Agency's 56th General Conference next month, while the Fukushima Ministerial Conference on Nuclear Safety in

Risk-informed, performance-based safety-security interface

International Nuclear Information System (INIS)

Mrowca, B.; Eltawila, F.

2012-01-01

Safety-security interface is a term that is used as part of the commercial nuclear power security framework to promote coordination of the many potentially adverse interactions between plant security and plant safety. Its object is to prevent the compromise of either. It is also used to describe the concept of building security into a plant's design similar to the long standing practices used for safety therefore reducing the complexity of the operational security while maintaining or enhancing overall security. With this in mind, the concept of safety-security interface, when fully implemented, can influence a plant's design, operation and maintenance. It brings the approach use for plant security to one that is similar to that used for safety. Also, as with safety, the application of risk-informed techniques to fully implement and integrate safety and security is important. Just as designers and operators have applied these techniques to enhance and focus safety, these same techniques can be applied to security to not only enhance and focus the security but also to aid in the implementation of effective techniques to address the safety-security interfaces. Implementing this safety-security concept early within the design process can prevent or reduce security vulnerabilities through low cost solutions that often become difficult and expensive to retrofit later in the design and/or post construction period. These security considerations address many of the same issues as safety in ensuring that the response of equipment and plant personnel are adequate. That is, both safety and security are focused on reaching safe shutdown and preventing radiological release. However, the initiation of challenges and the progression of actions in response these challenges and even the definitions of safe shutdown can be considerably different. This paper explores the techniques and limitations that are employed to fully implement a risk-informed, safety-security interface

Information systems in food safety management.

Science.gov (United States)

McMeekin, T A; Baranyi, J; Bowman, J; Dalgaard, P; Kirk, M; Ross, T; Schmid, S; Zwietering, M H

2006-12-01

Information systems are concerned with data capture, storage, analysis and retrieval. In the context of food safety management they are vital to assist decision making in a short time frame, potentially allowing decisions to be made and practices to be actioned in real time. Databases with information on microorganisms pertinent to the identification of foodborne pathogens, response of microbial populations to the environment and characteristics of foods and processing conditions are the cornerstone of food safety management systems. Such databases find application in: Identifying pathogens in food at the genus or species level using applied systematics in automated ways. Identifying pathogens below the species level by molecular subtyping, an approach successfully applied in epidemiological investigations of foodborne disease and the basis for national surveillance programs. Predictive modelling software, such as the Pathogen Modeling Program and Growth Predictor (that took over the main functions of Food Micromodel) the raw data of which were combined as the genesis of an international web based searchable database (ComBase). Expert systems combining databases on microbial characteristics, food composition and processing information with the resulting "pattern match" indicating problems that may arise from changes in product formulation or processing conditions. Computer software packages to aid the practical application of HACCP and risk assessment and decision trees to bring logical sequences to establishing and modifying food safety management practices. In addition there are many other uses of information systems that benefit food safety more globally, including: Rapid dissemination of information on foodborne disease outbreaks via websites or list servers carrying commentary from many sources, including the press and interest groups, on the reasons for and consequences of foodborne disease incidents. Active surveillance networks allowing rapid dissemination

Implementation of the obligations of the convention on nuclear safety. Fourth Swiss report in accordance with Article 5

International Nuclear Information System (INIS)

2007-07-01

Switzerland has signed the Convention on Nuclear Safety. Most of the requirements of the articles of the Convention were already standard practice in Switzerland. In the last years, all Swiss nuclear power plants (NPPs) as well as the Swiss Federal Nuclear Safety Inspectorate (HSK) built up documented quality management systems. The independence of HSK from licensing authorities is fulfilled on a technical level. In 2005, a new Nuclear Energy Act came into force requiring formal independence of the supervisory authorities from the licensing authorities. A separate act to legally settle the Inspectorate's fully independent status was adopted by Parliament. HSK participates in international projects and is represented in numerous nuclear safety working groups in order to ensure the exchange of scientific, technical and regulatory know-how. The regulatory processes applied to the licensing and safety surveillance of nuclear installations and their operation are up to date with the current state of science and technology. Deterministic and probabilistic safety evaluations guide and prioritise inspections and provide the basis for a graded approach to safety review and assessment. The surveillance of the NPPs' operating, control and safety systems, their component performance and integrity, their organisational and human aspects as well as the management, conditioning and interim storage of radioactive waste are permanent features of the supervisory authority's activities. Within the frame of a new integrated oversight process there is an annual systematic assessment of nuclear safety for each NPP based on the analysis of events, inspection results and operator licensing reviews. The assurance of low radiation doses to both NPP workers and the general public is an additional goal that is directly associated with the safe operation of NPPs. In case of an accident in a nuclear installation, contingency plans are in place and are continually updated. Emergency drills are

Implementation of the obligations of the convention on nuclear safety. Fourth Swiss report in accordance with Article 5

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-15

Switzerland has signed the Convention on Nuclear Safety. Most of the requirements of the articles of the Convention were already standard practice in Switzerland. In the last years, all Swiss nuclear power plants (NPPs) as well as the Swiss Federal Nuclear Safety Inspectorate (HSK) built up documented quality management systems. The independence of HSK from licensing authorities is fulfilled on a technical level. In 2005, a new Nuclear Energy Act came into force requiring formal independence of the supervisory authorities from the licensing authorities. A separate act to legally settle the Inspectorate's fully independent status was adopted by Parliament. HSK participates in international projects and is represented in numerous nuclear safety working groups in order to ensure the exchange of scientific, technical and regulatory know-how. The regulatory processes applied to the licensing and safety surveillance of nuclear installations and their operation are up to date with the current state of science and technology. Deterministic and probabilistic safety evaluations guide and prioritise inspections and provide the basis for a graded approach to safety review and assessment. The surveillance of the NPPs' operating, control and safety systems, their component performance and integrity, their organisational and human aspects as well as the management, conditioning and interim storage of radioactive waste are permanent features of the supervisory authority's activities. Within the frame of a new integrated oversight process there is an annual systematic assessment of nuclear safety for each NPP based on the analysis of events, inspection results and operator licensing reviews. The assurance of low radiation doses to both NPP workers and the general public is an additional goal that is directly associated with the safe operation of NPPs. In case of an accident in a nuclear installation, contingency plans are in place and are continually updated

Norwegian national report. Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. [National report from Norway, fourth review meeting, 14-23 May 2012

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-11-15

This report contains the national report from Norway to the fourth review meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management to be held 14 to 23 May 2012. (Author)

Convention on Nuclear Safety. Second national report on the implementation by france of the obligations of the Convention; Convention sur la surete nucleaire. Deuxieme rapport national sur la mise en oeuvre par la France des obligations de la Convention

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-15

The first national report on the implementation by france of the obligation under the Convention is structured along its Articles. the french Nuclear safety Authority ensured the co ordination of the report, with contributions from other regulators and nuclear operators. this report was distributed at the middle of April 2003 to the other Contracting party (on 3 november to 14, 2003 at the IAEA headquarters. (author)

Criticality Safety Information Resource Center Web portal: www.csirc.net

International Nuclear Information System (INIS)

Harmon, C.D. II; Jones, T.

2000-01-01

The Nuclear Criticality Safety Group (ESH-6) at Los Alamos National Laboratory (LANL) is in the process of collecting and archiving historical and technical information related to nuclear criticality safety from LANL and other facilities. In an ongoing effort, this information is being made available via the Criticality Safety Information Resource Center (CSIRC) web site, which is hosted and maintained by ESH-6 staff. Recently, the CSIRC Web site was recreated as a Web portal that provides the criticality safety community with much more than just archived data

Joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Report of the Federal Republic of Germany for the sixth review meeting in May 2018

International Nuclear Information System (INIS)

2017-08-01

The joint convention on the safety of spent fuel management and on the safety of radioactive waste management covers the following topics: historical development and actual status of the civil use of nuclear power, politics and the spent fuel management, inventories and listing, legislation and executive systems, other safeguard regulations, safety during spent fuel handling, safety during radioactive waste processing, transport across national borders, disused enclosed radioactive sources, general regulations for safety enhancement.

National report of the Slovak Republic. Compiled according to the terms of the convention on nuclear safety, June 2010

International Nuclear Information System (INIS)

Balaj, J.; Homola, J.; Rovny, J.; Metke, E.; Zemanova, D.; Grebeciova, J.; Turner, M.; Pospisil, M.; Bystricka, S.; Jurina, V.; Rovny, I.; Soltes, L.; Husarova, M.; Petrovic, J.; Fazekasova, H.; Zizkova, D.; Vagac, M.; Maudry, J.; Hacaj, A.; Betak, A.; Barbaric, M.

2010-06-01

A brief safety report of the Slovak Republic in 2010 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented.These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovak Republic in terms of the convention; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; ((6) Annexes; (6.1) List of nuclear installations and technical and economic indicators; (6.2) Selected generally binding legal regulations and safety guidelines in relation to nuclear and radiation safety; (6.3) List of selected national and international documents applicable to safety of nuclear installations; (6.4) Limits for radioactive discharges; (6.5) Team of authors.

47 CFR 80.1135 - Transmission of maritime safety information.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 5 2010-10-01 2010-10-01 false Transmission of maritime safety information. 80... RADIO SERVICES STATIONS IN THE MARITIME SERVICES Global Maritime Distress and Safety System (GMDSS) Operating Procedures for Distress and Safety Communications § 80.1135 Transmission of maritime safety...

IAEA Director General's concluding remarks. Meeting of the Contracting Parties to the Convention on Nuclear Safety. Vienna, 26 April 2002

International Nuclear Information System (INIS)

ElBaradei, M.

2002-01-01

The Convention on Nuclear Safety is considered as a part of the overall nuclear safety regime. That regime has many components, but they all have one single objective - to make sure that safety is at as high a level as possible. The Convention is a living process, a process which should eventually lead to increasingly greater safety. The Meting has focused on a number of issues that are also priorities for the Agency; one such issue is safety culture. The effectiveness and transparency are key issues. A second issue which is highlighted is management of nuclear knowledge. Other high priority issues which were identified include: planned life extension; the need during life extension to look into the ageing of equipment and structures; deregulation and its impact on safety; and the question of periodic safety reviews. The question of co-operation between regulatory bodies is one that was given emphasis to over the last few years. It is very important that there be exchange of experience and exchange of expertise between regulatory bodies, and between the manufacturers of power reactors and the countries where the reactors are operated. Also of importance in terms of international co-operation is the development of adequate emergency response everywhere. A major point that which is left to the participating countries is that although safety is a national responsibility - there is absolutely no question about that -many issues need international co-operation

A method for risk-informed safety significance categorization using the analytic hierarchy process and bayesian belief networks

International Nuclear Information System (INIS)

Ha, Jun Su; Seong, Poong Hyun

2004-01-01

A risk-informed safety significance categorization (RISSC) is to categorize structures, systems, or components (SSCs) of a nuclear power plant (NPP) into two or more groups, according to their safety significance using both probabilistic and deterministic insights. In the conventional methods for the RISSC, the SSCs are quantitatively categorized according to their importance measures for the initial categorization. The final decisions (categorizations) of SSCs, however, are qualitatively made by an expert panel through discussions and adjustments of opinions by using the probabilistic insights compiled in the initial categorization process and combining the probabilistic insights with the deterministic insights. Therefore, owing to the qualitative and linear decision-making process, the conventional methods have the demerits as follows: (1) they are very costly in terms of time and labor, (2) it is not easy to reach the final decision, when the opinions of the experts are in conflict and (3) they have an overlapping process due to the linear paradigm (the categorization is performed twice - first, by the engineers who propose the method, and second, by the expert panel). In this work, a method for RISSC using the analytic hierarchy process (AHP) and bayesian belief networks (BBN) is proposed to overcome the demerits of the conventional methods and to effectively arrive at a final decision (or categorization). By using the AHP and BBN, the expert panel takes part in the early stage of the categorization (that is, the quantification process) and the safety significance based on both probabilistic and deterministic insights is quantified. According to that safety significance, SSCs are quantitatively categorized into three categories such as high safety significant category (Hi), potentially safety significant category (Po), or low safety significant category (Lo). The proposed method was applied to the components such as CC-V073, CV-V530, and SI-V644 in Ulchin Unit

Information report on the nuclear safety and radiation protection of the Aube storage Centre - 2012

International Nuclear Information System (INIS)

2013-07-01

This report first present the site of the Aube Storage Centre (CSA), its storage areas, its buildings and equipment, describes the water treatment process, proposes some exploitation data for 2012 (deliveries, storage, compacting), and indicates highlights and works performed in 2012. The next part reviews measures related to nuclear safety: recall of safety principles and objectives, technical arrangements to meet safety objectives, inspections by the ASN, quality audits. The third part reviews measures related to safety and radiation protection: principles for radiation protection, staff dosimetry practices and results, personnel safety, works performed in 2012. The fourth part addresses incidents and accidents (none occurred in 2012) and other minor events classified according to the INES scale. The fifth part addresses the control of the environment and the releases by the centre: measurement locations, measurement results (in the atmosphere, in rivers, in underground waters, radiological control, control of ecosystems, assessment of the radiological impact), physical-chemical control of a local river, actions undertaken for the protection of the environment, highlights for 2012. The next chapter addresses the management of the various wastes produced by the Centre (radioactive wastes, conventional wastes) and the last part reports actions regarding information and transparency. Recommendations of the CHSCT are reported

Organizing safety: conditions for successful information assurance programs.

Science.gov (United States)

Collmann, Jeff; Coleman, Johnathan; Sostrom, Kristen; Wright, Willie

2004-01-01

Organizations must continuously seek safety. When considering computerized health information systems, "safety" includes protecting the integrity, confidentiality, and availability of information assets such as patient information, key components of the technical information system, and critical personnel. "High Reliability Theory" (HRT) argues that organizations with strong leadership support, continuous training, redundant safety mechanisms, and "cultures of high reliability" can deploy and safely manage complex, risky technologies such as nuclear weapons systems or computerized health information systems. In preparation for the Health Insurance Portability and Accountability Act (HIPAA) of 1996, the Office of the Assistant Secretary of Defense (Health Affairs), the Offices of the Surgeons General of the United States Army, Navy and Air Force, and the Telemedicine and Advanced Technology Research Center (TATRC), US Army Medical Research and Materiel Command sponsored organizational, doctrinal, and technical projects that individually and collectively promote conditions for a "culture of information assurance." These efforts include sponsoring the "P3 Working Group" (P3WG), an interdisciplinary, tri-service taskforce that reviewed all relevant Department of Defense (DoD), Miliary Health System (MHS), Army, Navy and Air Force policies for compliance with the HIPAA medical privacy and data security regulations; supporting development, training, and deployment of OCTAVE(sm), a self-directed information security risk assessment process; and sponsoring development of the Risk Information Management Resource (RIMR), a Web-enabled enterprise portal about health information assurance.

Application of life-cycle information for advancement in safety of nuclear fuel cycle facilities. Application of safety information to advanced safety management support system

International Nuclear Information System (INIS)

Suzuki, Kazuhiko; Ishida, Michihiko

2005-08-01

Risk management is major concern to nuclear energy reprocessing plants to improve plant and process reliability and ensure their safety. This is because we are required to predict potential risks before any accident or disaster occurs. The advancement of safety design and safety systems technologies showed large amount of useful safety-related knowledge that can be of great importance to plant operation to reduce operation risks and ensure safety. This research proposes safety knowledge modeling framework on the basis of ontology technologies to systematically construct plant knowledge model, which includes plant structure, operation, and the associated behaviors. In such plant knowledge model safety related information is defined and linked to the different elements of plant knowledge model. Ontology editor is employed to define the basic concepts and their inter-relations, which are used to capture and construct plant safety knowledge. In order to provide detailed safety knowledgebase, HAZOP results are analyzed and structured so that safety-related knowledge are identified and structured within the plant knowledgebase. The target safety knowledgebase includes: failures, deviations, causes, consequences, and fault propagation as mapped to plant knowledge. The proposed ontology-based safety framework is applied on case study nuclear plant to structure failures, causes, consequences, and fault propagation, which are used to support plant operation. (author)

Providing public information in the Slovenian Nuclear Safety Administration

International Nuclear Information System (INIS)

Fon Jager, Mojca

2000-01-01

Full text: Good safety culture is strongly related to transparent and timely information. Experience has shown that radiation and nuclear safety are under continuous surveillance by the public. The provision of open and authentic information to the public is a fundamental policy of the SNSA. The SNSA endeavors to provide substantial and reliable information to the interested institutions, mass media and to the citizens through press conferences, public statements, media discussions, and active participation in domestic and international meetings, symposia and congresses, through publications, the Internet and direct contacts with the interested public. The SNSA regularly provides information on nuclear safety to the Government, the National Assembly and the citizens of the Republic of Slovenia. The Annual Report on Nuclear and Radiation Safety is published in Poroeevalec (Reporter) - the publication of the National Assembly - in autumn, and is available in public libraries throughout Slovenia. Annual Report is available also on the Internet (http://www.sigov.si/ursjv/uvod.html) in Slovene and English. Access to data of the Central Radiation Early Warning System of Slovenia (CROSS), recording the real time (at half-hour intervals) gamma dose rate levels, is also available through Internet. The report in English is sent every year to Slovenian embassies world-wide, to certain foreign embassies in Slovenia and to other organizations participating in the activities in the nuclear and radiological field. Reports on the SNSA activities are also published in the bulletin Okolje in prostor (Environment and Spatial Planning), published by the Ministry of Environment and Spatial Planning. The SNSA regularly contributes articles on courses, seminars and symposia attended at home and abroad. The articles are intended to give basic information on training and the names of contact persons to provide additional information on certain topics to those interested. More than half of

Three types of children’s informational web sites: an inventory of design conventions

NARCIS (Netherlands)

Jochmann-Mannak, Hanna; Lentz, Leo; Huibers, Theo W.C.; Sanders, Ted

2012-01-01

"Purpose: Research on Web design conventions has an almost exclusive focus on Web design for adults. There is far less knowledge about Web design for children. For the first time, an overview is presented of the current design conventions for children's informational Web sites. Method: In this study

75 FR 53733 - Pipeline Safety: Information Collection Activities

Science.gov (United States)

2010-09-01

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2010-0246] Pipeline Safety: Information Collection Activities AGENCY: Pipeline and Hazardous... liquefied natural gas, hazardous liquid, and gas transmission pipeline systems operated by a company. The...

Food safety: correct information for pregnant women

Directory of Open Access Journals (Sweden)

Bartolomeo Griglio

2013-04-01

Full Text Available This study was aimed at investigating the knowledge of pregnant women on food safety with particular attention to the effectiveness of the informative material (pamphlet and poster prepared in a previous study. To this scope, a questionnaire composed by 8 questions (Likert scaled was used except for one which was a Y/N question. Themes of the questionnaire were: level of concerns on food safety, and knowledge on foodborne diseases (salomonellosis, toxoplasmosis and listeriosis, risk factors and preventive measures. Results indicate that knowledge increased in respect to that of the previous study, but in relation to informative material previously distributed.

National report of the Slovak Republic - proposal. Compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. Jun 2008

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Kobzova, D.; Petrik, T.; Sovcik, J.; Hekel, P.; Suess, J.; Tomek, J.; Lukacovic, J.; Hekel, P.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Konecny, L.; Parimucha, F.; Vaclav, J.; Horvath, J.; Soos, F.; Betak, A.; Pospisil, P.; Mihaly, B.; Kubala, M.; Schmidtova, B.; Orihel, M.; Vasina, D.; Balaz, J.; Ehn, L.; Micovicova, D.; Vrtoch, M.; Mlcuch, L.; Granak, P.; Meleg, J.; Sedliak, D.; Bardy, M.; Gogoliak, J.; Prazska, M.; Burslova, J.

2008-06-01

A brief national safety report of the Slovak Republic compiled in terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management in 2008 is presented. This safety report consists of following chapters: (A) Introduction; (B) Spent nuclear fuel (SNF) and radioactive waste (RAW) management conception; (C) Scope of application; (D) Spent nuclear fuel (SNF) and radioactive waste (RAW) management; (E) Legislation and regulatory framework; (F) General safety provisions; (G) Safety of spent nuclear fuel management; (H) Safety of radioactive waste management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Discussed sealed radioactive sources; (K) Planned measures to improve safety; (L) Annexes

Implementation of the obligations of the Convention on Nuclear Safety - 6th national report of Switzerland to the Convention in accordance with its article 5

International Nuclear Information System (INIS)

2013-08-01

After a short description of Switzerland as a state in the middle of Europe and of its political organization, the report explains the development of the nuclear power from the first experimental reactor in 1957. Presently five nuclear power plants (NPP) are operating in Switzerland, producing about 40% of the electricity consumption of the country, the rest being produced essentially by hydroelectric plants. As the first regulatory authority, the Swiss Federal Nuclear Safety Commission was set up in 1960, which evolved to the Swiss Nuclear Safety Inspectorate (ENSI). Switzerland signed the Convention on Nuclear Safety (CNS) which came into force at the end of 1996. Since there, Switzerland has prepared and submitted the country reports for the regular Review Meetings of Contracting Countries. This 6th report by ENSI provides an update on compliance with CNS obligations. It gives consideration to issues that aroused particular interest at the 5th meeting and at the extraordinary meeting dedicated to the consequences of the accident at Fukushima Daiichi. Shortly after the accident at Fukushima Daiichi, the Swiss government has decided to phase out nuclear energy; existing plants will continue to operate as long as they are safe. In Switzerland, on-going activities regarding safety assessment of the different stages in the lifetime of nuclear installations consist of periodic assessments and assessments of long-term operation for existing Swiss NPPs. Such assessments have been performed for two Swiss NPPs (Beznau NPP and Muehleberg NPP) which have been in commercial operation for over 40 years. A detailed examination demonstrated that the conditions for the taking out of service of an NPP are not and will not be reached by these two plants within the next 10 years. Nevertheless, it is mandatory to continue with the scheduled ageing management, maintenance and backfitting activities. After the Fukushima accident, additional safety reviews were performed. All Swiss

Implementation of the obligations of the Convention on Nuclear Safety - 6th national report of Switzerland to the Convention in accordance with its article 5

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

After a short description of Switzerland as a state in the middle of Europe and of its political organization, the report explains the development of the nuclear power from the first experimental reactor in 1957. Presently five nuclear power plants (NPP) are operating in Switzerland, producing about 40% of the electricity consumption of the country, the rest being produced essentially by hydroelectric plants. As the first regulatory authority, the Swiss Federal Nuclear Safety Commission was set up in 1960, which evolved to the Swiss Nuclear Safety Inspectorate (ENSI). Switzerland signed the Convention on Nuclear Safety (CNS) which came into force at the end of 1996. Since there, Switzerland has prepared and submitted the country reports for the regular Review Meetings of Contracting Countries. This 6th report by ENSI provides an update on compliance with CNS obligations. It gives consideration to issues that aroused particular interest at the 5th meeting and at the extraordinary meeting dedicated to the consequences of the accident at Fukushima Daiichi. Shortly after the accident at Fukushima Daiichi, the Swiss government has decided to phase out nuclear energy; existing plants will continue to operate as long as they are safe. In Switzerland, on-going activities regarding safety assessment of the different stages in the lifetime of nuclear installations consist of periodic assessments and assessments of long-term operation for existing Swiss NPPs. Such assessments have been performed for two Swiss NPPs (Beznau NPP and Muehleberg NPP) which have been in commercial operation for over 40 years. A detailed examination demonstrated that the conditions for the taking out of service of an NPP are not and will not be reached by these two plants within the next 10 years. Nevertheless, it is mandatory to continue with the scheduled ageing management, maintenance and backfitting activities. After the Fukushima accident, additional safety reviews were performed. All Swiss

Spinal cordd biological safety comparison of intensity modulated radiotherapy and conventional radiation therapy

International Nuclear Information System (INIS)

Xilinbaoleri; Xu Wanlong; Chen Gang; Liu Hao; Wang Ruozheng; Bai Jingping

2010-01-01

Objective: To compare the spine intensity modulated radiation therapy (IMRT) and the conventional radiation therapy on the beagle spinal cord neurons, in order to prove the biological safety of IMRT of the spinal cord. Methods: Twelve selected purebred beagles were randomly divided into 2 groups. A beagle clinical model of tumor was mimiced in the ninth and tenth thoracic vertebrae. Then the beagles were irradiated by 2 different models of intensity modulated radiotherapy and conventional radiation therapy, with the total irradiation doses of 50 and 70 Gy. The samples of spinal cord were taken out from the same position of the nine and tenth thoracic vertebrae at the third month after radiation.All the samples were observed by the electron microscope, and the Fas and HSP70 expression in spinal cord neurons were evaluated by immunohistochemistry method. Terminal deoxynucleatidyl transferase mediated dUTP nick and labeling (TUNEL) technique was used to examine the apoptotic cells in the spinal cord. Results: The neurons in the spinal cord of IMRT group were mainly reversible injury, and those in the conventional radiation therapy were mainly apoptosis. Compared with the conventional radiation therapy group [50 Gy group, (7.3 ± 1.1)%; 70 Gy group, (11.3 ± 1.4)%], the apoptosis rate of the spinal cord neurons of the intensity modulated radiotherapy group [50 Gy group, (1.2 ± 0.7)%; 70 Gy group (2.5 ± 0.8)%] was much lower[(50 Gy group, t=0.022, P<0.05; 70 Gy group, t=0.017, P<0.05)]. The expression levels of Fas in the IMPT group (50 Gy group, 4.6 ± 0.8; 70 Gy group, 7.4 ± 1.1) were also much lowerthan those in the other group (50 Gy group, 15.1 ± 6.4; 70 Gy group, 19.3 ± 7.6. 50 Gy group, t=0.231, P<0.05; 70 Gy group, t=0.457, P<0.05), while the expression levels of HSP70 in the IMPT group (50 Gy group, 9.1 ± 0.8; 70 Gy group, 7.3 ± 1.4)were much higher than those in the conventional radiation therapy group (50 Gy group, 2.1 ± 0.9; 70 Gy group, 1.7 ± 0

International cooperation in nuclear safety

International Nuclear Information System (INIS)

Rosen, M.

1991-01-01

The mechanisms of international co-operations, co-ordinated by International Atomic Energy Agency, are presented. These co-operations are related to international safety standards, to the safety of the four hundred existing reactors in operation, to quick help and information in case of emergency, and to the already valid international conventions. The relation between atomic energy and environmental protection is also discussed briefly. (K.A.)

National report of the Slovak Republic. Compiled according to the terms of the convention on nuclear safety. September 2001

International Nuclear Information System (INIS)

Balaj, J.; Bezak, S.; Gies, F.

2001-09-01

A brief national safety report of the Slovak Republic in 2001 is presented. A account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (1) Introduction; (2) Nuclear installations in Slovakia accords to the convention definition; (3) Legislation and regulation; (4) General safety aspects; (5) Safety of nuclear installations in Slovakia; ((6) Annexes: (a) List of nuclear installations and technical and economic parameters; (b) 6.2 Some generally binding legal regulations concerning nuclear and radiation safety; (c) 6.3 List of some national and international documents relating to safety of WWER type reactors; 6.4 Limits of radioactive substance discharges; 6.5 Author team. Contents, list of abbreviations used as well as reference index are included

Sweden's third national report under the Joint Convention on the safety of spent fuel management and on the safety of radioactive waste management. Swedish implementation of the obligations of the Joint Convention

International Nuclear Information System (INIS)

2008-01-01

Article 32 of the Joint Convention calls for a self-assessment by each Contracting Party regarding compliance with the obligations of the Convention. Sweden's self-assessment has demonstrated compliance with all the obligations of the Convention, as shown in detail in sections B to J of this report. The Swedish existing nuclear power programme is since a few years under strong development. Large amounts are being invested in the 10 remaining operating reactors to prepare for long term operation and major programmes are going on to upgrade and uprate the plants. The former regulatory authorities, the Swedish Nuclear Power Inspectorate (SKI), and the Swedish Radiation Protection Authority (SSI), was merged into a new regulatory body, the Swedish Radiation Safety Authority, July 01, 2008. The new authority has been tasked with the responsibility and tasks from SKI and SSI. These developments create new challenges for the safety work of the licensees as well as for the regulatory authority. Even though comprehensive and very active programmes for the management and disposal of spent fuel and radioactive waste have been established, many challenges remain. Over the next 5-15 years several new facilities will be sited, constructed and taken into operation, e.g. an encapsulation plant and a repository for spent fuel. These activities will require substantial efforts for both the nuclear industry and the regulatory bodies. The generally positive impression reported to earlier review meetings under the Joint Convention still stands. Therefore, Sweden would like to point out the following as strong features in its national nuclear practice: The responsibility for safety is clearly defined in the Swedish legal framework. In order not to dilute the responsibility of the licence holders, the Swedish regulations are designed to define requirements to be achieved, not the detailed means to achieve them. Within the framework given by the regulations, the licence holders have to

U.S. Perspectives on the Joint Convention

International Nuclear Information System (INIS)

Strosnider, J.; Federline, M.; Camper, L.; Abu-Eid, R.; Gnugnoli, G.; Gorn, J.; Bubar, P.; Tonkay, D.

2006-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) is an international convention, under the auspices of the International Atomic Energy Agency (IAEA). It is a companion to a suite of international conventions on nuclear safety and physical security, which serve to promote a global culture for the safe use of radioactive materials. Although the U.S. was the first nation to sign the Joint Convention on September 29, 1997, the ratification process was a challenging experience for the U.S., in the face of legislative priorities dominated by concerns for national security and threats from terrorism after September 11, 2001. Notwithstanding these prevailing circumstances, the U.S. ratified the Joint Convention in 2003, just prior to the First Review Meeting of the Contracting Parties, and participated fully therein. For the United States, participation as a Contracting Party provides many benefits. These range from working with other Parties to harmonize international approaches to achieve strong and effective nuclear safety programs on a global scale, to stimulating initiatives to improve safety systems within our own domestic programs, to learning about technical innovations by other Parties that can be useful to U.S. licensees, utilities, and industry in managing safety and its associated costs in our waste management activities. The Joint Convention process also provides opportunities to identify future areas of bilateral and multilateral technical and regulatory cooperation with other Parties, as well as an opportunity for U.S. vendors and suppliers to broaden their market to include foreign clients for safety improvement equipment and services. The Joint Convention is consistent with U.S. foreign policy considerations to support, as a priority, the strengthening of the worldwide safety culture in the use of nuclear energy. Because of its many benefits, we believe it is important to take

National report of the Slovak Republic compiled in terms of the join convention on the safety of spent fuel management and on the safety of radwaste management

International Nuclear Information System (INIS)

Jurina, V.; Viktory, D.; Petrik, T.; Sovcik, J.; Suess, J.; Tomek, J.; Lukacovic, J.; Ivan, J.; Ziakova, M.; Metke, E.; Pospisil, M.; Turner, M.; Homola, J.; Vaclav, J.; Bystricka, S.; Barbaric, M.; Horvath, J.; Betak, J.; Mihaly, B.; Adamovsky, V.; Baloghova, A.; Orihel, M.; Vasina, D.; Balaz, J.; Misovicova, D.; Vrtoch, M.; Mlcuch, J.; Granak, P.; Meleg, J.; Bardy, M.; Gogoliak, J.

2011-08-01

The National safety report of the Slovak Republic on the safety of spent fuel management and on the safety of radwaste management in 2011 is presented. These activities in the safety of spent fuel management and radioactive waste management in the Slovak Republic are reported under the headings: (A) Introduction; B) Concept for spent nuclear fuel management (SNF) and radwaste management (RAW); (C) Scope of application of the convention; (D) Spent fuel management and radioactive waste (RAW) management facilities; (E) Legislation and regulation; (F) General safety provisions; (G) Safety of spent fuel management; (H) Safety of radioactive waste (RAW) management; (I) Transboundary movement of spent nuclear fuel and radioactive waste; (J) Disused sealed sources; (K) Planned measures to improve safety; (L) Communication with the public; (M) Annexes. Annexes consists of following parts: I. List of nuclear facilities for spent fuel and RAW management. II. Limits of radioactive material discharges into atmosphere and hydrosphere. III. List of nuclear installations in decommissioning. IV. Inventory of stored spent nuclear fuel. V. Inventory of stored RAW. VI. List of national laws, decrees and guidelines. VII. List of international expert reports (including safety reports). VIII. List of authors.

Collection and accumulation of seismic safety research findings, and considerations for information dissemination

International Nuclear Information System (INIS)

2013-01-01

Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

Collection and accumulation of seismic safety research findings, and considerations for information dissemination

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

Seismic Safety Division of JNES is collecting and analyzing the findings of seismic safety research, and is developing a system to organize and disseminate the information internally and internationally. These tasks have been conducted in response to the lessons learned from Fukushima Daiichi NPP accident. The overview of the tasks is as follows; 1) Collection of the knowledge and findings from seismic safety research. JNES collects information on seismic safety researches including the 2011 off the Pacific coast of Tohoku Earthquake. The information is analyzed whether it is important for regulation to increase seismic safety of NPP. 2) Constructing database of seismic safety research. JNES collects information based on documents published by committee and constructs database of active faults around NPP sites in order to incorporate in the seismic safety review. 3) Dissemination of information related to seismic safety. JNES disseminates outcomes of own researches internally and internationally. (author)

Nuclear power safety

International Nuclear Information System (INIS)

1988-01-01

The International Atomic Energy Agency, the organization concerned with worldwide nuclear safety has produced two international conventions to provide (1) prompt notification of nuclear accidents and (2) procedures to facilitate mutual assistance during an emergency. IAEA has also expanded operational safety review team missions, enhanced information exchange on operational safety events at nuclear power plants, and planned a review of its nuclear safety standards to ensure that they include the lessons learned from the Chernobyl nuclear plant accident. However, there appears to be a nearly unanimous belief among IAEA members that may attempt to impose international safety standards verified by an international inspection program would infringe on national sovereignty. Although several Western European countries have proposed establishing binding safety standards and inspections, no specific plant have been made; IAEA's member states are unlikely to adopt such standards and an inspection program

Tailings dams from the perspective of conventional dam engineering

International Nuclear Information System (INIS)

Szymanski, M.B.

1999-01-01

A guideline intended for conventional dams such as hydroelectric, water supply, flood control, or irrigation is used sometimes for evaluating the safety of a tailings dam. Differences between tailings dams and conventional dams are often substantial and, as such, should not be overlooked when applying the techniques or safety requirements of conventional dam engineering to tailings dams. Having a dam safety evaluation program developed specifically for tailings dams is essential, if only to reduce the chance of potential errors or omissions that might occur when relying on conventional dam engineering practice. This is not to deny the merits of using the Canadian Dam Safety Association Guidelines (CDSA) and similar conventional dam guidelines for evaluating the safety of tailings dams. Rather it is intended as a warning, and as a rationale underlying basic requirement of tailings dam emgineering: specific experience in tailings dams is essential when applying conventional dam engineering practice. A discussion is included that focuses on the more remarkable tailings dam safety practics. It is not addressed to a technical publications intended for such dams, or significantly different so that the use of conventional dam engineering practice would not be appropriate. The CDSA Guidelines were recently revised to include tailings dams. But incorporating tailings dams into the 1999 revision of the CDSA Guidelines is a first step only - further revision is necessary with respect to tailings dams. 11 refs., 2 tabs

Transactions of the nineteenth water reactor safety information meeting

International Nuclear Information System (INIS)

Weiss, A.J.

1991-10-01

This report contains summaries of papers on reactor safety research to be presented at the 19th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 28--30, 1991. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from the governments and industry in Europe and Japan are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting, and are given in the order of their presentation in each session. The individual summaries have been cataloged separately

Transoral endoscopic surgery versus conventional thoracoscopic surgery for thoracic intervention: safety and efficacy in a canine survival model.

Science.gov (United States)

Liu, Chien-Ying; Chu, Yen; Wu, Yi-Cheng; Yuan, Hsu-Chia; Ko, Po-Jen; Liu, Yun-Hen; Liu, Hui-Ping

2013-07-01

Transoral endoscopic surgery has been shown to be feasible and safe in both humans and animal models. The purpose of this study was to evaluate the safety and efficacy of transoral and conventional thoracoscopy for thoracic exploration, surgical lung biopsy, and pericardial window creation. The animals (n = 20) were randomly assigned to the transoral endoscopic approach group (n = 10) or conventional thoracoscopic approach group (n = 10). Transoral thoracoscopy was performed with a flexible bronchoscope via an incision over the vestibulum oris. In conventional thoracoscopy, access to the thoracic cavity was obtained through a thoracic incision. Surgical outcomes (body weight, operating time, operative complications, and time to resumption of normal diet), physiologic parameters (respiratory rate, body temperature), inflammatory parameters [white blood cell (WBC) counts and C-reactive protein (CRP)], and pulmonary parameters (arterial blood gases) were compared for both procedures. The surgical lung biopsy and pericardial window creation were successfully performed in all animals except one animal in the transoral group. There was no significant difference in operating times between the groups. The increase in WBC in the transoral thoracoscopy group was significantly smaller on postoperative day 1 than in the conventional thoracoscopy group (p = 0.0029). The transoral group had an earlier return to preoperative body temperature (p = 0.041) and respiratory rate (p = 0.045) on day 7. With respect to pulmonary parameters, there was no significant difference in blood pH, pCO2, or PaCO2 between the transoral and transthoracic groups. All animals survived without complications 14 days after surgery. This study demonstrated that the transoral approach was comparable to conventional thoracoscopic surgery for lung biopsy and pericardial window creation in terms of safety and efficacy.

Safety Psychology Applicating on Coal Mine Safety Management Based on Information System

Science.gov (United States)

Hou, Baoyue; Chen, Fei

In recent years, with the increase of intensity of coal mining, a great number of major accidents happen frequently, the reason mostly due to human factors, but human's unsafely behavior are affected by insecurity mental control. In order to reduce accidents, and to improve safety management, with the help of application security psychology, we analyse the cause of insecurity psychological factors from human perception, from personality development, from motivation incentive, from reward and punishment mechanism, and from security aspects of mental training , and put forward countermeasures to promote coal mine safety production,and to provide information for coal mining to improve the level of safety management.

A proposed approach for enhancing design safety assurance of future plants

International Nuclear Information System (INIS)

Oh, Kyu Myeng; Ahn, Sang Kyu; Lee, Chang Ju; Kim, Inn Seock

2010-01-01

This paper provides various insights from a detailed review of deterministic approaches typically applied to ensure design safety of nuclear power plants (NPPs) and risk-informed approaches proposed to evaluate safety of advanced reactors such as Generation IV reactors. Also considered herein are the risk-informed safety analysis (RISA) methodology suggested by Westinghouse as a means to improve the conventional accident analysis, together with the Technology Neutral Framework recently suggested by the U.S. NRC for safety evaluation of future plants. These insights from the comparative review of deterministic and risk-informed approaches could be used in further enhancing the methodology for design safety assurance of future plants

MedWatch, the FDA Safety Information and Adverse Event Reporting Program

Science.gov (United States)

... Reporting Program MedWatch: The FDA Safety Information and Adverse Event Reporting Program Share Tweet Linkedin Pin it ... approved information that can help patients avoid serious adverse events. Potential Signals of Serious Risks/New Safety ...

The Nuclear Safety Convention - does it confirm existing German law, and update international law?

International Nuclear Information System (INIS)

Lindemann, C.

1995-01-01

Some selected examples are discussed that are intended to answer the question of whether the NSC in its essence represents a development in confirmation of existing German nuclear law, and whether, assuming its coming into effect, this Convention will mean a step forward in the development of international law. The author examines the value of this codification of international law as such, and some of the obligations and standards such as retrofitting measures or shutdown of reactors below safety standard, and continues with briefly discussing the relationship between the NSC and nuclear liability law, the planned provisions for radiological protection in Art. 15, and the obligations for transboundary notification of safety-relevant events. These stipulations are analysed in comparison to existing international law, and with a view to their implementation under German law. Some provisions of the NSC that are based on standards of international technical guidance are compared with German regulatory guides. (orig./HP) [de

An international nuclear safety regime

International Nuclear Information System (INIS)

Rosen, M.

1995-01-01

For all the parties involved with safe use of nuclear energy, the opening for signature of the 'Convention on Nuclear Safety' (signed by 60 countries) and the ongoing work to prepare a 'Convention on Radioactive Waste Safety' are particularly important milestones. 'Convention on Nuclear Safety' is the first legal instrument that directly addresses the safety of nuclear power plants worldwide. The two conventions are only one facet of international cooperation to enhance safety. A review of some cooperative efforts of the past decades, and some key provisions of the new safety conventions, presented in this paper, show how international cooperation is increasing nuclear safety worldwide. The safety philosophy and practices involved with legal framework for the safe use of nuclear power will foster a collective international involvement and commitment. It will be a positive step towards increasing public confidence in nuclear power

Managing knowledge and information on nuclear safety

International Nuclear Information System (INIS)

Hahn, L.

2005-01-01

Described is the management of nuclear safety knowledge through education networks, knowledge pool, sharing, archiving and distributing the knowledge information. Demonstrated is the system used at Gesellschaft fuer Anlagen-und Reaktorsicherheit

The Aube Storage Centre. Information report on nuclear safety and radiation protection for 2014 - Annual report 2014

International Nuclear Information System (INIS)

2014-06-01

After a presentation of the installations of CSA (Aube Storage Centre), its equipment, its exploitation (deliveries, storage, compacting unit, injection unit, storage works), works performed and highlights in 2014, and perspectives of evolution for 2015 and 2016, this report presents the measures regarding nuclear safety: safety principles, technical measures to meet objectives, inspections performed by the Nuclear Safety Authority (ASN), and quality management. The next part presents measures regarding measures for radiation protection and safety: staff dosimetry (measurements results and evolutions), safety exercise. It outlines that no important incident occurred, and described three minor events which have been declared to the ASN. The next part addresses actions related to the control of the environment and of releases: water management, presentation and discussion of the main results of radiological measurements (rainfalls, air, brook waters, sediments, underground waters, radiation at the edge of the centre, ground vegetal, food chain, aquatic ecosystems), physical-chemical control of waters, actions for the protection of the environment. The report then gives an overview of the management of radioactive and conventional wastes produced by the Centre. The last part indicates and comments actions related to transparency and information (they may concern the public, local authorities, institutions, or media): visits, conferences, exhibitions, animations, partnerships, publications

Transactions of the twenty-fifth water reactor safety information meeting

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.

1997-09-01

This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session.

Transactions of the twenty-fifth water reactor safety information meeting

International Nuclear Information System (INIS)

Monteleone, S.

1997-09-01

This report contains summaries of papers on reactor safety research to be presented at the 25th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 20--22, 1997. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion of information exchanged during the course of the meeting, and are given in order of their presentation in each session

Radiation safety research information database

International Nuclear Information System (INIS)

Yukawa, Masae; Miyamoto, Kiriko; Takeda, Hiroshi; Kuroda, Noriko; Yamamoto, Kazuhiko

2004-01-01

National Institute of Radiological Sciences in Japan began to construct Radiation Safety Research Information Database' in 2001. The research information database is of great service to evaluate the effects of radiation on people by estimating exposure dose by determining radiation and radioactive matters in the environment. The above database (DB) consists of seven DB such as Nirs Air Borne Dust Survey DB, Nirs Environmental Tritium Survey DB, Nirs Environmental Carbon Survey DB, Environmental Radiation Levels, Abe, Metabolic Database for Assessment of Internal Dose, Graphs of Predicted Monitoring Data, and Nirs nuclear installation environment water tritium survey DB. Outline of DB and each DB are explained. (S.Y.)

Information report on nuclear safety and radiation protection of the Manche storage Centre - 2012

International Nuclear Information System (INIS)

2013-06-01

After a presentation of the Manche Storage Centre (CSM), the first French centre of surface storage of weakly and moderately radioactive wastes, of its history, its buildings and activities, of the multi-layer cover, of the water management system (installation, controls, sampling), this report describes the measures related to nuclear safety (principles and objectives, prevention measures, technical measures, regulatory plan of control of the Centre and of its environment, control of releases from storage installations, quality organisation, archiving system). It describes measures related to radiation protection: principles, staff dosimetry, and personnel safety. The next part presents the nuclear event scale (INES) and indicates that no incident occurred. The effluents and releases from the Centre are then addressed: origin, locations and results of radiological controls of rainfalls, of risky effluents, of underground waters, of rivers, impacts of the Centre on its environment (releases in the sea, in rivers). The management of conventional and nuclear wastes produced by the Centre is reviewed as well as the actions related to information and transparency. Recommendations of the CHSCT are reported

Information about the control of nuclear safety in France

International Nuclear Information System (INIS)

Gerster, D.

1994-01-01

The permanent objective of the French Nuclear Safety Authority is the public information about technical controls performed in French nuclear installations. Three publications from the DSIN (Direction of Nuclear Installations Safety) are devoted to this effort: the MAGNUC Minitel magazine, the annual activity report and the CONTROLE magazine. Details about the content of these publications are given. A large part of the information about control of nuclear safety concerns the incidents and accidents and their importance level. A seriousness scale was created in France at the beginning of 1988 and replaced in April 1994 by the very similar International Nuclear Event Scale (INES). Explanation of this scale is given and illustrated with examples of real events and accidents. However, international comparison between incidents and accidents remains delicate because the detailed content of safety reports can change significantly from one country to another. (J.S.). 1 fig

An Adaptive Information Quantity-Based Broadcast Protocol for Safety Services in VANET

Directory of Open Access Journals (Sweden)

Wenjie Wang

2016-01-01

Full Text Available Vehicle-to-vehicle communication plays a significantly important role in implementing safe and efficient road traffic. When disseminating safety messages in the network, the information quantity on safety packets changes over time and space. However, most of existing protocols view each packet the same to disseminate, preventing vehicles from collecting more recent and precise safety information. Hence, an information quantity-based broadcast protocol is proposed in this paper to ensure the efficiency of safety messages dissemination. In particular, we propose the concept of emergency-degree to evaluate packets’ information quantity. Then we present EDCast, an emergency-degree-based broadcast protocol. EDCast differentiates each packet’s priority for accessing the channel based on its emergency-degree so as to provide vehicles with more safety information timely and accurately. In addition, an adaptive scheme is presented to ensure fast dissemination of messages in different network condition. We compare the performance of EDCast with those of three other representative protocols in a typical highway scenario. Simulation results indicate that EDCast achieves higher broadcast efficiency and less redundancy with less delivery delay. What we found demonstrates that it is feasible and necessary for incorporating information quantity of messages in designing an efficient safety message broadcast protocol.

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2009

International Nuclear Information System (INIS)

2009-01-01

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2009 are published

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2011

International Nuclear Information System (INIS)

2011-04-01

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2012

International Nuclear Information System (INIS)

2012-04-01

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2011

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-04-15

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2011 are published.

Answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2014

International Nuclear Information System (INIS)

2014-04-01

In this publication detail answers to questions on National report of the Slovak Republic compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management of April 2014 are published.

Comparison of the Microbiological Quality and Safety between Conventional and Organic Vegetables Sold in Malaysia

Directory of Open Access Journals (Sweden)

Chee-Hao Kuan

2017-07-01

Full Text Available Given the remarkable increase of public interest in organic food products, it is indeed critical to evaluate the microbiological risk associated with consumption of fresh organic produce. Organic farming practices including the use of animal manures may increase the risk of microbiological contamination as manure can act as a vehicle for transmission of foodborne pathogens. This study aimed to determine and compare the microbiological status between organic and conventional fresh produce at the retail level in Malaysia. A total of 152 organic and conventional vegetables were purchased at retail markets in Malaysia. Samples were analyzed for mesophilic aerobic bacteria, yeasts and molds, and total coliforms using conventional microbiological methods. Combination methods of most probable number-multiplex polymerase chain reaction (MPN-mPCR were used to detect and quantify foodborne pathogens, including Escherichia coli O157:H7, Shiga toxin-producing E. coli (STEC, Listeria monocytogenes, Salmonella Typhimurium, and Salmonella Enteritidis. Results indicated that most types of organic and conventional vegetables possessed similar microbial count (P > 0.05 of mesophilic aerobic bacteria, yeasts and molds, and total coliforms. E. coli O157:H7 and S. Typhimurium were not detected in any sample analyzed in this study. Among the 152 samples tested, only the conventional lettuce and organic carrot were tested positive for STEC and S. Enteritidis, respectively. L. monocytogenes were more frequently detected in both organic (9.1% and conventional vegetables (2.7% as compared to E. coli O157:H7, S. Typhimurium, and S. Enteritidis. Overall, no trend was shown that either organically or conventionally grown vegetables have posed greater microbiological risks. These findings indicated that one particular type of farming practices would not affect the microbiological profiles of fresh produce. Therefore, regardless of farming methods, all vegetables should be

Comparison of the Microbiological Quality and Safety between Conventional and Organic Vegetables Sold in Malaysia.

Science.gov (United States)

Kuan, Chee-Hao; Rukayadi, Yaya; Ahmad, Siti H; Wan Mohamed Radzi, Che W J; Thung, Tze-Young; Premarathne, Jayasekara M K J K; Chang, Wei-San; Loo, Yuet-Ying; Tan, Chia-Wanq; Ramzi, Othman B; Mohd Fadzil, Siti N; Kuan, Chee-Sian; Yeo, Siok-Koon; Nishibuchi, Mitsuaki; Radu, Son

2017-01-01

Given the remarkable increase of public interest in organic food products, it is indeed critical to evaluate the microbiological risk associated with consumption of fresh organic produce. Organic farming practices including the use of animal manures may increase the risk of microbiological contamination as manure can act as a vehicle for transmission of foodborne pathogens. This study aimed to determine and compare the microbiological status between organic and conventional fresh produce at the retail level in Malaysia. A total of 152 organic and conventional vegetables were purchased at retail markets in Malaysia. Samples were analyzed for mesophilic aerobic bacteria, yeasts and molds, and total coliforms using conventional microbiological methods. Combination methods of most probable number-multiplex polymerase chain reaction (MPN-mPCR) were used to detect and quantify foodborne pathogens, including Escherichia coli O157:H7, Shiga toxin-producing E. coli (STEC), Listeria monocytogenes, Salmonella Typhimurium, and Salmonella Enteritidis. Results indicated that most types of organic and conventional vegetables possessed similar microbial count ( P > 0.05) of mesophilic aerobic bacteria, yeasts and molds, and total coliforms. E. coli O157:H7 and S . Typhimurium were not detected in any sample analyzed in this study. Among the 152 samples tested, only the conventional lettuce and organic carrot were tested positive for STEC and S . Enteritidis, respectively. L. monocytogenes were more frequently detected in both organic (9.1%) and conventional vegetables (2.7%) as compared to E. coli O157:H7, S . Typhimurium, and S . Enteritidis. Overall, no trend was shown that either organically or conventionally grown vegetables have posed greater microbiological risks. These findings indicated that one particular type of farming practices would not affect the microbiological profiles of fresh produce. Therefore, regardless of farming methods, all vegetables should be subjected to

Comparison of the Microbiological Quality and Safety between Conventional and Organic Vegetables Sold in Malaysia

Science.gov (United States)

Kuan, Chee-Hao; Rukayadi, Yaya; Ahmad, Siti H.; Wan Mohamed Radzi, Che W. J.; Thung, Tze-Young; Premarathne, Jayasekara M. K. J. K.; Chang, Wei-San; Loo, Yuet-Ying; Tan, Chia-Wanq; Ramzi, Othman B.; Mohd Fadzil, Siti N.; Kuan, Chee-Sian; Yeo, Siok-Koon; Nishibuchi, Mitsuaki; Radu, Son

2017-01-01

Given the remarkable increase of public interest in organic food products, it is indeed critical to evaluate the microbiological risk associated with consumption of fresh organic produce. Organic farming practices including the use of animal manures may increase the risk of microbiological contamination as manure can act as a vehicle for transmission of foodborne pathogens. This study aimed to determine and compare the microbiological status between organic and conventional fresh produce at the retail level in Malaysia. A total of 152 organic and conventional vegetables were purchased at retail markets in Malaysia. Samples were analyzed for mesophilic aerobic bacteria, yeasts and molds, and total coliforms using conventional microbiological methods. Combination methods of most probable number-multiplex polymerase chain reaction (MPN-mPCR) were used to detect and quantify foodborne pathogens, including Escherichia coli O157:H7, Shiga toxin-producing E. coli (STEC), Listeria monocytogenes, Salmonella Typhimurium, and Salmonella Enteritidis. Results indicated that most types of organic and conventional vegetables possessed similar microbial count (P > 0.05) of mesophilic aerobic bacteria, yeasts and molds, and total coliforms. E. coli O157:H7 and S. Typhimurium were not detected in any sample analyzed in this study. Among the 152 samples tested, only the conventional lettuce and organic carrot were tested positive for STEC and S. Enteritidis, respectively. L. monocytogenes were more frequently detected in both organic (9.1%) and conventional vegetables (2.7%) as compared to E. coli O157:H7, S. Typhimurium, and S. Enteritidis. Overall, no trend was shown that either organically or conventionally grown vegetables have posed greater microbiological risks. These findings indicated that one particular type of farming practices would not affect the microbiological profiles of fresh produce. Therefore, regardless of farming methods, all vegetables should be subjected to

Transactions of the Twenty-First Water Reactor Safety Information Meeting

International Nuclear Information System (INIS)

Monteleone, S.

1993-10-01

This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session

Transactions of the Twenty-First Water Reactor Safety Information Meeting

Energy Technology Data Exchange (ETDEWEB)

Monteleone, S. [comp.

1993-10-01

This report contains summaries of papers on reactor safety research to be presented at the 21st Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 25--27, 1993. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session.

Transactions of the twenty-second water reactor safety information meeting

International Nuclear Information System (INIS)

1994-10-01

This report contains summaries of papers on reactor safety research to be presented at the 22nd Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel, Bethesda, Maryland, October 24--26, 1994. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, US NRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the nuclear industry, and from foreign governments and industry are also included. The summaries have been compiled in one report to provide a basis for meaningful discussion and information exchange during the course of the meeting and are given in the order of their presentation in each session. Individual papers have been cataloged separately

Transactions of the Twentieth Water Reactor Safety Information Meeting

International Nuclear Information System (INIS)

Weiss, A.J.

1992-10-01

This report contains summaries of papers on reactor safety research to be presented at the 20th Water Reactor Safety Information Meeting at the Bethesda Marriott Hotel in Bethesda, Maryland, October 21--23, 1992. The summaries briefly describe the programs and results of nuclear safety research sponsored by the Office of Nuclear Regulatory Research, USNRC. Summaries of invited papers concerning nuclear safety issues from US government laboratories, the electric utilities, the Electric Power Research Institute (EPRI), the nuclear industry, and from foreign governments and industry are also included

Maintenance of radiation safety information system

Energy Technology Data Exchange (ETDEWEB)

Choi, Ho Sun [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Park, Moon Il; Chung, Chong Kyu; Lim, Bock Soo; Kim, Hyung Uk; Chang, Kwang Il; Nam, Kwan Hyun; Cho, Hye Ryan [AD center incubation LAB, Taejon (Korea, Republic of)

2001-12-15

The objectives of radiation safety information system maintenance are to maintain the requirement of users, change of job process and upgrade of the system performance stably and effectively while system maintenance. We conduct the code of conduct recommended by IAEA, management of radioisotope inventory database systematically using analysis for the state of inventory database integrated in this system. This system and database will be support the regulatory guidance, rule making and information to the MOST, KINS, other regulatory related organization and general public optimizationally.

49 CFR 575.301 - Vehicle Labeling of Safety Rating Information.

Science.gov (United States)

2010-10-01

... providing them with safety rating information developed by NHTSA in its New Car Assessment Program (NCAP..., as specified at 15 U.S.C. 1231-1233. (2) Safety rating label means the label with NCAP safety rating... has approved an optional NCAP test that will cover that category, the manufacturer may depict vehicles...

Integrated care: an Information Model for Patient Safety and Vigilance Reporting Systems.

Science.gov (United States)

Rodrigues, Jean-Marie; Schulz, Stefan; Souvignet, Julien

2015-01-01

Quality management information systems for safety as a whole or for specific vigilances share the same information types but are not interoperable. An international initiative tries to develop an integrated information model for patient safety and vigilance reporting to support a global approach of heath care quality.

Design Information from the PSA for Digital Safety-Critical Systems

International Nuclear Information System (INIS)

Kang, Hyun Gook; Jang, Seung Cheol

2005-01-01

Many safety-critical applications such as nuclear field application usually adopt a similar design strategy for digital safety-critical systems. Their differences from the normal design for the non-safety-critical applications could be summarized as: multiple-redundancy, highly reliable components, strengthened monitoring mechanism, verified software, and automated test procedure. These items are focusing on maintaining the capability to perform the given safety function when it is requested. For the past several decades, probabilistic safety assessment (PSA) techniques are used in the nuclear industry to assess the relative effects of contributing events on plant risk and system reliability. They provide a unifying means of assessing physical faults, recovery processes, contributing effects, human actions, and other events that have a high degree of uncertainty. The applications of PSA provide not only the analysis results of already installed system but also the useful information for the system under design. The information could be derived from the PSA experience of the various safety-critical systems. Thanks to the design flexibility, the digital system is one of the most suitable candidates for risk-informed design (RID). In this article, we will describe the feedbacks for system design and try to develop a procedure for RID. Even though the procedure is not sophisticated enough now, it could be the start point of the further investigation for developing more complete and practical methodology

Safety of type and screen method compared to conventional antiglobulin crossmatch procedures for compatibility testing in Indian setting

Directory of Open Access Journals (Sweden)

Chaudhary Rajendra

2011-01-01

Full Text Available Background: Over the past 30 years, pretransfusion tests have undergone considerable modification. In 1984, AABB recommended that the full cross match could be replaced by an abbreviated cross match in patients with negative antibody screen. However, before implementation of such a policy, issue regarding safety of T & S needs to be evaluated. Objectives: The aim of pretransfusion testing (PTT is to ensure that enough red blood cells (RBCs in the selected red cell components will survive when transfused. Results and Conclusion: We have, therefore in this study; evaluated safety of T & S procedure for PTT in comparison with conventional test tube cross match. The T & S procedure gave a safety of 91.6%. Also, the usefulness of the T & S was shown through the detection of unexpected antibodies in 0.75% (15 out of 2026 of cases.

Transumbilical Thoracoscopy Versus Conventional Thoracoscopy for Lung Wedge Resection: Safety and Efficacy in a Live Canine Model.

Science.gov (United States)

Chen, Tzu-Ping; Yen-Chu; Wu, Yi-Cheng; Yeh, Chi-Ju; Liu, Chien-Ying; Hsieh, Ming-Ju; Yuan, Hsu-Chia; Ko, Po-Jen; Liu, Yun-Hen

2015-12-01

Transumbilical single-port surgery has been associated with less postoperative pain and offers better cosmetic outcomes than conventional 3-port laparoscopic surgery. This study compares the safety and efficacy of transumbilical thoracoscopy and conventional thoracoscopy for lung wedge resection. The animals (n = 16) were randomly assigned to the transumbilical thoracoscopic approach group (n = 8) or conventional thoracoscopic approach group (n = 8). Transumbilical lung resection was performed via an umbilical incision and a diaphragmatic incision. In the conventional thoracoscopic group, lung resection was completed through a thoracic incision. For both procedures, we compared the surgical outcomes, for example, operating time and operative complications; physiologic parameters, for example, respiratory rate and body temperature; inflammatory parameters, for example, white blood cell count; and pulmonary parameters, for example, arterial blood gas levels. The animals were euthanized 2 weeks after the surgery for gross and histologic evaluations. The lung wedge resection was successfully performed in all animals. There was no significant difference in the mean operating times or complications between the transumbilical and the conventional thoracoscopic approach groups. With regard to the physiologic impact of the surgeries, the transumbilical approach was associated with significant elevations in body temperature on postoperative day 1, when compared with the standard thoracoscopic approach. This study suggests that both approaches for performing lung wedge resection were comparable in efficacy and postoperative complications. © The Author(s) 2014.

Statement to Sixth Review Meeting of Contracting Parties to Convention on Nuclear Safety, 4 April 2014, Vienna, Austria

International Nuclear Information System (INIS)

Amano, Y.

2014-01-01

Full text: Good afternoon, Dear Colleagues, Ladies and Gentlemen, I am pleased to say a few words to you at the end of the Sixth Review Meeting of the Contracting Parties to the Convention on Nuclear Safety. The Convention is a very important mechanism which has contributed a lot to strengthening nuclear safety in the countries which are party to it. In the last two weeks, you have addressed some very important issues. During your productive and lively discussions, a number of challenges were identified for consideration by Contracting Parties. These included: how to achieve harmonized emergency plans and response measures; how to make better use of operating and regulatory experience and international peer review services; and how to strengthen regulators' independence, safety culture, transparency and openness. The Agency will continue to work closely with you in addressing all of these issues. The Fifth Review Conference, which took place in 2011 just after the Fukushima Daiichi accident, was the first opportunity for Contracting Parties to address the accident in an international conference. The fact that you devoted a special session to the Fukushima Daiichi accident this time demonstrates the continued resolve of the Contracting Parties to ensure that the right lessons are learned everywhere. The Agency continues to work with all our Member States to implement the IAEA Action Plan on Nuclear Safety, about which you received a briefing. I know you will agree with me that it is vitally important that all the measures that have been agreed to strengthen global nuclear safety are actually implemented. Work continues on the IAEA report on the Fukushima Daiichi accident, which will be finalised this year. I understand that you decided to submit a proposal to amend the text of the Convention, addressing design and construction objectives for both existing and new nuclear power plants, to a Diplomatic Conference to be convened within one year. I am aware that a clear

77 FR 69899 - Public Conference on Geographic Information Systems (GIS) in Transportation Safety

Science.gov (United States)

2012-11-21

... NATIONAL TRANSPORTATION SAFETY BOARD Public Conference on Geographic Information Systems (GIS) in... Geographic Information Systems (GIS) in transportation safety on December 4-5, 2012. GIS is a rapidly... visualization of data. The meeting will bring researchers and practitioners in transportation safety and GIS...

Compatibility of Safety Properties and Possibilistic Information Flow Security in MAKS

OpenAIRE

Bauereiss , Thomas; Hutter , Dieter

2014-01-01

Part 6: Information Flow Control; International audience; Motivated by typical security requirements of workflow management systems, we consider the integrated verification of both safety properties (e.g. separation of duty) and information flow security predicates of the MAKS framework (e.g. modeling confidentiality requirements). Due to the refinement paradox, enforcement of safety properties might violate possibilistic information flow properties of a system. We present an approach where s...

Overview of the IAEA Joint Convention and Implementation Status of the Obligation as the Contracting Party of the 5th Joint Convention

International Nuclear Information System (INIS)

Lee, Jeong Ken; Lee, Youn Keun; Ahn, Sang Myeon

2016-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) was adopted on 5 September 1997 by a Diplomatic Conference convened by the International Atomic Energy Agency (IAEA). The Joint Convention was opened for signature at Vienna in September 1997 and will remain open for signature until its entry into force. Korean government signed the Joint Convention in 1997 and this Convention was effective in 2002 as the Convention No. 1612. This paper will show overview of the Joint Convention and implementation status of the obligation as a Contracting Party of the 5th Joint Convention. The Joint Convention is the inter-national convention organized by the IAEA. All contracting parties shall comply with rules of the Joint Convention and conduct the obligation of this convention. Korean government successfully conducted all obligation (attending Organization Meeting and Review Meeting, submitting paper including National Report, question paper and answer paper) of the 5th Joint Convention from May 2014 to May 2015, and will prepare the obligation of the 6th Joint Convention

Quantum information transfer between topological and conventional charge qubits

International Nuclear Information System (INIS)

Li Jun; Zou Yan

2016-01-01

We propose a scheme to realize coherent quantum information transfer between topological and conventional charge qubits. We first consider a hybrid system where a quantum dot (QD) is tunnel-coupled to a semiconductor Majorana-hosted nanowire (MNW) via using gated control as a switch, the information encoded in the superposition state of electron empty and occupied state can be transferred to each other through choosing the proper interaction time to make measurements. Then we consider another system including a double QDs and a pair of parallel MNWs, it is shown that the entanglement information transfer can be realized between the two kinds of systems. We also realize long distance quantum information transfer between two quantum dots separated by an MNW, by making use of the nonlocal fermionic level formed with the pared Majorana feimions (MFs) emerging at the two ends of the MNW. Furthermore, we analyze the teleportationlike electron transfer phenomenon predicted by Tewari et al. [Phys. Rev. Lett. 100, 027001 (2008)] in our considered system. Interestingly, we find that this phenomenon exactly corresponds to the case that the information encoded in one QD just returns back to its original place during the dynamical evolution of the combined system from the perspective of quantum state transfer. (paper)

Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. April 2006

International Nuclear Information System (INIS)

2003-04-01

Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (2005). Slovakia is ready to provide additional explanations to these Answers during the 2 nd Review Meeting. In the Annexes the 541/2004 Coll. LL. Act of 9 September 2004 on Peaceful Use of Nuclear Energy (Atomic Act) and on Alternations and Amendments to Some Acts

30 CFR 75.206 - Conventional roof support.

Science.gov (United States)

2010-07-01

... HEALTH MANDATORY SAFETY STANDARDS-UNDERGROUND COAL MINES Roof Support § 75.206 Conventional roof support. (a) Except in anthracite mines using non-mechanized mining systems, when conventional roof support... 30 Mineral Resources 1 2010-07-01 2010-07-01 false Conventional roof support. 75.206 Section 75...

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory

International Nuclear Information System (INIS)

Henderson, B.D.; Meade, R.A.; Pruvost, N.L.

1999-01-01

The Criticality Safety Information Resource Center (CSIRC) at Los Alamos National Laboratory (LANL) is a program jointly funded by the U.S. Department of Energy (DOE) and the U.S. Nuclear Regulatory Commission (NRC) in conjunction with the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2. The goal of CSIRC is to preserve primary criticality safety documentation from U.S. critical experimental sites and to make this information available for the benefit of the technical community. Progress in archiving criticality safety primary documents at the LANL archives as well as efforts to make this information available to researchers are discussed. The CSIRC project has a natural linkage to the International Criticality Safety Benchmark Evaluation Project (ICSBEP). This paper raises the possibility that the CSIRC project will evolve in a fashion similar to the ICSBEP. Exploring the implications of linking the CSIRC to the international criticality safety community is the motivation for this paper

Thermal analysis and safety information for metal nanopowders by DSC

Energy Technology Data Exchange (ETDEWEB)

Tseng, J.M.; Huang, S.T. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Duh, Y.S.; Hsieh, T.Y.; Sun, Y.Y. [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China); Lin, J.Z. [Institute of Safety and Disaster Prevention Technology, Central Taiwan University of Science and Technology, 666, Buzih Road, Beitun District, Taichung 40601, Taiwan, ROC (China); Wu, H.C. [Institute of Occupational Safety and Health, Council of Labor Affairs, Taipei, Taiwan, ROC (China); Kao, C.S., E-mail: jcsk@nuu.edu.tw [Department of Safety Health and Environmental Engineering, National United University, Miaoli, Taiwan, ROC (China)

2013-08-20

Highlights: • Metal nanopowders are common and frequently employed in industry. • Nano iron powder experimental results of T{sub o} were 140–150 °C. • Safety information can benefit relevant metal powders industries. - Abstract: Metal nanopowders are common and frequently employed in industry. Iron is mostly applied in high-performance magnetic materials and pollutants treatment for groundwater. Zinc is widely used in brass, bronze, die casting metal, alloys, rubber, and paints, etc. Nonetheless, some disasters induced by metal powders are due to the lack of related safety information. In this study, we applied differential scanning calorimetry (DSC) and used thermal analysis software to evaluate the related thermal safety information, such as exothermic onset temperature (T{sub o}), peak of temperature (T{sub p}), and heat of reaction (ΔH). The nano iron powder experimental results of T{sub o} were 140–150 °C, 148–158 °C, and 141–149 °C for 15 nm, 35 nm, and 65 nm, respectively. The ΔH was larger than 3900 J/g, 5000 J/g, and 3900 J/g for 15 nm, 35 nm, and 65 nm, respectively. Safety information can benefit the relevant metal powders industries for preventing accidents from occurring.

Manche storage Centre. Information report on nuclear safety and radiation protection 2014. Annual report 2014

International Nuclear Information System (INIS)

2015-06-01

After a presentation of the Manche Storage Centre (CSM), the first French centre of surface storage of weakly and moderately radioactive wastes, of its history, its buildings and activities, of the multi-layer cover, of the water management system (installation, controls, sampling), this report then describes the measures related to nuclear safety (principles and objectives), the management of conventional and nuclear wastes produced by the Centre and its other environmental impacts. The follow up of the installations and of their effluents and releases are then addressed: origin, locations and results of radiological controls of rainfalls, of risky effluents, of underground waters, of rivers, impacts of the Centre on its environment (releases in the sea, in rivers, in sediments). The measures related to radiation protection are described: principles, staff dosimetry, and personnel safety. The next part presents the nuclear event scale (INES) and indicates that no incident occurred in 2014. Finally the actions related to public information and transparency are summarized. Recommendations of the CHSCT are reported at the end

Health and safety information program for hazardous materials

International Nuclear Information System (INIS)

O'Brien, M.P.; Fallon, N.J.; Kuehner, A.V.

1979-01-01

The system is used as a management tool in several safety and health programs. It is used to: trace the use of hazardous materials and to determine monitoring needs; inform the occupational physician of the potential health problems associated with materials ordered by a given individual; inform the fire and rescue group of hazardous materials in a given building; provide waste disposal recommendations to the hazardous waste management group; assist the hazardous materials shipping coordinator in identifying materials which are regulated by the Department of Transportation; and guide management decisions in the area of recognizing and rectifying unsafe conditions. The information system has been expanded from a manual effort to provide a brief description of health hazards of chemicals used at the lab to a computerized health and safety information system which serves the needs of all personnel who may encounter the material in the course of their work. The system has been designed to provide information needed to control the potential problems associated with a hazardous material up to the time that it is consumed in a given operation or is sent to the waste disposal facility

Opportunities for Using Building Information Modeling to Improve Worker Safety Performance

Directory of Open Access Journals (Sweden)

Kasim Alomari

2017-02-01

Full Text Available Building information modelling (BIM enables the creation of a digital representation of a designed facility combined with additional information about the project attributes, performance criteria, and construction process. Users of BIM tools point to the ability to visualize the final design along with the construction process as a beneficial feature of using BIM. Knowing the construction process in relationship to a facility’s design benefits both safety professionals when planning worker safety measures for a project and designers when creating a project’s design. Success in using BIM to enhance safety partly depends on the familiarity of project personnel with BIM tools and the extent to which the tools can be used to identify and eliminate safety hazards. In a separate, ongoing study, the authors investigated the connection between BIM and safety to document the opportunities, barriers, and impacts. Utilizing an on-line survey of project engineers who work for construction firms together with a comprehensive literature review, the study found those who use BIM feel that it aids in communication of project information and project delivery, both of which have been found to have positive impacts on construction site safety. Further, utilizing the survey results, the authors apply the binary logistic regression econometric framework to better understand the factors that lead to safety professionals believing that BIM increases safety in the work place. In addition, according to the survey results, a large percentage of the engineers who use BIM feel that ultimately it helps to eliminate safety hazards and improve worker safety. The study findings suggest that improvements in safety performance across the construction industry may be due in part to increased use of BIM in the construction industry.

The challenge of effectively communicating patient safety information.

Science.gov (United States)

Hugman, Bruce; Edwards, I Ralph

2006-07-01

Rational use of drugs and patient safety are seriously compromised by a lack of good information, education and effective communication at all stages of drug development and use. From animal trials through to dispensing, there are misconceptions and opportunities for error which current methods of drug information communication do not adequately address: they do not provide those responsible for prescribing and dispensing drugs with the data and information they need to pass on complex and often changing messages to patients and the public. The incidence of adverse reactions due to the way drugs are used; the variable impact of regulatory guidelines and warnings on prescribing behaviour; drug scares and crises suggest a great gap between the ideals of the safe use of medicines and the reality in homes, clinics and hospitals around the world. To address these challenges, the authors review the several levels at which safety information is generated and communicated, and examine how, at each stage, the content and its significance, and the method of communication can be improved.

Progress towards a convention on the safe management of radioactive waste

International Nuclear Information System (INIS)

Webb, G.A.M.; Jankowitsch, O.

1996-01-01

The Convention on Nuclear Safety was prepared during the period 1992 to 1994 and after consideration by a diplomatic conference in June 1994 was opened for signature at the general conference of the IAEA in September 1994. The matter of the safety of radioactive waste was discussed many times during the development of the convention but it was eventually decided to restrict the coverage to matters concerned with nuclear safety of land-based civil nuclear power plants and those aspects of radioactive waste management directly connected with and carried out on the same site as the power plant. In the preamble to the convention, however, item (ix) affirms 'the need to begin promptly the development of an international convention on the safety of radioactive waste management as soon as the ongoing process to develop waste management safety fundamentals has resulted in broad international agreement'. In September 1994, the general conference of the IAEA also passed a resolution inviting the board of governors and the director general to commence preparations for a convention on the safety of radioactive waste management. The director general therefore organized a preparatory meeting of experts from member states to discuss the basic concepts and the possible scope of such a convention and to examine working methods and the procedures for its preparation. This meeting which took place in February 1995 prepared a paper entitled 'Inventory of Issues Raised' and proposed that the appropriate mechanism would be the setting up of an open-ended group of legal and technical experts to prepare the convention. The Safety Series document at the fundamentals level on the principles of radioactive waste management was approved by the Board of Governors in March 1995 and all the initial preconditions for starting work on the convention were then fulfilled. (author)

Information need about the safety of the final disposal of nuclear waste. Information receiver's views in Eurajoki, Kuhmo and Aeaenekoski municipalities

International Nuclear Information System (INIS)

Hautakangas, H.

1997-03-01

The study analyses the public's information need about the safety issues related to the final disposal of spent nuclear fuel generated by the Finnish nuclear power stations. Locals in three municipalities that are studied as possible sites for final disposal were interviewed for the study. Earlier studies made in Finland had indicated that the public's knowledge about safety issues related to the final disposal was almost opposite to the findings of the natural sciences. Also, the public had expressed a wish to receive more information from the safety authority, the Finnish Centre for Radiation and Nuclear Safety (STUK). This study therefore had two basic objectives: To find out what kind of safety information the locals need and what the safety authority's role could be in providing information. The main results show interest and need especially for information concerning the disposal phases taking place on the ground level, such as nuclear waste transportation and encapsulation. Also, the interviews show a clear need and desire for an impartial actor such as STUK in the information and communication process. (author) (107 refs.)

Third National Report on compliance with the Joint Convention Obligations

International Nuclear Information System (INIS)

2008-09-01

The Joint Convention on the Safety of Spent Fuel Management and the Safety of Radioactive Waste Management, hereinafter referred to as the 'Joint Convention', is the result of international discussions that followed the adoption of the Convention on Nuclear Safety, in 1994. France signed the Joint Convention at the General Conference of the International Atomic Energy Agency (IAEA) held on 29 September 1997, the very first day the Joint Convention was opened for signature. She approved it on 22 February 2000 and filed the corresponding instruments with the IAEA on 27 April 2000. The Joint Convention entered into force on 18 June 2001. For many years, France has been taking an active part in the pursuit of international actions to reinforce nuclear safety and considers the Joint Convention to be a key step in that direction. The fields covered by the Joint Convention have long been part of the French approach to nuclear safety. This report is the third one of its kind. It is published in accordance with Article 32 of the Joint Convention and presents the measures taken by France to meet each of her obligations set out in the Convention. The facilities and the radioactive materials covered by this Convention are quite diversified in nature and are controlled in France by different regulatory authorities. Above a specific threshold of radioactive content, a facility is referred to as a 'basic nuclear facility' (installation nucleaire de base - INB) and placed under the control of the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). Below that threshold and provided that the facility involved is subject to the nomenclature of classified facilities for other purposes than their radioactive materials, any facility may be considered as a 'classified facility on environmental-protection grounds' (installation classee pour la protection de l'environnement - ICPE) and placed under the control of the Ministry for the Environment. Facilities that contain only

Exchange of information between nuclear safety authorities: Policy of the French regulator

International Nuclear Information System (INIS)

Asty, Michel

2000-01-01

Full text: The decree setting up the Nuclear Safety Authority in 1973 entrusted it with international assignments whose objectives are still valid: - develop exchanges of information with foreign counterparts on regulatory systems and practices, on problems encountered in the nuclear safety field and on provisions made, with a view to enhancing its approach, and - becoming better acquainted with the actual operating practice of these Safety Authorities from which lessons could be learned for its own working procedures; - improving its position in the technical discussions with the French operators, since its arguments would be strengthened by practical knowledge of conditions abroad; - make known and explain the French approach and practices in the nuclear safety field and provide information on measures taken to deal with the problems encountered. This approach has several objectives: - promote the circulation of information on French positions on certain issues, such as very low level waste, for instance; - assist some countries wishing to create or modify their Nuclear Safety Authority, such as countries of the former USSR, the Central and Eastern European countries, and emerging countries on other continents; - help, when requested, foreign Safety Authorities required to issue permits for nuclear equipment of French origin; - provide the countries concerned with all relevant information on French nuclear installations located near their frontiers. Examples are given on the way the French Nuclear Safety Authority implements these objectives. (author)

Impediments for the application of risk-informed decision making in nuclear safety

International Nuclear Information System (INIS)

Hahn, L.

2001-01-01

A broad application of risk-informed decision making in the regulation of safety of nuclear power plants is hindered by the lack of quantitative risk and safety standards as well as of precise instruments to demonstrate an appropriate safety. An additional severe problem is associated with the difficulty to harmonize deterministic design requirements and probabilistic safety assessment. The problem is strengthened by the vulnerability of PSA for subjective influences and the potential of misuse. Beside this scepticism the nuclear community is encouraged to intensify the efforts to improve the quality standards for probabilistic safety assessments and their quality assurance. A prerequisite for reliable risk-informed decision making processes is also a well-defined and transparent relationship between deterministic and probabilistic safety approaches. (author)

Answers to questions on National Report of the Slovak Republic. Compiled according to the terms of the joint convention on the safety of spent fuel management and on the safety of radioactive waste management. October 2003

International Nuclear Information System (INIS)

2003-10-01

Slovakia is pleased to present to the State Parties of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management the Answers to questions received on the National Report of the Slovak Republic compiled according to the terms of the Joint Convention (April 2003). Slovakia is ready to provide additional explanations to these Answers during the 1 st Review Meeting. In the Annexes the 254/1994 Coll. LL. Act of the National Council of the Slovak Republic of 25 August 1994 on State Fund of Decommissioning of Nuclear Installations and Handling of Spent Nuclear Fuels and Nuclear Wastes is included

46 CFR 91.60-40 - Duration of Convention certificates.

Science.gov (United States)

2010-10-01

... VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea... period of not more than 60 months. (1) A Cargo Ship Safety Construction Certificate. (2) A Cargo Ship Safety Equipment Certificate. (3) A Safety Management Certificate. (4) A Cargo Ship Safety Radio...

Feedback from incident reporting: information and action to improve patient safety.

Science.gov (United States)

Benn, J; Koutantji, M; Wallace, L; Spurgeon, P; Rejman, M; Healey, A; Vincent, C

2009-02-01

Effective feedback from incident reporting systems in healthcare is essential if organisations are to learn from failures in the delivery of care. Despite the wide-scale development and implementation of incident reporting in healthcare, studies in the UK suggest that information concerning system vulnerabilities could be better applied to improve operational safety within organisations. In this article, the findings and implications of research to identify forms of effective feedback from incident reporting are discussed, to promote best practices in this area. The research comprised a mixed methods review to investigate mechanisms of effective feedback for healthcare, drawing upon experience within established reporting programmes in high-risk industry and transport domains. Systematic searches of published literature were undertaken, and 23 case studies describing incident reporting programmes with feedback were identified for analysis from the international healthcare literature. Semistructured interviews were undertaken with 19 subject matter experts across a range of domains, including: civil aviation, maritime, energy, rail, offshore production and healthcare. In analysis, qualitative information from several sources was synthesised into practical requirements for developing effective feedback in healthcare. Both action and information feedback mechanisms were identified, serving safety awareness, improvement and motivational functions. The provision of actionable feedback that visibly improved systems was highlighted as important in promoting future reporting. Fifteen requirements for the design of effective feedback systems were identified, concerning: the role of leadership, the credibility and content of information, effective dissemination channels, the capacity for rapid action and the need for feedback at all levels of the organisation, among others. Above all, the safety-feedback cycle must be closed by ensuring that reporting, analysis and

'BeSAFE', effect-evaluation of internet-based, tailored safety information combined with personal counselling on parents' child safety behaviours: study design of a randomized controlled trial

Directory of Open Access Journals (Sweden)

van Beeck Eduard F

2010-08-01

Full Text Available Abstract Background Injuries in or around the home are the most important cause of death among children aged 0-4 years old. It is also a major source of morbidity and loss of quality of life. In order to reduce the number of injuries, the Consumer Safety Institute introduced the use of Safety Information Leaflets in the Netherlands to provide safety education to parents of children aged 0-4 years. Despite current safety education, necessary safety behaviours are still not taken by a large number of parents, causing unnecessary risk of injury among young children. In an earlier study an E-health module with internet-based, tailored safety information was developed and applied. It concerns an advice for parents on safety behaviours in their homes regarding their child. The aim of this study is to evaluate the effect of this safety information combined with personal counselling on parents' child safety behaviours. Methods/Design Parents who are eligible for the regular well-child visit with their child at child age 5-8 months are invited to participate in this study. Participating parents are randomized into one of two groups: 1 internet-based, tailored safety information combined with personal counselling (intervention group, or 2 personal counselling using the Safety Information Leaflets of the Consumer Safety Institute in the Netherlands for children aged 12 to 24 months (control group. All parents receive safety information on safety topics regarding the prevention of falling, poisoning, drowning and burning. Parents of the intervention group will access the internet-based, tailored safety information module when their child is approximately 10 months old. After completion of the assessment questions, the program compiles a tailored safety advice. The parents are asked to devise and inscribe a personal implementation intention. During the next well-child visit, the Child Health Clinic professional will discuss this tailored safety information

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)

Quantifying Safety Margin Using the Risk-Informed Safety Margin Characterization (RISMC)

Energy Technology Data Exchange (ETDEWEB)

Grabaskas, David; Bucknor, Matthew; Brunett, Acacia; Nakayama, Marvin

2015-04-26

The Risk-Informed Safety Margin Characterization (RISMC), developed by Idaho National Laboratory as part of the Light-Water Reactor Sustainability Project, utilizes a probabilistic safety margin comparison between a load and capacity distribution, rather than a deterministic comparison between two values, as is usually done in best-estimate plus uncertainty analyses. The goal is to determine the failure probability, or in other words, the probability of the system load equaling or exceeding the system capacity. While this method has been used in pilot studies, there has been little work conducted investigating the statistical significance of the resulting failure probability. In particular, it is difficult to determine how many simulations are necessary to properly characterize the failure probability. This work uses classical (frequentist) statistics and confidence intervals to examine the impact in statistical accuracy when the number of simulations is varied. Two methods are proposed to establish confidence intervals related to the failure probability established using a RISMC analysis. The confidence interval provides information about the statistical accuracy of the method utilized to explore the uncertainty space, and offers a quantitative method to gauge the increase in statistical accuracy due to performing additional simulations.

Use of information technologies to contribute for optimizing the safety radiation management in Cuba

International Nuclear Information System (INIS)

Valdes Ramos, M.; Prendes Alonso, M.; Hernandez Saiz, A.; Manzano de Armas, J.

2013-01-01

This paper presents the results achieved in Cuba, with the development of a group of information management tools to implement radiation safety systemic and proactive approaches to safety and ICT supported. These tools were designed for different organisms with responsibility for the security at the country level, to the regulatory authority, for user entities, for individual monitoring services and other radiation protection services. It describes the philosophy of information management model used, the characteristics of the developed tools and their integration, the work performed for the homogenization of information available and the ability to capture and deliver data at different levels in decision making. The tools developed are based on the use of variables and indicators of importance to the safety and the systemic approach adopted allows to facilitate the optimization process for supervision of safety practices as well as contribute to the management of knowledge in radiation safety, through a synergistic combination of process data, information, information management systems, and the creative and innovative radiation safety experts

THE FORMATION OF THE CONTOUR OF THE DOCUMENTED AND REAL FLIGHT SAFETY IN THE SYSTEM OF THE INFORMATION PROVISION OF SAFETY OF FLIGHTS

Directory of Open Access Journals (Sweden)

B. I. Bachkalo

2015-01-01

Full Text Available The article discusses the principles and mechanisms of formation of the contour of the real safety of flights and contour of the documented safety, allowing us to obtain information to control fligh safety. The proposed approach can be used in the algorithms of active on-board flight safety management system for the implementation of information support to the crew in flight and automatic control of flight safety.

75 FR 36615 - Pipeline Safety: Information Collection Gas Distribution Annual Report Form

Science.gov (United States)

2010-06-28

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part 192 [Docket No. PHMSA-RSPA-2004-19854] Pipeline Safety: Information Collection Gas Distribution Annual Report Form AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), DOT. ACTION: Request...

Patient-Reported Safety Information: A Renaissance of Pharmacovigilance?

Science.gov (United States)

Härmark, Linda; Raine, June; Leufkens, Hubert; Edwards, I Ralph; Moretti, Ugo; Sarinic, Viola Macolic; Kant, Agnes

2016-10-01

The role of patients as key contributors in pharmacovigilance was acknowledged in the new EU pharmacovigilance legislation. This contains several efforts to increase the involvement of the general public, including making patient adverse drug reaction (ADR) reporting systems mandatory. Three years have passed since the legislation was introduced and the key question is: does pharmacovigilance yet make optimal use of patient-reported safety information? Independent research has shown beyond doubt that patients make an important contribution to pharmacovigilance signal detection. Patient reports provide first-hand information about the suspected ADR and the circumstances under which it occurred, including medication errors, quality failures, and 'near misses'. Patient-reported safety information leads to a better understanding of the patient's experiences of the ADR. Patients are better at explaining the nature, personal significance and consequences of ADRs than healthcare professionals' reports on similar associations and they give more detailed information regarding quality of life including psychological effects and effects on everyday tasks. Current methods used in pharmacovigilance need to optimise use of the information reported from patients. To make the most of information from patients, the systems we use for collecting, coding and recording patient-reported information and the methodologies applied for signal detection and assessment need to be further developed, such as a patient-specific form, development of a severity grading and evolution of the database structure and the signal detection methods applied. It is time for a renaissance of pharmacovigilance.

Report on probabilistic safety assessment (PSA) quality assurance in utilization of risk information

International Nuclear Information System (INIS)

2006-12-01

Recently in Japan, introduction of nuclear safety regulations using risk information such as probabilistic safety assessment (PSA) has been considered and utilization of risk information in the rational and practical measures on safety assurance has made a progress to start with the operation or inspection area. The report compiled results of investigation and studies of PSA quality assurance in risk-informed activities in the USA. Relevant regulatory guide and standard review plan as well as issues and recommendations were reviewed for technical adequacy and advancement of probabilistic risk assessment technology in risk-informed decision making. Useful and important information to be referred as issues in PSA quality assurance was identified. (T. Tanaka)

High committee for nuclear safety transparency and information. July 1, 2009 meeting

International Nuclear Information System (INIS)

2009-07-01

The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 5 main points: 1 - radioactive waste management: status and steps of the June 28, 2006 law, ANDRA's projects of deep geologic disposal for long living/high-medium activity wastes and of low depth disposal for long living/low activity wastes, French nuclear safety authority (ASN) opinion about the sites choice, implementation of article 10 of the June 28, 2006 law relative to public information; 2 - progress of the working groups' works on transparency and secrecy, on the development of a communication scale, and on the creation of an Internet portal for the radio-ecological follow-up of nuclear sites; 3 - comments of the ASN's report on the nuclear safety and radiation protection in France in 2008; 4 - procedure of management of the radio-physicists shortage in order to warrant the patients' safety and information; 5 - miscellaneous points: project of European directive on nuclear safety, organisation of a visit day onboard of a ship for nuclear materials transportation, comments about the by-law from May 5, 2009, relative to the exemption to informing consumers about the addition of radionuclides to consumption and construction products. (J.S.)

numerical assessment of conventional regulation effectiveness

African Journals Online (AJOL)

Benkoussas B, Djedjig R, and Vauquelin O

2016-05-01

May 1, 2016 ... The effectiveness of an underground smoke control system mainly depends on fire safety engineering that is ... In the same context, this work aims firstly, at investigating the effectiveness of conventional regulation applied to .... 5a). Fig.4. Station smoke behavior for conventional ventilation regulation. Fig.5a.

Risk-informed decision making a keystone in advanced safety assessment

International Nuclear Information System (INIS)

Reinhart, M.

2007-01-01

Probabilistic Safety Assessment (PSA) has provided extremely valuable complementary insight, perspective, comprehension, and balance to deterministic nuclear reactor safety assessment. This integrated approach of risk-informed management and decision making has been called Risk-Informed Decision Making (RIDM). RIDM provides enhanced safety, reliability, operational flexibility, reduced radiological exposure, and improved fiscal economy. Applications of RIDM continuously increase. Current applications are in the areas of design, construction, licensing, operations, and security. Operational phase safety applications include the following: technical specifications improvement, risk-monitors and configuration control, maintenance planning, outage planning and management, in-service inspection, inservice testing, graded quality assurance, reactor oversight and inspection, inspection finding significance determination, operational events assessment, and rulemaking. Interestingly there is a significant spectrum of approaches, methods, programs, controls, data bases, and standards. The quest of many is to assimilate the full compliment of PSA and RIDM information and to achieve a balanced international harmony. The goal is to focus the best of the best, so to speak, for the benefit of all. Accordingly, this presentation will address the principles, benefits, and applications of RIDM. It will also address some of the challenges and areas to improve. Finally it will highlight efforts by the IAEA and others to capture the international thinking, experience, successes, challenges, and lessons in RIDM. (authors)

10 CFR 52.157 - Contents of applications; technical information in final safety analysis report.

Science.gov (United States)

2010-01-01

...; technical information in final safety analysis report. The application must contain a final safety analysis... 10 Energy 2 2010-01-01 2010-01-01 false Contents of applications; technical information in final safety analysis report. 52.157 Section 52.157 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES...

10 CFR 52.79 - Contents of applications; technical information in final safety analysis report.

Science.gov (United States)

2010-01-01

...; technical information in final safety analysis report. (a) The application must contain a final safety... 10 Energy 2 2010-01-01 2010-01-01 false Contents of applications; technical information in final safety analysis report. 52.79 Section 52.79 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES...

Risk-informed approaches to assess ecological safety of facilities with radioactive waste

International Nuclear Information System (INIS)

Vashchenko, V.N.; Zlochevskij, V.V.; Skalozubov, V.I.

2011-01-01

Ingenious risk-informed methods to assess ecological safety of facilities with radioactive waste are proposed in the paper. Probabilistic norms on lethal outcomes and reliability of safety barriers are used as safety criteria. Based on the probability measures, it is established that ecological safety conditions are met for the standard criterion of lethal outcomes

Factors shaping effective utilization of health information technology in urban safety-net clinics.

Science.gov (United States)

George, Sheba; Garth, Belinda; Fish, Allison; Baker, Richard

2013-09-01

Urban safety-net clinics are considered prime targets for the adoption of health information technology innovations; however, little is known about their utilization in such safety-net settings. Current scholarship provides limited guidance on the implementation of health information technology into safety-net settings as it typically assumes that adopting institutions have sufficient basic resources. This study addresses this gap by exploring the unique challenges urban resource-poor safety-net clinics must consider when adopting and utilizing health information technology. In-depth interviews (N = 15) were used with key stakeholders (clinic chief executive officers, medical directors, nursing directors, chief financial officers, and information technology directors) from staff at four clinics to explore (a) nonhealth information technology-related clinic needs, (b) how health information technology may provide solutions, and (c) perceptions of and experiences with health information technology. Participants identified several challenges, some of which appear amenable to health information technology solutions. Also identified were requirements for effective utilization of health information technology including physical infrastructural improvements, funding for equipment/training, creation of user groups to share health information technology knowledge/experiences, and specially tailored electronic billing guidelines. We found that despite the potential benefit that can be derived from health information technologies, the unplanned and uninformed introduction of these tools into these settings might actually create more problems than are solved. From these data, we were able to identify a set of factors that should be considered when integrating health information technology into the existing workflows of low-resourced urban safety-net clinics in order to maximize their utilization and enhance the quality of health care in such settings.

Information Management of Health and Safety at the Tarkwa Mine of ...

African Journals Online (AJOL)

Michael

2016-06-01

Jun 1, 2016 ... Information Management of Health and Safety at the Tarkwa ... heap leach technology. ... the quality of information was assessed using the content of information ..... managing library users' expectations; and reference service.

Nuclear power safety

International Nuclear Information System (INIS)

1991-11-01

This paper reports that since the Chernobyl nuclear plant accident in 1986, over 70 of the International Atomic Energy Agency's 112 member states have adopted two conventions to enhance international cooperation by providing timely notification of an accident and emergency assistance. The Agency and other international organizations also developed programs to improve nuclear power plant safety and minimize dangers from radioactive contamination. Despite meaningful improvements, some of the measures have limitations, and serious nuclear safety problems remain in the design and operation of the older, Soviet-designed nuclear power plants. The Agency's ability to select reactors under its operational safety review program is limited. Also, information on the extent and seriousness of safety-related incidents at reactors in foreign countries is not publicly available. No agreements exist among nuclear power countries to make compliance with an nuclear safety standards or principles mandatory. Currently, adherence to international safety standards or principles is voluntary and nonbinding. Some states support the concept of mandatory compliance, but others, including the United States, believe that mandatory compliance infringes on national sovereignty and that the responsibility for nuclear reactor safety remains with each nation

Methods of Certification tests PLC-Networks in Compliance Safety Information

Directory of Open Access Journals (Sweden)

A. A. Balaev

2011-12-01

Full Text Available The aim of this research was description of the methodology of the audit plc-network to meet the requirements of information security. The technique is based on the provisions of the guidance documents and model FSTEC Russia test object methods of information on safety information.

Measuring and improving patient safety through health information technology: The Health IT Safety Framework.

Science.gov (United States)

Singh, Hardeep; Sittig, Dean F

2016-04-01

Health information technology (health IT) has potential to improve patient safety but its implementation and use has led to unintended consequences and new safety concerns. A key challenge to improving safety in health IT-enabled healthcare systems is to develop valid, feasible strategies to measure safety concerns at the intersection of health IT and patient safety. In response to the fundamental conceptual and methodological gaps related to both defining and measuring health IT-related patient safety, we propose a new framework, the Health IT Safety (HITS) measurement framework, to provide a conceptual foundation for health IT-related patient safety measurement, monitoring, and improvement. The HITS framework follows both Continuous Quality Improvement (CQI) and sociotechnical approaches and calls for new measures and measurement activities to address safety concerns in three related domains: 1) concerns that are unique and specific to technology (e.g., to address unsafe health IT related to unavailable or malfunctioning hardware or software); 2) concerns created by the failure to use health IT appropriately or by misuse of health IT (e.g. to reduce nuisance alerts in the electronic health record (EHR)), and 3) the use of health IT to monitor risks, health care processes and outcomes and identify potential safety concerns before they can harm patients (e.g. use EHR-based algorithms to identify patients at risk for medication errors or care delays). The framework proposes to integrate both retrospective and prospective measurement of HIT safety with an organization's existing clinical risk management and safety programs. It aims to facilitate organizational learning, comprehensive 360 degree assessment of HIT safety that includes vendor involvement, refinement of measurement tools and strategies, and shared responsibility to identify problems and implement solutions. A long term framework goal is to enable rigorous measurement that helps achieve the safety

29 CFR 1960.12 - Dissemination of occupational safety and health program information.

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Dissemination of occupational safety and health program... OCCUPATIONAL SAFETY AND HEALTH PROGRAMS AND RELATED MATTERS Administration § 1960.12 Dissemination of occupational safety and health program information. (a) Copies of the Act, Executive Order 12196, program...

Technical Site Information: Planning group of the Directorate and Conventional Construction Division

International Nuclear Information System (INIS)

1993-11-01

This document presents the technical site information for the Superconducting Super Collider project. The Ellis County, Texas site was selected by the Department of Energy in 1989. After assembling the initial staff at temporary facilities in Dallas, the SSC Laboratory began site-specific design work. The resulting design for the SSC accelerators, experimental areas, and laboratory facilities were described in the Site-Specific Conceptual Design Report of July 1990. Since then, design specifications for the technical components and conventional facilities have been formulated. In fact, a very significant amount of surface and underground construction has been initiated and many buildings have been completed. Testing of prototypes for most technical components is advanced. The construction phase of the SSC project is approximately 20% complete. At this time, it is appropriate to capture the conventional design work which has taken place since 1990. This documents records regional and physical information used in site studies, summarizes the site studies for conventional facilities, and presents site layouts for buildings and utilities as they would have been at the end of the construction project. As such, this documents summarizes and complements the work of many groups in the SSC laboratory, the Texas National Research Laboratory Commission (TNRLC), and several subcontractors to the SSC project. The document contains extensive references to their work contained in other drafts and final reports. In particular, it borrows heavily from the Site Development Plan (released in draft form in January, 1992) which has, to date, guided aspects of site development

Technical Site Information: Planning group of the Directorate and Conventional Construction Division

Energy Technology Data Exchange (ETDEWEB)

NONE

1993-11-01

This document presents the technical site information for the Superconducting Super Collider project. The Ellis County, Texas site was selected by the Department of Energy in 1989. After assembling the initial staff at temporary facilities in Dallas, the SSC Laboratory began site-specific design work. The resulting design for the SSC accelerators, experimental areas, and laboratory facilities were described in the Site-Specific Conceptual Design Report of July 1990. Since then, design specifications for the technical components and conventional facilities have been formulated. In fact, a very significant amount of surface and underground construction has been initiated and many buildings have been completed. Testing of prototypes for most technical components is advanced. The construction phase of the SSC project is approximately 20% complete. At this time, it is appropriate to capture the conventional design work which has taken place since 1990. This documents records regional and physical information used in site studies, summarizes the site studies for conventional facilities, and presents site layouts for buildings and utilities as they would have been at the end of the construction project. As such, this documents summarizes and complements the work of many groups in the SSC laboratory, the Texas National Research Laboratory Commission (TNRLC), and several subcontractors to the SSC project. The document contains extensive references to their work contained in other drafts and final reports. In particular, it borrows heavily from the Site Development Plan (released in draft form in January, 1992) which has, to date, guided aspects of site development.

Thirteenth water reactor safety research information meeting: proceedings Volume 1

International Nuclear Information System (INIS)

Weiss, A.J.

1986-02-01

This six-volume report contains 151 papers out of the 178 that were presented at the Thirteenth Water Reactor Safety Research Information Meeting held at the National Bureau of Standards, Gaithersburg, Maryland, during the week of October 22-25, 1985. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included thirty-one different papers presented by researchers from Japan, Canada and eight European countries. The title of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. This volume presents information on: risk analysis PRA application; severe accident sequence analysis; risk analysis/dependent failure analysis; and industry safety research

Guidelines regarding National Reports under the Convention on Nuclear Safety

International Nuclear Information System (INIS)

1999-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties regarding material which it may be useful to include in the national reports required by Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention

Guidelines regarding national reports under the convention on nuclear safety

International Nuclear Information System (INIS)

1998-01-01

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties regarding material which it may be useful to include in the national reports required by Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention

Guidelines regarding National Reports under the Convention on Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-10-15

These guidelines, established by the Contracting Parties pursuant to Article 22 of the Convention, are intended to be read in conjunction with the text of the Convention. Their purpose is to provide guidance to the Contracting Parties regarding material which it may be useful to include in the national reports required by Article 5 and thereby to facilitate the most efficient review of implementation by the Contracting Parties of their obligations under the Convention.

The European single market of energy faced with conventional supply safety concepts

International Nuclear Information System (INIS)

Belyi, A.

2004-01-01

By analysing the context of the creation of the Single Energy Market, this article tries to understand the logic behind the coexistence of two energy safety concepts: (1) the financial gains of international trading; (2) the protection against supply shortage risks using domestic self-sufficiency policies. Both concepts are based on an informative context conditioned by the two crises, which mainly impact the security perceptions of today: the oil crisis in the seventies and the Californian crisis in 2001. They are based on opposite factors: anti-market behaviour in the first case and excessive competition in the second case. The nature of liberalization, of the relation-ship with non-EU producing countries and the perception of the dangers are inherent to such an informative context. (author)

U.S. Continuing Involvement with the Joint Convention

International Nuclear Information System (INIS)

Stewart, L.; Tonkay, D.; Regnier, E.; Schultheisz, D.; Gnugnoli, G.

2009-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (Joint Convention) is an international convention, under the auspices of the International Atomic Energy Agency (IAEA). It is a companion to a suite of international conventions on nuclear safety and physical security, which serve to promote a global culture for the safe use of radioactive materials. The Joint Convention is an official international treaty, and as such, there are obligations on the part of the United States. Those nations having ratified the Joint Convention are designated as 'Contracting Parties.' Nations that are not IAEA Member States may also become Contracting Parties to the Joint Convention, although none has done so. The primary obligations are threefold. The first is to prepare a national report, which addresses the national safety program in radioactive waste management, spent nuclear fuel management, and disused sealed sources. As the U.S. prepares a national report, other Contracting Parties to the Joint Convention also prepare their national reports, which leads to the second obligation on the part of the Contracting Parties. This is the obligation to review other countries' national reports. The last specific obligation is to actively participate in the triennial peer review meeting, referred to as the Review Meeting of the Contracting Parties. The U.S. ratified the Joint Convention in 2003, just prior to the First Review Meeting of the Contracting Parties, and has participated fully therein in the ensuing Review Meetings. Because of the benefits in active participation, it is important for the U.S. to maintain its leadership role in promoting its ratification in the global setting, as well as in more focused regions. Because of the important benefits associated with active participation, the U.S. has strongly supported a Regional Conference Initiative outreach program to increase membership. To launch the Initiative, the U

Patterns of patient safety culture: a complexity and arts-informed project of knowledge translation.

Science.gov (United States)

Mitchell, Gail J; Tregunno, Deborah; Gray, Julia; Ginsberg, Liane

2011-01-01

The purpose of this paper is to describe patterns of patient safety culture that emerged from an innovative collaboration among health services researchers and fine arts colleagues. The group engaged in an arts-informed knowledge translation project to produce a dramatic expression of patient safety culture research for inclusion in a symposium. Scholars have called for a deeper understanding of the complex interrelationships among structure, process and outcomes relating to patient safety. Four patterns of patient safety culture--blinding familiarity, unyielding determination, illusion of control and dismissive urgency--are described with respect to how they informed creation of an arts-informed project for knowledge translation.

Health Information Technology in Healthcare Quality and Patient Safety: Literature Review.

Science.gov (United States)

Feldman, Sue S; Buchalter, Scott; Hayes, Leslie W

2018-06-04

The area of healthcare quality and patient safety is starting to use health information technology to prevent reportable events, identify them before they become issues, and act on events that are thought to be unavoidable. As healthcare organizations begin to explore the use of health information technology in this realm, it is often unclear where fiscal and human efforts should be focused. The purpose of this study was to provide a foundation for understanding where to focus health information technology fiscal and human resources as well as expectations for the use of health information technology in healthcare quality and patient safety. A literature review was conducted to identify peer-reviewed publications reporting on the actual use of health information technology in healthcare quality and patient safety. Inductive thematic analysis with open coding was used to categorize a total of 41 studies. Three pre-set categories were used: prevention, identification, and action. Three additional categories were formed through coding: challenges, outcomes, and location. This study identifies five main categories across seven study settings. A majority of the studies used health IT for identification and prevention of healthcare quality and patient safety issues. In this realm, alerts, clinical decision support, and customized health IT solutions were most often implemented. Implementation, interface design, and culture were most often noted as challenges. This study provides valuable information as organizations determine where they stand to get the most "bang for their buck" relative to health IT for quality and patient safety. Knowing what implementations are being effectivity used by other organizations helps with fiscal and human resource planning as well as managing expectations relative to cost, scope, and outcomes. The findings from this scan of the literature suggest that having organizational champion leaders that can shepherd implementation, impact culture

Information security as part of the nuclear safety culture

Energy Technology Data Exchange (ETDEWEB)

Sitnica, A., E-mail: demetrkj@westinghouse.com [Westinghouse Electric Co., 1000 Westinghouse Drive, Cranberry Township, PA 16066 (United States)

2016-09-15

No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

Information security as part of the nuclear safety culture

International Nuclear Information System (INIS)

Sitnica, A.

2016-09-01

No industry, organization, individual or even the government is immune to the information security risks which are associated with nuclear power. It can no longer be ignored, delayed or treated as unimportant. Nuclear safety is paramount to our industry, and cyber security must be woven into the fabric of our safety culture in order to succeed. Achieving this in an environment which has remained relatively unchanged and conservative prior to digitalisation demands a shift in behavior and culture. (Author)

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

International Nuclear Information System (INIS)

Sun Haipeng; Liu Zhijun; Li Tianshu

2013-01-01

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

Finding Business Information on the "Invisible Web": Search Utilities vs. Conventional Search Engines.

Science.gov (United States)

Darrah, Brenda

Researchers for small businesses, which may have no access to expensive databases or market research reports, must often rely on information found on the Internet, which can be difficult to find. Although current conventional Internet search engines are now able to index over on billion documents, there are many more documents existing in…

Food Safety and Nutrition Information for Kids and Teens

Science.gov (United States)

... Vaccines, Blood & Biologics Animal & Veterinary Cosmetics Tobacco Products Food Home Food Resources for You Consumers Kids & Teens ... More sharing options Linkedin Pin it Email Print Food Safety & Nutrition Information for Kids and Teens Fun & ...

The role of nuclear law in nuclear safety after Fukushima

International Nuclear Information System (INIS)

Cardozo, Diva E. Puig

2013-01-01

The paper contains the following topics: nuclear law, origin and evolution, role of the legal instruments on nuclear safety, nuclear safety the impact of major nuclear accidents: Chernobyl and Fukushima. The response of the nuclear law post Fukushima. Safety and security. International framework for nuclear safety: nuclear convention joint convention on safety on spent fuel management and on the safety of radioactive waste management. The Fukushima World Conference on Nuclear Safety. Convention on Prompt Notification and Assistance in case of a Nuclear Accident or Radiological Emergency. Plan of Action for Nuclear Safety. IAEA recommendations for the safety transport of radioactive material. International framework for nuclear security. Convention on the Physical Protection of Nuclear Materials. International Convention for the Suppression of Acts Against Nuclear Terrorism. Resolution No. 1540 of the Security Council of United Nations (2004). Measures to strengthen international safety. Code of conduct on the safety research reactor

Twenty-First Water Reaction Safety Information Meeting

International Nuclear Information System (INIS)

Monteleone, S.

1994-04-01

This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25--27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Individual papers have been cataloged separately. This document, Volume 2, presents papers on severe accident research

Twenty-First Water Reactor Safety Information Meeting

International Nuclear Information System (INIS)

Monteleone, S.

1994-04-01

This three-volume report contains 90 papers out of the 102 that were presented at the Twenty-First Water Reactor Safety Information Meeting held at the Bethesda Marriott Hotel, Bethesda, Maryland, during the week of October 25-27, 1993. The papers are printed in the order of their presentation in each session and describe progress and results of programs in nuclear safety research conducted in this country and abroad. Foreign participation in the meeting included papers presented by researchers from France, Germany, Japan, Russia, Switzerland, Taiwan, and United Kingdom. The titles of the papers and the names of the authors have been updated and may differ from those that appeared in the final program of the meeting. Selected papers were indexed separately for inclusion in the Energy Science and Technology Database

Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

Energy Technology Data Exchange (ETDEWEB)

Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of); Byun, Jaehyung; Seo, Jonghwan [Dong-A Univ., Busan (Korea, Republic of)

2013-05-15

There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

Standardized System of Nuclear Safety Information for the Promotion of Transparency and Openness

International Nuclear Information System (INIS)

Lee, Gihyung; Kim, Sanghyun; Lee, Gyehwi; Yoon, Yeonhwa; Song, Song Hyerim; Jeong, Jina; Byun, Jaehyung; Seo, Jonghwan

2013-01-01

There has been an increasing emphasis on the need for increased disclosure of information through the home page of the Korea Institute of Nuclear Safety (KINS), responsible for nuclear safety regulations, and the Nuclear Safety Information Center (NSIC) to enhance public understanding of nuclear safety. However, due to the dazzled structure of the existing KINS and NSIC home pages, improvements in accessibility and convenience are necessary. At the same time, content standardization is required to increase operational efficiency and provide coherent information. In this study, the Delphi method was used to select the major contents to make available on the home page as well as the main user base definition for the home page layout development. Also, internal and external expert groups were created to conduct AHP (Analytic Hierarchy Process) analysis and develop the comparative analysis items for the U. S. Nuclear Regulatory Commission(NRC)/KINS/NSIC home pages. Afterwards, problems and points of improvements for the home page system, design, and profile were derived using heuristic analysis. The implications arising from the Delphi analysis results were applied to the home page layout. In the nuclear safety information standardized system construction process, the comparative analysis conducted using the AHP and heuristic analyses of the NRC home page resulted in deriving improvements for the Guidance, Organization, and Trustworthy items of the KINS/NSIC home page. Furthermore, through the Delphi analysis, a clear purpose and core values were set for the KINS web site, and the needs of the main user base were identified. By developing the home page layout, user interest and utility were raised to improve the organization method and layout. Through this study, KINS was able to construct a nuclear safety information standardized system and increase transparency and openness by providing feature enhancements in information provision as well as user accessibility and

Safety Requirements and Modern Technical Requirements in Human Information Systems in Amman Hotels

OpenAIRE

Farouq Ahmad Alazzam; Sattam Rakan Allahawiah; Mohammad Nayef Alsarayreh; Kafa Hmoud Abdallah al Nawaiseh

2015-01-01

This study aimed to demonstrate the availability of Safety requirements and modern technical requirements in human information systems in Amman hotels. an the most important results of this study is the availability of security and safety requirements in human information systems In Amman hotels and The adequacy of the information that it provided .and show that all departments are not connected by appropriate and effective communication networks in adequate form . Also sophisticated operatin...

Riding on air: critical safety information for you and your tires

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

This booklet is issued for public distribution by Transport Canada. It provides a few simple tips concerning automobile tire safety which, if followed, is expected to result in increased personal and vehicle safety, improved fuel economy, prolonged tire life, energy savings and reduced environmental pollution. The information provided include tips about tire pressure, tire inspection for damage and wear, rotation of tires for more even wear, replacing worn tires, the advantages of using snow tires in winter and an explanation of the meaning of the information found on the tire sidewall.

A risk-informed perspective on deterministic safety analysis of nuclear power plants

International Nuclear Information System (INIS)

Wan, P.T.

2009-01-01

In this work, the deterministic safety analysis (DSA) approach to nuclear safety is examined from a risk-informed perspective. One objective of safety analysis of a nuclear power plant is to demonstrate via analysis that the risks to the public from events or accidents that are within the design basis of the power plant are within acceptable levels with a high degree of assurance. This nuclear safety analysis objective can be translated into two requirements on the risk estimates of design basis events or accidents: the nominal risk estimate to the public must be shown to be within acceptable levels, and the uncertainty in the risk estimates must be shown to be small on an absolute or relative basis. The DSA approach combined with the defense-in-depth (DID) principle is a simplified safety analysis approach that attempts to achieve the above safety analysis objective in the face of potentially large uncertainties in the risk estimates of a nuclear power plant by treating the various uncertainty contributors using a stylized conservative binary (yes-no) approach, and applying multiple overlapping physical barriers and defense levels to protect against the release of radioactivity from the reactor. It is shown that by focusing on the consequence aspect of risk, the previous two nuclear safety analysis requirements on risk can be satisfied with the DSA-DID approach to nuclear safety. It is also shown the use of multiple overlapping physical barriers and defense levels in the traditional DSA-DID approach to nuclear safety is risk-informed in the sense that it provides a consistently high level of confidence in the validity of the safety analysis results for various design basis events or accidents with a wide range of frequency of occurrence. It is hoped that by providing a linkage between the consequence analysis approach in DSA with a risk-informed perspective, greater understanding of the limitation and capability of the DSA approach is obtained. (author)

Preliminary safety information document for the standard MHTGR. Volume 4

Energy Technology Data Exchange (ETDEWEB)

None

1986-01-01

This report contains information concerning: operational radionuclide control; occupational radiation protection, conduct of operations; initial test program; safety analysis; technical specifications; and quality assurance. (JDB)

Evaluating and Predicting Patient Safety for Medical Devices With Integral Information Technology

Science.gov (United States)

2005-01-01

323 Evaluating and Predicting Patient Safety for Medical Devices with Integral Information Technology Jiajie Zhang, Vimla L. Patel, Todd R...errors are due to inappropriate designs for user interactions, rather than mechanical failures. Evaluating and predicting patient safety in medical ...the users on the identified trouble spots in the devices. We developed two methods for evaluating and predicting patient safety in medical devices

An approach for risk informed safety culture assessment for Canadian nuclear power stations

International Nuclear Information System (INIS)

Nelson, W.R.

2010-01-01

One of the most important components of effective safety and risk management for nuclear power stations is a healthy safety culture. DNV has developed an approach for risk informed safety culture assessment that combines two complementary paradigms for safety and risk management: loss prevention - for preventing and intervening in accidents; and critical function management - for achieving safety and performance goals. Combining these two paradigms makes it possible to provide more robust systems for safety management and to support a healthy safety culture. This approach is being applied to safety culture assessment in partnership with a Canadian nuclear utility. (author)

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

International Nuclear Information System (INIS)

Song, Tae Young

2007-01-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas

Development of a Safety Assessment Information System for the Management of Periodic Safety Assessment Activities

Energy Technology Data Exchange (ETDEWEB)

Song, Tae Young [Nuclear Engineering and Technology Institute, Daejeon (Korea, Republic of)

2007-07-01

At present, the 10-year Periodic Safety Review(PSR) has been performing to confirm all the aspects of safety issues for all the operating plants in compliance with domestic nuclear law of article 23, subarticle 3. For each plant, in addition, Probabilistic Safety Assessment(PSA) and Severe Accident Management Guideline(SAMG) are being implemented and revised periodically to reflect the latest safety level according to principle fulfillment of severe accident policy statement. The assessment reports, as one of outcomes from these activities, are submitted into and reviewed by domestic regulatory body. During reviewing (in-office duty) and licensing (regulatory duty) process, a large number of outcomes of which most are the formal technical reports and licensing materials, are inevitably produced. Moreover, repeated review process over the plants can make them accumulated and produce a variety of documents additionally. This circumstance motivates to develop effective tool or system for the management of these reports and related technical documents for the future use in licensing process and for subsequent plant assessments. This paper presents the development status of Safety Assessment Information System(SAIS) which manages safety-related documents of PSR, PSA and SAMG for practical use for experienced engineers in charge of these areas.

NASA Aviation Safety Program Weather Accident Prevention/weather Information Communications (WINCOMM)

Science.gov (United States)

Feinberg, Arthur; Tauss, James; Chomos, Gerald (Technical Monitor)

2002-01-01

Weather is a contributing factor in approximately 25-30 percent of general aviation accidents. The lack of timely, accurate and usable weather information to the general aviation pilot in the cockpit to enhance pilot situational awareness and improve pilot judgment remains a major impediment to improving aviation safety. NASA Glenn Research Center commissioned this 120 day weather datalink market survey to assess the technologies, infrastructure, products, and services of commercial avionics systems being marketed to the general aviation community to address these longstanding safety concerns. A market survey of companies providing or proposing to provide graphical weather information to the general aviation cockpit was conducted. Fifteen commercial companies were surveyed. These systems are characterized and evaluated in this report by availability, end-user pricing/cost, system constraints/limits and technical specifications. An analysis of market survey results and an evaluation of product offerings were made. In addition, recommendations to NASA for additional research and technology development investment have been made as a result of this survey to accelerate deployment of cockpit weather information systems for enhancing aviation safety.

Memorandum on the use of information technology to improve medication safety.

Science.gov (United States)

Ammenwerth, E; Aly, A-F; Bürkle, T; Christ, P; Dormann, H; Friesdorf, W; Haas, C; Haefeli, W E; Jeske, M; Kaltschmidt, J; Menges, K; Möller, H; Neubert, A; Rascher, W; Reichert, H; Schuler, J; Schreier, G; Schulz, S; Seidling, H M; Stühlinger, W; Criegee-Rieck, M

2014-01-01

Information technology in health care has a clear potential to improve the quality and efficiency of health care, especially in the area of medication processes. On the other hand, existing studies show possible adverse effects on patient safety when IT for medication-related processes is developed, introduced or used inappropriately. To summarize definitions and observations on IT usage in pharmacotherapy and to derive recommendations and future research priorities for decision makers and domain experts. This memorandum was developed in a consensus-based iterative process that included workshops and e-mail discussions among 21 experts coordinated by the Drug Information Systems Working Group of the German Society for Medical Informatics, Biometry and Epidemiology (GMDS). The recommendations address, among other things, a stepwise and comprehensive strategy for IT usage in medication processes, the integration of contextual information for alert generation, the involvement of patients, the semantic integration of information resources, usability and adaptability of IT solutions, and the need for their continuous evaluation. Information technology can help to improve medication safety. However, challenges remain regarding access to information, quality of information, and measurable benefits.

Trade associations and labor organizations as intermediaries for disseminating workplace safety and health information.

Science.gov (United States)

Okun, Andrea H; Watkins, Janice P; Schulte, Paul A

2017-09-01

There has not been a systematic study of the nature and extent to which business and professional trade associations and labor organizations obtain and communicate workplace safety and health information to their members. These organizations can serve as important intermediaries and play a central role in transferring this information to their members. A sample of 2294 business and professional trade associations and labor organizations in eight industrial sectors identified by the National Occupational Research Agenda was surveyed via telephone. A small percent of these organizations (40.9% of labor organizations, 15.6% of business associations, and 9.6% of professional associations) were shown to distribute workplace safety and health information to their members. Large differences were also observed between industrial sectors with construction having the highest total percent of organizations disseminating workplace safety and health information. There appears to be significant potential to utilize trade and labor organizations as intermediaries for transferring workplace safety and health information to their members. Government agencies have a unique opportunity to partner with these organizations and to utilize their existing communication channels to address high risk workplace safety and health concerns. Published 2017. This article is a U.S. Government work and is in the public domain in the USA.

Safety recommendation component of mobile information assistant of the tourist

Science.gov (United States)

Savchuk, Valeriya V.; Kunanec, Natalia E.; Pasichnyk, Volodymyr V.; Popiel, Piotr; Weryńska-Bieniasz, RóŻa; Kashaganova, Gulzhamal; Kalizhanova, Aliya

2017-08-01

The goal of article is to introduce and justify the need for the safety system components of Mobile Information of the tourist (MIAT). One of the objectives of the system is to determine the level of risk in a particular tourist destination on the basis of available information in the knowledge base.

State Traffic Safety Information - 2010-2015 FARS Accident File data

Data.gov (United States)

Department of Transportation — The State Traffic Safety Information (STSI) portal is part of the larger Fatality Analysis Reporting System (FARS) Encyclopedia. STSI provides state-by-state traffic...

The Research on Safety Management Information System of Railway Passenger Based on Risk Management Theory

Science.gov (United States)

Zhu, Wenmin; Jia, Yuanhua

2018-01-01

Based on the risk management theory and the PDCA cycle model, requirements of the railway passenger transport safety production is analyzed, and the establishment of the security risk assessment team is proposed to manage risk by FTA with Delphi from both qualitative and quantitative aspects. The safety production committee is also established to accomplish performance appraisal, which is for further ensuring the correctness of risk management results, optimizing the safety management business processes and improving risk management capabilities. The basic framework and risk information database of risk management information system of railway passenger transport safety are designed by Ajax, Web Services and SQL technologies. The system realizes functions about risk management, performance appraisal and data management, and provides an efficient and convenient information management platform for railway passenger safety manager.

Risk-informed regulation: handling uncertainty for a rational management of safety

International Nuclear Information System (INIS)

Zio, Enrico

2008-01-01

A risk-informed regulatory approach implies that risk insights be used as supplement of deterministic information for safety decision-making purposes. In this view, the use of risk assessment techniques is expected to lead to improved safety and a more rational allocation of the limited resources available. On the other hand, it is recognized that uncertainties affect both the deterministic safety analyses and the risk assessments. In order for the risk-informed decision making process to be effective, the adequate representation and treatment of such uncertainties is mandatory. In this paper, the risk-informed regulatory framework is considered under the focus of the uncertainty issue. Traditionally, probability theory has provided the language and mathematics for the representation and treatment of uncertainty. More recently, other mathematical structures have been introduced. In particular, the Dempster-Shafer theory of evidence is here illustrated as a generalized framework encompassing probability theory and possibility theory. The special case of probability theory is only addressed as term of comparison, given that it is a well known subject. On the other hand, the special case of possibility theory is amply illustrated. An example of the combination of probability and possibility for treating the uncertainty in the parameters of an event tree is illustrated

A quantitative approach for risk-informed safety significance categorization in option-2

International Nuclear Information System (INIS)

Ha, Jun Su; Seong, Poong Hyun

2004-01-01

OPTION-2 recommends that Structures, Systems, or Components (SSCs) of Nuclear Power Plants (NPPs) should be categorized into four groups according to their safety significance as well as whether they are safety-related or not. With changes to the scope of SSCs covered by 10 CFR 50, safety-related components which categorized into low safety significant SSC (RISC-3 SSC) can be exempted from the existing conservative burden (or requirements). As OPTION-2 paradigm is applied, a lot of SSCs may be categorized into RISC-3 SSCs. Changes in treatment of the RISC-3 SSCs will be recommended and then finally the recommended changes shall be evaluated. Consequently, before recommending the changes in treatment, probable candidate SSCs for the changes in treatment need to be identified for efficient risk-informed regulation and application (RIRA). Hence, in this work, a validation focused on the RISC-3 SSCs is proposed to identify probable candidate SSCs. Burden to Importance Ratio (BIR) is utilized as a quantitative measure for the validation. BIR is a measure representing the extent of resources or requirements imposed on a SSC with respect to the value of the importance measure of the SSC. Therefore SSCs having high BIR can be considered as probable candidate SSCs for the changes in treatment. In addition, the final decision whether RISC-3 SSCs can be considered as probable candidate SSCs or not should be made by an expert panel. For the effective decision making, a structured mathematical decision-making process is constructed based on Belief Networks (BBN) to overcome demerits of conventional group meeting based on unstructured discussion for decision-making. To demonstrate the usefulness of the proposed approach, the approach is applied to 22 components selected from 512 In-Service Test (IST) components of Ulchin unit 3. The results of the application show that the proposed approach can identify probable candidate SSCs for changes in treatment. The identification of the

Implementation of the obligations of the Convention on Nuclear Safety CNS - Switzerland’s seventh national report to the Convention on Nuclear Safety

International Nuclear Information System (INIS)

2016-07-01

In the aftermath of the Fukushima Daiichi accident in 2011, the Swiss government decided to phase out nuclear energy. Existing plants will continue to operate as long as they are considered safe by the Swiss Federal Nuclear Safety Inspectorate (ENSI) and as long as they fulfil all legal and regulatory requirements in this respect. In Switzerland, on-going activities regarding safety assessment of the different stages in the lifetime of nuclear installations consist of periodic assessments and assessments of long-term operation for existing Swiss nuclear power plants (NPPs). Assessments of long-term operation have been performed for two Swiss NPPs (Beznau and Muehleberg) which have been in commercial operation for over 40 years. A detailed examination demonstrated that the conditions for taking a NPP out of service have not yet been reached and will not be reached by these two plants within the next 10 years. Nevertheless, it is mandatory to continue with the scheduled ageing management, maintenance and backfitting activities. In late 2013, BKW Energy Ltd announced that Muehleberg NPP will be decommissioned at the end of 2019. The plant will shut down on December 20 th , 2019.The single 373 MWe boiling water reactor began operating in 1972. It will be the first Swiss nuclear power plant to be decommissioned. The preparatory work for decommissioning is well under way. In April 2015, a follow-up mission was conducted by the Integrated Regulatory Review Service in Switzerland. The Swiss government should give ENSI the ability to issue legally binding technical safety requirements and license conditions concerning nuclear safety, nuclear security and radiation safety. A follow-up mission by the Operational Safety Review Team on the Muehleberg NPP was completed in June 2014. Switzerland participated in the European Stress Test and its follow-up activities. During 2014, the necessary measures to achieve continuous improvement in the supervisory culture were defined. The

Implementation of the obligations of the Convention on Nuclear Safety CNS - Switzerland’s seventh national report to the Convention on Nuclear Safety

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-07-15

In the aftermath of the Fukushima Daiichi accident in 2011, the Swiss government decided to phase out nuclear energy. Existing plants will continue to operate as long as they are considered safe by the Swiss Federal Nuclear Safety Inspectorate (ENSI) and as long as they fulfil all legal and regulatory requirements in this respect. In Switzerland, on-going activities regarding safety assessment of the different stages in the lifetime of nuclear installations consist of periodic assessments and assessments of long-term operation for existing Swiss nuclear power plants (NPPs). Assessments of long-term operation have been performed for two Swiss NPPs (Beznau and Muehleberg) which have been in commercial operation for over 40 years. A detailed examination demonstrated that the conditions for taking a NPP out of service have not yet been reached and will not be reached by these two plants within the next 10 years. Nevertheless, it is mandatory to continue with the scheduled ageing management, maintenance and backfitting activities. In late 2013, BKW Energy Ltd announced that Muehleberg NPP will be decommissioned at the end of 2019. The plant will shut down on December 20{sup th}, 2019.The single 373 MWe boiling water reactor began operating in 1972. It will be the first Swiss nuclear power plant to be decommissioned. The preparatory work for decommissioning is well under way. In April 2015, a follow-up mission was conducted by the Integrated Regulatory Review Service in Switzerland. The Swiss government should give ENSI the ability to issue legally binding technical safety requirements and license conditions concerning nuclear safety, nuclear security and radiation safety. A follow-up mission by the Operational Safety Review Team on the Muehleberg NPP was completed in June 2014. Switzerland participated in the European Stress Test and its follow-up activities. During 2014, the necessary measures to achieve continuous improvement in the supervisory culture were defined

Quality and safety implications of emergency department information systems.

Science.gov (United States)

Farley, Heather L; Baumlin, Kevin M; Hamedani, Azita G; Cheung, Dickson S; Edwards, Michael R; Fuller, Drew C; Genes, Nicholas; Griffey, Richard T; Kelly, John J; McClay, James C; Nielson, Jeff; Phelan, Michael P; Shapiro, Jason S; Stone-Griffith, Suzanne; Pines, Jesse M

2013-10-01

The Health Information Technology for Economic and Clinical Health Act of 2009 and the Centers for Medicare & Medicaid Services "meaningful use" incentive programs, in tandem with the boundless additional requirements for detailed reporting of quality metrics, have galvanized hospital efforts to implement hospital-based electronic health records. As such, emergency department information systems (EDISs) are an important and unique component of most hospitals' electronic health records. System functionality varies greatly and affects physician decisionmaking, clinician workflow, communication, and, ultimately, the overall quality of care and patient safety. This article is a joint effort by members of the Quality Improvement and Patient Safety Section and the Informatics Section of the American College of Emergency Physicians. The aim of this effort is to examine the benefits and potential threats to quality and patient safety that could result from the choice of a particular EDIS, its implementation and optimization, and the hospital's or physician group's approach to continuous improvement of the EDIS. Specifically, we explored the following areas of potential EDIS safety concerns: communication failure, wrong order-wrong patient errors, poor data display, and alert fatigue. Case studies are presented that illustrate the potential harm that could befall patients from an inferior EDIS product or suboptimal execution of such a product in the clinical environment. The authors have developed 7 recommendations to improve patient safety with respect to the deployment of EDISs. These include ensuring that emergency providers actively participate in selection of the EDIS product, in the design of processes related to EDIS implementation and optimization, and in the monitoring of the system's ongoing success or failure. Our recommendations apply to emergency departments using any type of EDIS: custom-developed systems, best-of-breed vendor systems, or enterprise systems

78 FR 34703 - Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report

Science.gov (United States)

2013-06-10

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2013-0004] Pipeline Safety: Information Collection Activities, Revision to Gas Distribution Annual Report AGENCY: Pipeline and Hazardous Materials Safety Administration, DOT. ACTION: Notice and request...

A qualitative exploration of the perceptions and information needs of public health inspectors responsible for food safety

Directory of Open Access Journals (Sweden)

Sargeant Jan M

2010-06-01

Full Text Available Abstract Background In Ontario, local public health inspectors play an important frontline role in protecting the public from foodborne illness. This study was an in-depth exploration of public health inspectors' perceptions of the key food safety issues in public health, and their opinions and needs with regards to food safety information resources. Methods Four focus group discussions were conducted with public health inspectors from the Central West region of Ontario, Canada during June and July, 2008. A questioning route was used to standardize qualitative data collection. Audio recordings of sessions were transcribed verbatim and data-driven content analysis was performed. Results A total of 23 public health inspectors participated in four focus group discussions. Five themes emerged as key food safety issues: time-temperature abuse, inadequate handwashing, cross-contamination, the lack of food safety knowledge by food handlers and food premise operators, and the lack of food safety information and knowledge about specialty foods (i.e., foods from different cultures. In general, participants reported confidence with their current knowledge of food safety issues and foodborne pathogens. Participants highlighted the need for a central source for food safety information, access to up-to-date food safety information, resources in different languages, and additional food safety information on specialty foods. Conclusions The information gathered from these focus groups can provide a basis for the development of resources that will meet the specific needs of public health inspectors involved in protecting and promoting food safety.

A Survey of Pilots on the Dissemination of Safety Information

National Research Council Canada - National Science Library

Rakovan, Lori

1999-01-01

A survey was conducted to obtain information from the pilot population on erections of safety-related training currently being offered, its usefulness, and the process through which it might be better...

Participatory approach to improving safety, health and working conditions in informal economy workplaces in Cambodia.

Science.gov (United States)

Kawakami, Tsuyoshi; Tong, Leng; Kannitha, Yi; Sophorn, Tun

2011-01-01

The present study aimed to improve safety and health in informal economy workplaces such as home workplaces, small construction sites, and rural farms in Cambodia by using "participatory" approach. The government, workers' and employers' organizations and NGOs jointly assisted informal economy workers in improving safety and health by using participatory training methodologies. The steps taken were: (1) to collect existing good practices in safety and health in Cambodia; (2) to develop new participatory training programmes for home workers and small construction sites referring to ILO's WISE training programme, and (3) to train government officers, workers, employers and NGOs as safety and health trainers. The participatory training programmes developed consisted of action-checklists associated with illustrations, good example photo sheets, and texts explaining practical, low-cost improvement measures. The established safety and health trainers reached many informal economy workers through their human networks, and trained them by using the developed participatory training programmes. More than 3,000 informal economy workers were trained and they implemented improvements by using low-cost methods. Participatory training methodologies and active cooperation between the government, workers, employers and NGOs made it possible to provide practical training for those involved in the informal economy workplaces.

Memorandum of understanding between the Government of the Kingdom of Norway and the Government of the Kingdom of the Netherlands on early notification of a nuclear accident and exchange of safety related information concerning the operation and management of nuclear facilities

International Nuclear Information System (INIS)

1989-01-01

This Agreement was concluded in implementation of the IAEA 1986 Convention on Early Notification of a Nuclear Accident. Both Governments undertake to notify each other forthwith of any abnormal radiation levels in their respective countries. They will exchange safety related information on nuclear facilities and inform each other of measures to protect the population and the environment. (NEA)

Memorandum of understanding between the Government of the Kingdom of Norway and the Government of the Kingdom of the Netherlands on early notification of a nuclear accident and exchange of safety related information concerning the operation and management of nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

1989-04-18

This Agreement was concluded in implementation of the IAEA 1986 Convention on Early Notification of a Nuclear Accident. Both Governments undertake to notify each other forthwith of any abnormal radiation levels in their respective countries. They will exchange safety related information on nuclear facilities and inform each other of measures to protect the population and the environment. (NEA).

Conceptual design of an integrated information system for safety related analysis of nuclear power plants (IRIS Phase 1)

International Nuclear Information System (INIS)

Hofer, K.; Zehnder, P.; Galperin, A.

1994-01-01

This report deals with a conceptual design of an integrated information management system, called PSI-IRIS, as needed to assist the analysts for reactor safety related investigations on Swiss nuclear power plants within the project STARS. Performing complicated engineering analyses of an NPP requires storage and manipulation of a large amount of information, both data and knowledge. This information is characterized by its multi-disciplinary nature, complexity, and diversity. The problems caused by inefficient and lengthy manual operations involving the data flow management within the framework of the safety related analysis of an NPP, can be solved by applying computer aided engineering (CAE) principles. These principles are the basis for the design of the integrated information management system PSI-IRIS presented in this report. The basic idea is to create a computerized environment, which includes both database and functional capabilities. The database of the PSI-IRIS consists of two parts, an NPP generic database (GDB) and a collection of analysis results (CASE L IB). The GDB includes all technical plant data and information needed to generate input decks for all computer codes utilized within the STARS project. The CASE L IB storage contains the accumulated knowledge, input decks, and result files of the NPP transient analyses. Considerations and analysis of the data types and the required data manipulation capabilities as well as operational requirements resulted in the choice of an object-oriented database management system (OODBMS) as a development platform for solving the software engineering problems. Several advantages of OODBMS's over conventional relational database management systems were found of crucial importance, especially providing the necessary flexibility for different data types and the potential for extensibility. (author) 15 figs., tabs., 20 refs

Information System Passive Safety at DaimlerChrysler: from vision to reality

Energy Technology Data Exchange (ETDEWEB)

Ruoff, H. [DaimlerChrysler AG, Sindelfingen (Germany)

2001-07-01

Today, short development times and an extensive model range are key factors when it comes to remaining a leading force in the highly competitive automobile market. Information technology plays a crucial role as an 'enabler' in keeping this competitive edge. It is only possible to make full use of existing potential by using 'state-of-the-art' information technology. In particular, this involves making knowledge that is distributed in various systems and 'heads' available quickly and transparently anytime and anywhere. The improved re-use of acquired expertise, efficient information searches, and standardized and seamless applications lead to a high level of performance. This often involves the transformation of a company culture from 'information hider' to 'information provider'. The vision of converting a gradually created, complex range of systems into a seamless sequence of distributed working processes with numerous participants is becoming reality in the Passive Safety area in Automobile/Vehicle Development at DaimlerChrysler. The INFOS Passive Safety information system provides all the data and information, which is required for, or results from, the entire crash test process. (orig.)

Information dissemination and use: critical components in occupational safety and health.

Science.gov (United States)

Schulte, P A; Okun, A; Stephenson, C M; Colligan, M; Ahlers, H; Gjessing, C; Loos, G; Niemeier, R W; Sweeney, M H

2003-11-01

Information dissemination is a mandated, but understudied, requirement of occupational and environmental health laws and voluntary initiatives. Research is needed on the factors that enhance and limit the development, transfer, and use of occupational safety and health information (OSH). Contemporary changes in the workforce, workplaces, and the nature of work will require new emphasis on the dissemination of information to foster prevention. Legislative and regulatory requirements and voluntary initiatives for dissemination of OSH information were identified and assessed. Literature on information dissemination was reviewed to identify important issues and useful approaches. More than 20 sections of laws and regulations were identified that mandated dissemination of occupational and environmental safety and health information. A four-stage approach for tracking dissemination and considering the flow of information was delineated. Special areas of dissemination were identified: the information needs of the changing workforce, new and young workers; small businesses; and workers with difficulty in understanding or reading English. We offer a framework for dissemination of OSH information and underscore the need to focus on the extent to which decision-makers and others receive and use such information. More solid data are also needed on current investments in disseminating, diffusing and applying OSH information and on the utility of that information. Am. J. Ind. Med. 44:515-531, 2003. Published 2003 Wiley-Liss, Inc.

Biologic and Conventional Systemic Therapies Show Similar Safety and Efficacy in Elderly and Adult Patients With Moderate to Severe Psoriasis.

Science.gov (United States)

Garber, Caren; Plotnikova, Natalia; Au, Shiu-chung; Sorensen, Eric P; Gottlieb, Alice

2015-08-01

Despite the aging population, few studies have documented the treatment of geriatric psoriasis. The purpose of this study is to compare the efficacy, safety, and prescribing patterns of biologics and conventional systemic medications in elderly versus adult psoriasis. All patient visits coded for psoriasis or psoriatic arthritis (ICD-9 696.1 or 696.0) at the Tufts Medical Center General Dermatology Clinic from January 1, 2008, to March 1, 2015 were included in this retrospective cohort study. The outcome measure used was the validated simple-measure for assessing psoriasis activity (S-MAPA), the product of the physician's global assessment and the body surface area. 194 patients who underwent 278 treatment courses were included in the study. 48 patients were included in the elderly cohort (≥ 65 years old) and 146 in the adult cohort (18-64 years old). There was no significant difference in S-MAPA improvement at 12 weeks between the two cohorts when treated with biologics (42.92% improvement in adults, 48.77% in elderly; P=0.498) or conventional systemics (43.96% and 51.82%, respectively; P=0.448). Within the elderly cohort, there was no significant difference in efficacy of biologics versus conventional systemics at any time point. Topical prescription rates were significantly higher in the elderly cohort ( P=0.004) while biologic prescription rates were significantly lower ( P=0.014) despite the same baseline S-MAPA in both age groups. For both biologics and conventional systemics, there was no statistically significant intergroup difference in the rate of adverse events ( P=0.322 for biologics; P=0.581 for conventional systemics) or infection ( P=0.753 for biologics; P=0.828 for conventional systemics). Within the elderly cohort, there was a higher rate of adverse events with conventional systemic treatment than with biologic treatment ( P=0.033). This study provides preliminary evidence to suggest that biologic and conventional systemic therapies are similarly

An Anesthesia Preinduction Checklist to Improve Information Exchange, Knowledge of Critical Information, Perception of Safety, and Possibly Perception of Teamwork in Anesthesia Teams.

Science.gov (United States)

Tscholl, David W; Weiss, Mona; Kolbe, Michaela; Staender, Sven; Seifert, Burkhardt; Landert, Daniel; Grande, Bastian; Spahn, Donat R; Noethiger, Christoph B

2015-10-01

An anesthesia preinduction checklist (APIC) to be performed before anesthesia induction was introduced and evaluated with respect to 5 team-level outcomes, each being a surrogate end point for patient safety: information exchange (the percentage of checklist items exchanged by a team, out of 12 total items); knowledge of critical information (the percentage of critical information items out of 5 total items such as allergies, reported as known by the members of a team); team members' perceptions of safety (the median scores given by the members of a team on a continuous rating scale); their perception of teamwork (the median scores given by the members of a team on a continuous rating scale); and clinical performance (the percentage of completed items out of 14 required tasks, e.g., suction device checked). A prospective interventional study comparing anesthesia teams using the APIC with a control group not using the APIC was performed using a multimethod design. Trained observers rated information exchange and clinical performance during on-site observations of anesthesia inductions. After the observations, each team member indicated the critical information items they knew and their perceptions of safety and teamwork. One hundred five teams using the APIC were compared with 100 teams not doing so. The medians of the team-level outcome scores in the APIC group versus the control group were as follows: information exchange: 100% vs 33% (P safety: 91% vs 84% (P improves information exchange, knowledge of critical information, and perception of safety in anesthesia teams-all parameters contributing to patient safety. There was a trend indicating improved perception of teamwork.

Comparison of organic and conventional food and food production

OpenAIRE

Norwegian Scientific Committee for Food Safety

2014-01-01

The Norwegian Scientific Committee for Food Safety has performed an assessment of the differences between organic and conventional foods and food production on plant health, animal health and welfare and human health at the request of the Norwegian Food Safety Authority.

General safety considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-09-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

General safety considerations

International Nuclear Information System (INIS)

2001-01-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness

General safety considerations

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness.

General safety considerations

International Nuclear Information System (INIS)

1998-01-01

This document presents the full filling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 4 of the document contains some details about the priority to safety, financial and human resources, human factors, quality assurance, safety assessment and verification, radiation protection and emergency preparedness

Analysis of safety information for nuclear power plants and development of source term estimation program

International Nuclear Information System (INIS)

Kim, Tae Woon; Choi, Seong Soo; Park, Jin Hee

1999-12-01

Current CARE(Computerized Advisory System for Radiological Emergency) in KINS(Korea Institute of Nuclear Safety) has no STES(Source Term Estimation System) which links between SIDS(Safety Information Display System) and FADAS(Following Accident Dose Assessment System). So in this study, STES is under development. STES system is the system that estimates the source term based on the safety information provided by SIDS. Estimated source term is given to FADAS as an input for estimation of environmental effect of radiation. Through this first year project STES for the Kori 3,4 and Younggwang 1,2 has been developed. Since there is no CARE for Wolsong(PHWR) plants yet, CARE for Wolsong is under construction. The safety parameters are selected and the safety information display screens and the alarm logic for plant status change are developed for Wolsong Unit 2 based on the design documents for CANDU plants

Discrete event simulation versus conventional system reliability analysis approaches

DEFF Research Database (Denmark)

Kozine, Igor

2010-01-01

Discrete Event Simulation (DES) environments are rapidly developing and appear to be promising tools for building reliability and risk analysis models of safety-critical systems and human operators. If properly developed, they are an alternative to the conventional human reliability analysis models...... and systems analysis methods such as fault and event trees and Bayesian networks. As one part, the paper describes briefly the author’s experience in applying DES models to the analysis of safety-critical systems in different domains. The other part of the paper is devoted to comparing conventional approaches...

Technical mechanics in constructional reactor safety

International Nuclear Information System (INIS)

Matthees, W.

1979-01-01

Reactor safety is based on close cooperation between a number of technical and scientific disciplines; most problems of reactor technology can be solved with the aid of technical mechanics. At the 5th International Conference on Structural Mechanics in Reactor Technology (5th SMIRT), one of the biggest conferences in the field of applied technical mechanics, about 800 papers were read giving the latest state of knowledge in the field of constructional reactor safety. The main subject of the conference was the analysis of material behaviour under high loads; the information and methods of these analysis go far beyond what is required in the conventional field. (orig./UA) [de

Smooth handling: the lack of safety-related consumer information in car advertisements.

Science.gov (United States)

Wilson, Nick; Maher, Anthony; Thomson, George; Keall, Michael

2007-10-01

To examine the content and trends of safety-related consumer information in magazine vehicle advertisements, as a case study within the worldwide marketing of vehicles. Content analysis of popular current affairs magazines in New Zealand for the 5-year period 2001-2005 was undertaken (n = 514 advertisements), supplemented with vehicle data from official websites. Safety information in advertisements for light passenger vehicles was relatively uncommon with only 27% mentioning one or more of nine key safety features examined (average: 1.7 out of nine features in this 27%). Also included were potentially hazardous features of: speed imagery (in 29% of advertisements), power references (14%), and acceleration data (4%). The speed and power aspects became relatively more common over the 5-year period (p advertisements and vehicle marketing - as already occurs with many other consumer products.

Application of the Aarhus Convention

Directory of Open Access Journals (Sweden)

Tubić Bojan

2011-01-01

Full Text Available Convention on access to information, public participation in decision-making and access to justice in environmental matters (Aarhus Convention has been adopted in 1998 and entered into force three years later. It envisages three elements for strengthening democratic procedures in decision-making: access to information, public participation and access to justice. At the first meeting of the Member States the Aarhus Convention Compliance Committee was founded. The European Union is a party of the Convention and it has implemented the provisions in its legal order. After entering into force of the Convention, several Directives that regulate these issues in the EU have been enacted. Republic of Serbia has ratified the Convention in 2009 and it is currently in the process of its implementation by involving private subjects in decision-making on environmental issues.

World Trade Organization, ILO conventions, and workers' compensation.

Science.gov (United States)

LaDou, Joseph

2005-01-01

The World Trade Organization, the World Bank, and the International Monetary Fund can assist in the implementation of ILO Conventions relating to occupational safety and health in developing countries. Most countries that seek to trade globally receive permission to do so from the WTO. If the WTO required member countries to accept the core ILO Conventions relating to occupational safety and health and workers' compensation, it could accomplish something that has eluded international organizations for decades. International workers' compensation standards are seldom discussed, but may at this time be feasible. Acceptance of a minimum workers' compensation insurance system could be a requirement imposed on applicant nations by WTO member states.

Comparison of the safety information on drug labels in three developed countries: The USA, UK and Canada

Directory of Open Access Journals (Sweden)

Thamir M. Alshammari

2017-12-01

Full Text Available The safety information on drug labels of a company marketing the same drugs in different countries is sometimes different. The aim of the present study is to understand the differences in the volume and content of safety information on the drug labels from the same manufacturers in three developed countries: the United States of America (USA, the United Kingdom (UK and Canada. This study involved the calculation of the proportion of total safety information (PSI and of contraindications (PCI in comparison to all information on the label and the percentage of boxed warnings (PBW among the 100 labels studied from each country. The PSI on the labels of different countries is different with USA labels bearing lesser value PSI and UK labels bearing higher value PSI. The qualitative information provided on these drug labels from each country in ‘contraindications’ sections, ‘boxed/serious warnings’ and ‘overdosage’ sections presented differences in the information provided on most of the labels. We have found distinct differences between the safety information available on drug labels in terms of volume and content. We conclude that the safety information for the same products should be standardised across all countries.

Stress Tests Worldwide - IAEA Nuclear Safety Action Plan

International Nuclear Information System (INIS)

Lyons, J.E.

2012-01-01

The IAEA nuclear safety action plan relies on 11 important issues. 1) Safety assessments in light of the Fukushima accident: the IAEA secretariat will develop a methodology for stress tests against specific extreme natural hazards and will provide assistance for their implementation; 2) Strengthen existing IAEA peer reviews; 3) Emergency preparedness and response; 4) National Regulatory bodies in terms of independence and adequacy of human and financial resources; 5) The development of safety culture and scientific and technical capacity in Operating Organizations; 6) The upgrading of IAEA safety standards in a more efficient way; 7) A better implementation of relevant conventions concerning nuclear safety and nuclear accidents; 8) To provide a broad assistance on safety standard for countries embarking on a nuclear power program; 9) To facilitate the use of available information, expertise and techniques concerning radiation protection; 10) To enhance the transparency of nuclear industry; and 11) To promote the cooperation between member states in nuclear safety. (A.C.)

Numerical assessment of conventional regulation effectiveness for ...

African Journals Online (AJOL)

... depends on fire safety engineering that is provided, and which is generally established using smoke spread field and temperature distribution predictions. ... conventional regulation; ventilation strategies; smoke temperature; smoke barriers ...

Classification of antecedents towards safety use of health information technology: A systematic review.

Science.gov (United States)

Salahuddin, Lizawati; Ismail, Zuraini

2015-11-01

This paper provides a systematic review of safety use of health information technology (IT). The first objective is to identify the antecedents towards safety use of health IT by conducting systematic literature review (SLR). The second objective is to classify the identified antecedents based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model and an extension of DeLone and McLean (D&M) information system (IS) success model. A systematic literature review (SLR) was conducted from peer-reviewed scholarly publications between January 2000 and July 2014. SLR was carried out and reported based on the preferred reporting items for systematic reviews and meta-analyses (PRISMA) statement. The related articles were identified by searching the articles published in Science Direct, Medline, EMBASE, and CINAHL databases. Data extracted from the resultant studies included are to be analysed based on the work system in Systems Engineering Initiative for Patient Safety (SEIPS) model, and also from the extended DeLone and McLean (D&M) information system (IS) success model. 55 articles delineated to be antecedents that influenced the safety use of health IT were included for review. Antecedents were identified and then classified into five key categories. The categories are (1) person, (2) technology, (3) tasks, (4) organization, and (5) environment. Specifically, person is attributed by competence while technology is associated to system quality, information quality, and service quality. Tasks are attributed by task-related stressor. Organisation is related to training, organisation resources, and teamwork. Lastly, environment is attributed by physical layout, and noise. This review provides evidence that the antecedents for safety use of health IT originated from both social and technical aspects. However, inappropriate health IT usage potentially increases the incidence of errors and produces new safety risks. The review cautions future

76 FR 67496 - Proposed Information Collection; Comment Request

Science.gov (United States)

2011-11-01

... Labor's Occupational Safety and Health Administration (OSHA) and to reduce litigation costs. The program... Law Judge. If settlement efforts fail, the case would continue under OSHRC's conventional proceedings... personally participated in cases from February 15, 2011 through February 14, 2012. The proposed information...

Public information and education on radiation safety and protection in Indonesia

Energy Technology Data Exchange (ETDEWEB)

Djaloeis, Azhar [National Atomic Energy Agency, Jalan KH Abdul Rohim, Mampang Prapatan, Jakarta (Indonesia)

1999-09-01

This paper presents a brief overview of public information and education concerning nuclear science and technology in general and radiation safety and protection in particular in Indonesia from the perspective of promoting the development and utilization of nuclear science and technology in the country. The role of nuclear science and technology in Indonesia is first introduced, followed by an overview of the nuclear activities in the country. Basic considerations, major objectives of the public information and education program on radiation safety and protection as well as basic and operational strategies to achieve those objectives are then presented. Major programs including highlights of the past and present activities as well as prospect on future course of actions are discussed. (author)

Public information and education on radiation safety and protection in Indonesia

International Nuclear Information System (INIS)

Djaloeis, Azhar

1999-01-01

This paper presents a brief overview of public information and education concerning nuclear science and technology in general and radiation safety and protection in particular in Indonesia from the perspective of promoting the development and utilization of nuclear science and technology in the country. The role of nuclear science and technology in Indonesia is first introduced, followed by an overview of the nuclear activities in the country. Basic considerations, major objectives of the public information and education program on radiation safety and protection as well as basic and operational strategies to achieve those objectives are then presented. Major programs including highlights of the past and present activities as well as prospect on future course of actions are discussed. (author)

Data Analysis Approaches for the Risk-Informed Safety Margins Characterization Toolkit

International Nuclear Information System (INIS)

Mandelli, Diego; Alfonsi, Andrea; Maljovec, Daniel P.; Parisi, Carlo; Cogliati, Joshua J.; Talbot, Paul W.; Smith, Curtis L.; Rabiti, Cristian; Picoco, Claudia

2016-01-01

In the past decades, several numerical simulation codes have been employed to simulate accident dynamics (e.g., RELAP5-3D, RELAP-7, MELCOR, MAAP). In order to evaluate the impact of uncertainties into accident dynamics, several stochastic methodologies have been coupled with these codes. These stochastic methods range from classical Monte-Carlo and Latin Hypercube sampling to stochastic polynomial methods. Similar approaches have been introduced into the risk and safety community where stochastic methods (such as RAVEN, ADAPT, MCDET, ADS) have been coupled with safety analysis codes in order to evaluate the safety impact of timing and sequencing of events. These approaches are usually called Dynamic PRA or simulation-based PRA methods. These uncertainties and safety methods usually generate a large number of simulation runs (database storage may be on the order of gigabytes or higher). The scope of this paper is to present a broad overview of methods and algorithms that can be used to analyze and extract information from large data sets containing time dependent data. In this context, ''extracting information'' means constructing input-output correlations, finding commonalities, and identifying outliers. Some of the algorithms presented here have been developed or are under development within the RAVEN statistical framework.

Variation among conventional cultivars could be used as a criterion for environmental safety assessment of Bt rice on nontarget arthropods

Science.gov (United States)

Wang, Fang; Dang, Cong; Chang, Xuefei; Tian, Junce; Lu, Zengbin; Chen, Yang; Ye, Gongyin

2017-02-01

The current difficulty facing risk evaluations of Bacillus thuringiensis (Bt) crops on nontarget arthropods (NTAs) is the lack of criteria for determining what represents unacceptable risk. In this study, we investigated the biological parameters in the laboratory and field population abundance of Nilaparvata lugens (Hemiptera: Delphacidae) on two Bt rice lines and the non-Bt parent, together with 14 other conventional rice cultivars. Significant difference were found in nymphal duration and fecundity of N. lugens fed on Bt rice KMD2, as well as field population density on 12 October, compared with non-Bt parent. However, compared with the variation among conventional rice cultivars, the variation of each parameter between Bt rice and the non-Bt parent was much smaller, which can be easily seen from low-high bar graphs and also the coefficient of variation value (C.V). The variation among conventional cultivars is proposed to be used as a criterion for the safety assessment of Bt rice on NTAs, particularly when statistically significant differences in several parameters are found between Bt rice and its non-Bt parent. Coefficient of variation is suggested as a promising parameter for ecological risk judgement of IRGM rice on NTAs.

The Aarhus Convention: A new regional convention on citizens' environmental rights

International Nuclear Information System (INIS)

Wates, J.

2000-01-01

The UN ECE Convention on Access to Information, Public Participation in Decision-making and Access to Justice in Environmental Matters had been adopted at Arhus, Denmark, at the Fourth Ministerial Conference in the 'Environment for Europe' process, and signed by thirty-five countries and the European Community. This paper summarises the main features of the Convention and briefly discusses its relevance to radioactive waste management issues. It then describes some of the activities currently being undertaken under the auspices of the Convention. (author)

Conference report. Fourth review meeting of the parties of the Joint Convention

International Nuclear Information System (INIS)

Brennecke, Peter

2012-01-01

The Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management, the first legal instrument to directly address these topics on a global scale, was opened for signature 29 September 1997. It entered into force 18 June 2001. The Convention calls for triannual review meetings of the Contracting Parties. Each Contracting Party is required to submit a national report to each review meeting that addresses measures taken to implement each of the obligations of the Convention. The first review meeting took place in 2003. The 4 th review meeting of this Convention took place from 14 to 23 May 2012 at the International Atomic Energy Agency (IAEA) Headquarter in Vienna/Austria. (orig.)

Gun barrel erosion - Comparison of conventional and LOVA gun propellants

NARCIS (Netherlands)

Hordijk, A.C.; Leurs, O.

2006-01-01

The research department Energetic Materials within TNO Defence, Security and Safety is involved in the development and (safety and insensitive munitions) testing of conventional (nitro cellulose based) and thermoplastic elastomer (TPE) based gun propellants. Recently our testing capabilities have

Radiation safety study for conventional facility and siting pre project phase of International Linear Collider

International Nuclear Information System (INIS)

Sanami, Toshiya; Ban, Syuichi; Sasaki, Shin-ichi

2015-01-01

The International Linear Collider (ILC) is a proposed high-energy collider consisting of two linear accelerators, two dumping rings, electron and positron sources, and a single colliding hall with two detectors. The total length and CMS energy of the ILC will be 31 km and 500 GeV, respectively (and 50 km and 1 TeV after future upgrade). The design of the ILC has entered the pre-project phase, which includes site-dependent design. Radiation safety design for the ILC is on-going as a part of conventional facility and siting activities of the pre-project phase. The thickness of a central wall of normal concrete is designed to be 3.5 m under a pessimistic assumption of beam loss. The beam loss scenario is under discussion. Experience and knowledge relating to shielding design and radiation control operational work at other laboratories are required. (authors)

78 FR 50079 - Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed...

Science.gov (United States)

2013-08-16

... DEPARTMENT OF THE INTERIOR Bureau of Safety and Environmental Enforcement [Docket ID BSEE-2013-0005; OMB Control Number 1014-0017: 134E1700D2 EEEE500000 ET1SF0000.DAQ000] Information Collection Activities: Safety and Environmental Management Systems (SEMS); Proposed Collection; Comment Request...

Database search for safety information on cosmetic ingredients.

Science.gov (United States)

Pauwels, Marleen; Rogiers, Vera

2007-12-01

Ethical considerations with respect to experimental animal use and regulatory testing are worldwide under heavy discussion and are, in certain cases, taken up in legislative measures. The most explicit example is the European cosmetic legislation, establishing a testing ban on finished cosmetic products since 11 September 2004 and enforcing that the safety of a cosmetic product is assessed by taking into consideration "the general toxicological profile of the ingredients, their chemical structure and their level of exposure" (OJ L151, 32-37, 23 June 1993; OJ L066, 26-35, 11 March 2003). Therefore the availability of referenced and reliable information on cosmetic ingredients becomes a dire necessity. Given the high-speed progress of the World Wide Web services and the concurrent drastic increase in free access to information, identification of relevant data sources and evaluation of the scientific value and quality of the retrieved data, are crucial. Based upon own practical experience, a survey is put together of freely and commercially available data sources with their individual description, field of application, benefits and drawbacks. It should be mentioned that the search strategies described are equally useful as a starting point for any quest for safety data on chemicals or chemical-related substances in general.

Intelligent Information Processing for Enhanced Safety in the NAS, Phase II

Data.gov (United States)

National Aeronautics and Space Administration — Our Phase I work focused on how improved information flow between actors in a flight deck environment can improve safety performance. An operational prototype was...

Intelligent Information Processing for Enhanced Safety in the NAS, Phase I

Data.gov (United States)

National Aeronautics and Space Administration — We propose a system that focuses on how improved information flow between agents acting in a flight deck environment can improve safety performance. Agents are...

Strengthening the culture of safety and performance in nuclear installations

International Nuclear Information System (INIS)

Briant, V.S.; Germann, R.P.

1997-01-01

In mid-1995, the International Atomic Energy Agency (IAEA) in Vienna brought together a group of safety culture experts from around the world to explore and summarize those practices they viewed as important in establishing sound safety cultures in nuclear installations. This paper will summarize key findings of the Vienna team and also expand those ideas based on related work in which the authors are engaged. The paper includes a definition of safety culture, a description of three stages of safety culture, and five key practices essential to establishing and maintaining a sound safety culture. Additionally, the authors contradicts the conventional view of safety and production as trade-offs, supporting the Vienna team's conclusion that the principles, attitudes, and practices which bring about sustained levels of high performance are the same as those which enhance safety. Based on input from colleagues in several countries, this appears to hold true across geographical and ethnic boundaries. The authors also discuss how this information can be put to practical use to obtain an objective, measurable, and repeated assessment of the current state of the safety culture within a company, plant or work unit. With that information, leaders are then in the position to act on any of the several parameters which affect both safety and performance effectiveness. (author)

Safety Assessment for Decommissioning

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-06-15

In the past few decades, international guidance has been developed on methods for assessing the safety of predisposal and disposal facilities for radioactive waste. More recently, it has been recognized that there is also a need for specific guidance on safety assessment in the context of decommissioning nuclear facilities. The importance of safety during decommissioning was highlighted at the International Conference on Safe Decommissioning for Nuclear Activities held in Berlin in 2002 and at the First Review Meeting of the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management in 2003. At its June 2004 meeting, the Board of Governors of the IAEA approved the International Action Plan on Decommissioning of Nuclear Facilities (GOV/2004/40), which called on the IAEA to: ''establish a forum for the sharing and exchange of national information and experience on the application of safety assessment in the context of decommissioning and provide a means to convey this information to other interested parties, also drawing on the work of other international organizations in this area''. In response, in November 2004, the IAEA launched the international project Evaluation and Demonstration of Safety for Decommissioning of Facilities Using Radioactive Material (DeSa) with the following objectives: -To develop a harmonized approach to safety assessment and to define the elements of safety assessment for decommissioning, including the application of a graded approach; -To investigate the practical applicability of the methodology and performance of safety assessments for the decommissioning of various types of facility through a selected number of test cases; -To investigate approaches for the review of safety assessments for decommissioning activities and the development of a regulatory approach for reviewing safety assessments for decommissioning activities and as a basis for regulatory decision making; -To provide a forum

Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

Energy Technology Data Exchange (ETDEWEB)

Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

2011-03-13

This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

Risk-Informing Safety Reviews for Non-Reactor Nuclear Facilities

International Nuclear Information System (INIS)

Mubayi, V.; Azarm, A.; Yue, M.; Mukaddam, W.; Good, G.; Gonzalez, F.; Bari, R.A.

2011-01-01

This paper describes a methodology used to model potential accidents in fuel cycle facilities that employ chemical processes to separate and purify nuclear materials. The methodology is illustrated with an example that uses event and fault trees to estimate the frequency of a specific energetic reaction that can occur in nuclear material processing facilities. The methodology used probabilistic risk assessment (PRA)-related tools as well as information about the chemical reaction characteristics, information on plant design and operational features, and generic data about component failure rates and human error rates. The accident frequency estimates for the specific reaction help to risk-inform the safety review process and assess compliance with regulatory requirements.

77 FR 22387 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

Science.gov (United States)

2012-04-13

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

77 FR 58616 - Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering...

Science.gov (United States)

2012-09-21

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration [Docket No. PHMSA-2012-0024] Pipeline Safety: Information Collection Activities, Revision to Gas Transmission and Gathering Pipeline Systems Annual Report, Gas Transmission and Gathering Pipeline Systems Incident Report...

National Report presented by the Mexican United States to satisfy the compromises of the Nuclear Safety Convention

International Nuclear Information System (INIS)

1998-01-01

In order to satisfy to the compromises derived of the ratification by part of the Mexican Government for the Nuclear Safety Convention it is presented this National Report which is based on the directives proposed as a result of the preparatory meetings held in the IAEA Headquarters in the city of Vienna, Austria. This National Report represents a document summary and activities realized at present in relation with the only nuclear facility in Mexico: the Nuclear Power Plant in Laguna Verde, Veracruz. This report consists of two parts: In the first one it is described how have been satisfied each one of the compromises. The second one talks about the Laws and Regulations on nuclear activities in the country. (Author)

Toward risk assessment 2.0: Safety supervisory control and model-based hazard monitoring for risk-informed safety interventions

International Nuclear Information System (INIS)

Favarò, Francesca M.; Saleh, Joseph H.

2016-01-01

Probabilistic Risk Assessment (PRA) is a staple in the engineering risk community, and it has become to some extent synonymous with the entire quantitative risk assessment undertaking. Limitations of PRA continue to occupy researchers, and workarounds are often proposed. After a brief review of this literature, we propose to address some of PRA's limitations by developing a novel framework and analytical tools for model-based system safety, or safety supervisory control, to guide safety interventions and support a dynamic approach to risk assessment and accident prevention. Our work shifts the emphasis from the pervading probabilistic mindset in risk assessment toward the notions of danger indices and hazard temporal contingency. The framework and tools here developed are grounded in Control Theory and make use of the state-space formalism in modeling dynamical systems. We show that the use of state variables enables the definition of metrics for accident escalation, termed hazard levels or danger indices, which measure the “proximity” of the system state to adverse events, and we illustrate the development of such indices. Monitoring of the hazard levels provides diagnostic information to support both on-line and off-line safety interventions. For example, we show how the application of the proposed tools to a rejected takeoff scenario provides new insight to support pilots’ go/no-go decisions. Furthermore, we augment the traditional state-space equations with a hazard equation and use the latter to estimate the times at which critical thresholds for the hazard level are (b)reached. This estimation process provides important prognostic information and produces a proxy for a time-to-accident metric or advance notice for an impending adverse event. The ability to estimate these two hazard coordinates, danger index and time-to-accident, offers many possibilities for informing system control strategies and improving accident prevention and risk mitigation

Guaranteed safety information for rising traffic safety at roads main junctions using infrastructure-aided driver-assistance systems; Sichere Information durch infrastrukturgestuetzte Fahrerassistenzsysteme zur Steigerung der Verkehrssicherheit an Strassenknotenpunkten

Energy Technology Data Exchange (ETDEWEB)

Wiltschko, T.

2004-07-01

Progress of development of driver assistance systems have more and more lead to systems assisting the driver on guidance level. These systems allow direct or indirect driving process contact thus being safety relevant vehicle systems, and their operation requires high safety and reliability standards. To realize the necessary driver assistance, complete collection and interpretation of traffic actions are required and a number of information and information sources has to be integrated, especially in case of traffic situations at junctions in urban areas. The requirements, however, cannot only be reduced to technical reliability of the system and system components but have also to be extended to the information in- and output thus guaranteeing safe operation. This information has to reach the required quality thus avoiding any hazards during the complete time of information use. It is evident that none of the existing models and methods allow a uniform description of information quality of driver assistance systems. The thesis shows a quality concept for description and evaluation of information quality within information processing systems. The quality concept consists of a quality model and an analysing procedure. The quality model is the basis of the quality concept. All types of information are described by a fixed set of quality characteristic, and suitable parameters are used for concretion and quantification. (orig.)

Bases for protection against radiation and conventional hazards

International Nuclear Information System (INIS)

Ganguly, A.K.

1977-01-01

The living and working environment of man is polluted by : (1) ionizing radiations, both natural and man-made, (2) man-made non-ionizing radiations e.g. microwaves, and (3) man-made chemicals. Many of these agents are carcinogenic and mutagenic. The basic radiation safety standards laid down by the ICRP have long-term objectives and take into account all aspects of radiation protection problem, but in the case of other agents the safety standards, whatever few are available, have short-term objectives and differ widely from country to country. If the paramountcy of man's health is accepted as the objective of all safety programmes i.e. either for radiation hazards or conventional hazards, the above disparity must be removed. In order to achieve this goal, just as assessment of damage to organs and tissues of man is available in the case of ionizing radiations, similar assessment in the case of conventional hazards must be made available by collecting relevant data. (M.G.B.)

Guidelines for nuclear-power-plant safety-issue prioritization information development

International Nuclear Information System (INIS)

Andrews, W.B.; Gallucci, R.H.V.; Konzek, G.J.

1983-05-01

This is the second in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues. This report contains results of issue-specific analyses for 15 issues. Each issue was considered within the contraints of available information as of September 1982 and two staff-weeks of labor. The results will be referenced, as one consideration in setting priorities for reactor safety issues, in an NRC prioritization report to be published at a future date

Why consumers behave as they do with respect to food safety and risk information

DEFF Research Database (Denmark)

Verbeke, Wim; Frewer, Lynn J.; Scholderer, Joachim

2007-01-01

rankings. The aim of this contribution is to provide a better understanding to food risk analysts of why consumers behave as they do with respect to food safety and risk information. This paper presents some cases of seemingly irrational and inconsistent consumer behaviour with respect to food safety...... and risk information and provides explanations for these behaviours based on the nature of the risk and individual psychological processes. Potential solutions for rebuilding consumer confidence in food safety and bridging between lay and expert opinions towards food risks are reviewed. These include......In recent years, it seems that consumers are generally uncertain about the safety and quality of their food and their risk perception differs substantially from that of experts. Hormone and veterinary drug residues in meat persist to occupy a high position in European consumers' food concern...

Using Active Learning to Identify Health Information Technology Related Patient Safety Events.

Science.gov (United States)

Fong, Allan; Howe, Jessica L; Adams, Katharine T; Ratwani, Raj M

2017-01-18

The widespread adoption of health information technology (HIT) has led to new patient safety hazards that are often difficult to identify. Patient safety event reports, which are self-reported descriptions of safety hazards, provide one view of potential HIT-related safety events. However, identifying HIT-related reports can be challenging as they are often categorized under other more predominate clinical categories. This challenge of identifying HIT-related reports is exacerbated by the increasing number and complexity of reports which pose challenges to human annotators that must manually review reports. In this paper, we apply active learning techniques to support classification of patient safety event reports as HIT-related. We evaluated different strategies and demonstrated a 30% increase in average precision of a confirmatory sampling strategy over a baseline no active learning approach after 10 learning iterations.

Geo-scientific Information in the Radioactive Waste Management Safety Case Main Messages from the AMIGO Project

International Nuclear Information System (INIS)

2010-01-01

Radioactive waste is associated with all phases of the nuclear fuel cycle as well as the use of radioactive materials in medicine, research and industry. For the most hazardous and long-lived waste, the solution being investigated worldwide is disposal in engineered repositories deep underground. The importance of geo-scientific information in selecting a site for geological disposal has long been recognised, but there has been growing acknowledgement of the broader role of this information in assessing and documenting the safety of disposal. The OECD/NEA Approaches and Methods for Integrating Geological Information in the Safety Case (AMIGO) project has demonstrated that geological data and understanding serve numerous roles in safety cases. The project, which ran from 2002 to 2008, underscored the importance of integrating geo-scientific information in the development of a disposal safety case and increasingly in the overall process of repository development, including, for example, siting decisions and ensuring the practical feasibility of repository layout and engineering. (authors)

Meeting challenges through good practice. Using the highlights from the third review meeting of the Convention on Nuclear Safety to improve national regulatory systems

International Nuclear Information System (INIS)

Keen, L.J.; Cameron, J.K.

2006-01-01

The third review meeting of the Convention on Nuclear Safety (CNS), held in April 2005, demonstrated collective progress on ensuring worldwide nuclear safety. The Contracting Parties highlighted areas of focus to be brought back to the fourth review meeting and also committed to a continuity process to revitalize the review processes under the CNS. Specific progress has been achieved in the first year since the conclusion of the third review meeting, but further commitment to progress is required, by the Contracting Parties and the Secretariat of the IAEA, over the next year, especially if changes to the review processes are to be achieved for the fourth review meeting in 2008. (author)

Risk and safety in the nuclear industry and conventional norms of society

International Nuclear Information System (INIS)

Tadmor, J.

1977-01-01

The societal acceptance of various risks is analyzed and rules of risk acceptance as a function of different parameters (e. g., expected benefit, intensity of effect) are spelled out. The monetary value of a human life is estimated, based on investments in safety of different human activities. The acceptable risks and safety investments in different human activities are then compared with risks and safety investments of the nuclear industry. Safety investments required to reduce radioactivity releases and risks from nuclear power stations to ALAP (as low as practiable) levels are taken as a study case. It is found that risks in the nuclear industry are several orders of magnitude lower and safety investments per human life saved are several orders of magnitude higher, as compared with risks and safety investments in other human activities

Government of Canada Initiatives in Support of the Joint Convention

International Nuclear Information System (INIS)

Brown, P.A.; Metcalfe, D.E.; Lojk, R.

2006-01-01

The Government of Canada strongly supported international efforts to bring into force the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management (the Joint Convention), and was the second country to ratify it. The Joint Convention places a number of obligations on Contracting Parties aimed at achieving and maintaining a high level of safety worldwide in spent fuel and radioactive waste management, ensuring that effective defenses against potential hazards are in place during all management stages, preventing accidents with radiological consequences and mitigating their consequences should they occur. In addition to establishing and maintaining a modem regulatory framework and an independent regulatory body through the 2000 Nuclear Safety and Control Act, the Government of Canada has implemented a number of initiatives that address its responsibilities and serve to further enhance Canada's compliance with the Joint Convention. For nuclear fuel waste, the Government of Canada brought into force the Nuclear Fuel Waste Act in 2002 to require waste owners to develop, fund, organize and implement a long-term solution for Canada's nuclear fuel waste. The Act clearly reserves for Government the decision on the solution to be implemented in the best interests of Canadians, as well as oversight to ensure that waste owners are fulfilling their responsibilities. In the case of low-level radioactive waste, long-term solutions are being developed to ensure the protection of health, safety, and the environment, both now and in the future. Regarding uranium mine and mill tailings, current operators have state-of-the-art waste management facilities in place. The Government of Canada works with provincial governments to ensure that any potential abandoned or legacy mines sites where no owner can be held responsible are safely decommissioned and managed over the long term. (authors)

78 FR 71036 - Pipeline Safety: Random Drug Testing Rate; Contractor Management Information System Reporting...

Science.gov (United States)

2013-11-27

... PHMSA-2013-0248] Pipeline Safety: Random Drug Testing Rate; Contractor Management Information System Reporting; and Obtaining Drug and Alcohol Management Information System Sign-In Information AGENCY: Pipeline... Management Information System (MIS) Data; and New Method for Operators to Obtain User Name and Password for...

Guidelines for nuclear power plant safety issue prioritization information development. Supplement 2

International Nuclear Information System (INIS)

Andrews, W.B.; Gallucci, R.H.V.; Konzek, G.J.; Heaberlin, S.W.; Fecht, B.A.; Allen, C.H.; Allen, R.D.; Bickford, W.E.; Carbaugh, E.H.; Lewis, J.R.

1983-12-01

This is the third in a series of reports to document the use of a methodology developed by the Pacific Northwest Laboratory to calculate, for prioritization purposes, the risk, dose and cost impacts of implementing resolutions to reactor safety issues (NUREG/CR-2800, Andrews et al. 1983). This report contains results of issue-specific analyses for 31 issues. Each issue was considered within the constraints of available information as of summer 1983, and two staff-weeks of labor. The results are referenced, as one consideration in setting priorities for reactor safety issues, in NUREG-0933, A Prioritization of Generic Safety Issues

Risk and safety in the nuclear industry and conventional norms of society

International Nuclear Information System (INIS)

Tadmor, J.

In the present study the societal acceptance of various risks is analyzed and rules of risk acceptance as a function of different parameters are spelled out. The monetary value of a human life is estimated, based on investments in safety of different human activities. The acceptable risks and safety investments in different human activities are then compared with risks and safety investments of the nuclear industry. Safety investments required to reduce the radioactivity releases and risks from nuclear power stations to ALAP levels are taken as a study case. It is found that risks in the nuclear industry are several orders of magnitude lower and safety investments per human life saved are several orders of magnitude higher, as compared with risks and safety investments in other human activities. It is also shown that the incremental safety investments needed to further reduce the radiation doses in the environment during normal and continuous operation of nuclear plants are extravagantly high as compared to safety investments in other human activities and in other facets of human life. Considering that there is a limit to the economic means available, societal expenditures for reducing risks should by spread, as much as possible, over all human activities to get the maximum return from investments. (B.G.)

Convention on supplementary compensation for nuclear damage

International Nuclear Information System (INIS)

Chinese Nuclear Society, Beijing; U.S. Nuclear Energy Institute

2000-01-01

The Contracting parties recognize the importance of the measures provided in the Vienna Convention on Civil Liability for Nuclear Damage and the Paris Convention on Third party liability in the Field of Nuclear Energy as well as in national legislation on compensation for nuclear damage consistent with the principles of these conventions. The Contracting parties desire to establish a worldwide liability regime to supplement and enhance these measures with a view to increasing the amount of compensation for nuclear damage and encourage regional and global co-operation to promote a higher level of nuclear safety in accordance with the principle of international partnership and solidarity

RESI-1 and RESI-2: pPrototypes of an information system on reactor safety

International Nuclear Information System (INIS)

Schultheiss, G.F.; Eglin, W.; Katz, F.W.; Krings, T.; Pee, A.; Schlechtendahl, E.G.

1975-04-01

To demonstrate by practical experience the feasibility of the information system elaborated in the 'Study of an Information System on Reactor Safety RESI' (KFK 1900), the prototype systems RESI-1 and RESI-2 were developed and tested in operation. The two systems have been considerably reduced both in extent and contents as compared to the information system described in the study. The RESI-1 prototype system is a paper version established for verification of all the individual functions before passing over to the computer-aided interactive version RESI-2. RESI-2 is based on the GOLEM system of Siemens. Both protoype systems have proved that the essential features: 1) documentation, 2) formulation of and answering to safety questions, which are relevant with respect to particular licensing cases, 3) formulation of safety questions related to individual reactor types can be managed satisfactorily. All the functions of information retrieval have been tested carefully over several months. Particularities of project development and of the methods elaborated are described in detail and presented in this report. (orig.) [de

Increase plant safety and reduce cost by implementing risk-informed in-service inspection programs

International Nuclear Information System (INIS)

Billington, A.; Monette, P.

2001-01-01

The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less that 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used to improve the effectiveness of inspecting safety-significant piping components, to reduce inspection requirements on other piping components, to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure, and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits from past projects is presented, since the methodology is applicable for WWER plant design. (author)

Increase plant safety and reduce cost by implementing risk-informed In-Service Inspection programs

International Nuclear Information System (INIS)

Billington, A.; Monette, P.; Doumont, C.

2000-01-01

The idea behind the program is that it is possible to 'inspect less, but inspect better'. In other words, the risk-informed In-Service Inspection (ISI) process is used to improve the effectiveness of examination of piping components, i.e. concentrate inspection resources and enhance inspection strategies on high safety significant locations, and reduce inspection requirements on others. The Westinghouse Owners Group (WOG) risk-informed ISI process has already been applied for full scope (Millstone 3, Surry 1) and limited scope (Beznau, Ringhals 4, Asco, Turkey Point 3). By examining the high safety significant piping segments for the different fluid piping systems, the total piping core damage frequency is reduced. In addition, more than 80% of the risk associated with potential pressure boundary failures is addressed with the WOG risk-informed ISI process, while typically less than 50% of this same risk is addressed by the current inspection programs. The risk-informed ISI processes are used: to improve the effectiveness of inspecting safety-significant piping components; to reduce inspection requirements on other piping components; to evaluate improvements to plant availability and enhanced safety measures, including reduction of personnel radiation exposure; and to reduce overall Operation and Maintenance (O and M) costs while maintaining regulatory compliance. A description of the process as well as benefits of past projects is presented, since the methodology is applicable for VVER plant design. (author)

78 FR 10200 - Proposed Information Collection; Captive Wildlife Safety Act

Science.gov (United States)

2013-02-13

... DEPARTMENT OF THE INTERIOR Fish and Wildlife Service [FWS-HQ-LE-2013-N020; FF09L00200-FX-LE12200900000] Proposed Information Collection; Captive Wildlife Safety Act AGENCY: Fish and Wildlife Service, Interior. ACTION: Notice; request for comments. SUMMARY: We (U.S. Fish and Wildlife Service) will ask the...

Decree No 87-137 of 2 March 1987 concerning the High Council for nuclear safety and information

International Nuclear Information System (INIS)

1987-01-01

This Decree amends the Decree of 13th March 1973 setting up a High Council for Nuclear Safety. Its purpose is to widen the terms of reference of the High Council for Nuclear Safety. In addition to its responsibilities as regards the safety of nuclear installations, it is now competent in the field of information. The Council is now charged with informing the media as well as the public not only on questions of safety proper but also on incidents and accidents occurring in nuclear installations. (NEA) [fr

Pesticide Health and Safety Information

Science.gov (United States)

Animal Health Safe Use Practices Pest Control Food Safety Low Risk Pesticides Integrated Pest Management directed by the product label. Pesticides may be ingested if stored improperly in food or beverage ; Environment Human Health Animal Health Safe Use Practices Food Safety Environment Air Water Soil Wildlife

Strengthening the culture of safety and performance in nuclear installations

Energy Technology Data Exchange (ETDEWEB)

Briant, V S [GPU Nuclear, Parsippany (United States); Germann, R P [Aberdeen Center for Team Learning, Matawan (United States)

1997-07-01

In mid-1995, the International Atomic Energy Agency (IAEA) in Vienna brought together a group of safety culture experts from around the world to explore and summarize those practices they viewed as important in establishing sound safety cultures in nuclear installations. This paper will summarize key findings of the Vienna team and also expand those ideas based on related work in which the authors are engaged. The paper includes a definition of safety culture, a description of three stages of safety culture, and five key practices essential to establishing and maintaining a sound safety culture. Additionally, the authors contradicts the conventional view of safety and production as trade-offs, supporting the Vienna team`s conclusion that the principles, attitudes, and practices which bring about sustained levels of high performance are the same as those which enhance safety. Based on input from colleagues in several countries, this appears to hold true across geographical and ethnic boundaries. The authors also discuss how this information can be put to practical use to obtain an objective, measurable, and repeated assessment of the current state of the safety culture within a company, plant or work unit. With that information, leaders are then in the position to act on any of the several parameters which affect both safety and performance effectiveness. (author) 9 refs., 5 tabs.

77 FR 28602 - Agency Information Collection Activities; Proposed Collection; Comment Request; Early Food Safety...

Science.gov (United States)

2012-05-15

... appropriate, and other forms of information technology. Early Food Safety Evaluation of New Non-Pesticidal... Evaluation of New Non-Pesticidal Proteins Produced by New Plant Varieties Intended for Food Use AGENCY: Food... for early food safety evaluation of new non-pesticidal proteins produced by new plant varieties...

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)

THE PROTECTION OF CONSUMER RIGHTS FOR AVIATION SAFETY AND SECURITY IN INDONESIA AND MALAYSIA

Directory of Open Access Journals (Sweden)

Annalisa Yahanan

2017-01-01

Full Text Available Indonesia and Malaysia have a good potency for cooperation in aviation industry. It can be seen in the establishing two aviation companies namely PT. Indonesia Air Asia and Malindo which both are low-cost carrier. These aviation industries are categorized as low-cost carrier, however safety and security are absolute factors because these are rights for consumers. This article will describe further about safety and security standard; protecting the rights for consumers in connection with safety aviation in Indonesia and Malaysia from the Consumer Protection Law and the Aviation Law. As a result of the research shows that safety standard passenger for air transportation in airport covers information and safety facility in the shape of availability of the emergency safety tools (fires, accidents and natural disasters; information, area and health facility; and healthcare workers. Moreover, safety standards for passenger in an aircraft include information and safety facility in the shape of availability information and the emergency safety tools for passenger in an aircraft. The protection for consumer rights for safety flight in Indonesia as follows: aviation industry has obligation to fulfill minimum standard of safety and security; consumers must be safety from false information which raises concern; aircraft operation which endanger of the passenger; and consumer protection in operating the electronic device which endanger flight. On the other hand, the law of consumer rights in Malaysia relating to aviation are ruled under the Aviation Law as a result of the Warsaw Convention 1929. In conclusion, the verdict of consumer rights related to security aviation begins when the passenger enter to an aircraft, in the aircraft, and by the time they get off the plane.

Planned activities to improve safety

International Nuclear Information System (INIS)

1998-01-01

This document presents the fulfilling of the Brazilian obligations under the Convention on Nuclear Safety. The Chapter 6 of the document contains some details about the planed activities to safety improvements

High committee for nuclear safety transparency and information. December 18, 2008 meeting

International Nuclear Information System (INIS)

2008-12-01

The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 6 main topics: 1 - a presentation of nuclear medicine by Prof. Devaux, of its domains of application and the respect of radiation protection rules; 2 - the launching of a working group on the transparency/secrecy problem with nuclear activities; 3 - the elaboration of an environmental radioactivity index by the nuclear safety authority (ASN); 4 - the order addressed to the Cruas nuclear facility for the lack of standardized marking and maintenance of pipes used for the transport of explosive fluids; 5 - the consequences of the blocking of 2 fuel assemblies (out of 157) in the Tricastin reactor core; 6 - the flood at the Tricastin site, its origin and consequences. (J.S.)

Effectiveness of transmitting safety-measures information in risk communication of nuclear power generation. Evaluation by the receiver of the messages

International Nuclear Information System (INIS)

Matsumoto, Takanobu; Shiomi, Tetsuro

2004-01-01

Effectiveness of risk communication were previously discussed through both ''risk information'' and ''benefit information'' of its topics. However, in technical facilities facilities such as nuclear power plant where safeness is an important concern, not only these two aspects but also safety-measures information'' are required. There have been previously no such discussions about risk communication that included ''safety-measures information''. In this report, we investigated general public's view of the difference in effectiveness of risk communication between two cases. In the first case, only ''risk'' and ''benefit information'' were given. In the second case, we added ''safety-measures information'' as well as ''risk'' and benefit information''. Measurement of the effect was performed using a questionnaire. We divided the subjects into two groups. Each group was shown one side of two pamphlets which had information concerning two conditions, and asked how it feels about ''reliance on information'', ''reliance on informer'', ''posture considered with informer'' which are factors in the process of the attitude change that is shown in the paradigm of risk communication (Kinoshita and Kikkawa, (1990)). Prior to this investigation, we identified each subject is position on nuclear power generation. Thus we were able to clarify the effectiveness of each risk communication style depending on each subject is position (approval, neutrality, objection). As a result, we reached the following conclusions: First about ''reliance on information'', where asked whether the contents of a pamphlet would be reliable, it was found that the person negative to nuclear power generation evaluated lower the pamphlet which included ''safety-measures information'' than the other. However, it was found that regardless of the difference in the position towards nuclear power generation, people who read the pamphlet including ''safety-measures information'' evaluated higher ''reliance on

Efficient improvement of nuclear power plant safety by reorganization of risk-informed safety importance evaluation methods for piping welded portions

Energy Technology Data Exchange (ETDEWEB)

Irie, Takashi; Hanafusa, Hidemitsu; Suyama, Takeshi [Institute of Nuclear Safety System, Inc., Mihama, Fukui (Japan); Morota, Hidetsugu; Kojima, Sigeo; Mizuno, Yoshinobu [Computer Software Development Co., Ltd., Tokyo (Japan)

2002-09-01

In this work, risk information was used to evaluate the safety importance of piping welded portions which were important for plant operation and maintenance of nuclear power plants. There are two types of risk-informed safety importance evaluation methods, namely the ASME method and the EPRI method. Since both methods have advantages and disadvantages, elements of each method were combined and reorganized. Considerations included whether the degradation mechanisms would be objectively evaluated and whether plant safety would be efficiently improved. The most objective and efficient method was as follows. Piping failure potential is quantitatively and objectively evaluated for failure with probabilistic fracture mechanics (PFM) and for other degradation mechanisms with empirical failure rates, and conditional core damage probability (CCDP) is calculated with PSA. This method reduces the inspected segment numbers to 1/4 of the deterministic method and increases the ratio of risk, which is covered by the inspected segments, to total risk from 80% of the deterministic method to 95%. Piping inspection numbers decreased for safety injection systems that were required the inspections by the deterministic method. Piping inspections were required for part of main feed water and main steam systems that were not required the inspections by the deterministic method. (author)

Management of safety, safety culture and self assessment

International Nuclear Information System (INIS)

Carnino, A.

2000-01-01

Safety management is the term used for the measures required to ensure that an acceptable level of safety is maintained throughout the life of an installation, including decommissioning. The safety culture concept and its implementation are described in part one of the paper. The principles of safety are now quite well known and are implemented worldwide. It leads to a situation where harmonization is being achieved as indicated by the entry into force of the Convention on Nuclear Safety. To go beyond the present nuclear safety levels, management of safety and safety culture will be the means for achieving progress. Recent events which took place in major nuclear power countries have shown the importance of the management and the consequences on safety. At the same time, electricity deregulation is coming and will impact on safety through reductions in staffing and in operation and maintenance cost at nuclear installations. Management of safety as well as its control and monitoring by the safety authorities become a key to the future of nuclear energy.(author)

Addressing the fundamental issues in reliability evaluation of passive safety of AP1000 for a comparison with active safety of PWR

International Nuclear Information System (INIS)

Hashim Muhammad; Yoshikawa, Hidekazu; Yang Ming

2013-01-01

Passive safety systems adopted in advanced Pressurized Water Reactor (PWR), such as AP1000 and EPR, should attain higher reliability than the existing active safety systems of the conventional PWR. The objective of this study is to discuss the fundamental issues relating to the reliability evaluation of AP1000 passive safety systems for a comparison with the active safety systems of conventional PWR, based on several aspects. First, comparisons between conventional PWR and AP1000 are made from the both aspects of safety design and cost reduction. The main differences between these PWR plants exist in the configurations of safety systems: AP1000 employs the passive safety system while reducing the number of active systems. Second, the safety of AP1000 is discussed from the aspect of severe accident prevention in the event of large break loss of coolant accidents (LOCA). Third, detailed fundamental issues on reliability evaluation of AP1000 passive safety systems are discussed qualitatively by using single loop models of safety systems of both PWRs plants. Lastly, methodology to conduct quantitative estimation of dynamic reliability for AP1000 passive safety systems in LOCA condition is discussed, in order to evaluate the reliability of AP1000 in future by a success-path-based reliability analysis method (i.e., GO-FLOW). (author)

Influence of health and environmental information on hedonic evaluation of organic and conventional bread.

Science.gov (United States)

Annett, L E; Muralidharan, V; Boxall, P C; Cash, S B; Wismer, W V

2008-05-01

Grain from paired samples of the hard red spring wheat cultivar "Park" grown on both conventionally and organically managed land was milled and baked into 60% whole wheat bread. Consumers (n= 384) rated their liking of the bread samples on a 9-point hedonic scale before (blind) and after (labeled) receiving information about organic production. Consumers liked organic bread more (P bread under blind and labeled conditions. Environmental information about organic production did not impact consumer preference changes for organic bread, but health information coupled with sensory evaluation increased liking of organic bread. Ordinary least squares (OLS) and binary response (probit) regression models identified that postsecondary education, income level, frequency of bread consumption, and proenvironmental attitudes played a significant role in preference changes for organic bread. The techniques used in this study demonstrate that a combination of sensory and econometric techniques strengthens the evaluation of consumer food choice.

DART - for design basis justification and safety related information management

International Nuclear Information System (INIS)

Billington, A.; Blondiaux, P.; Boucau, J.; Cantineau, B.; Doumont, C.; Mared, A.

2000-01-01

DART is the acronym for Design Analysis Re-engineering Tool. It embodies a systematic and integrated approach to NPP safety re-assessment and configuration management, that makes use of Reverse Failure Mode and Effect Analysis in conjunction with a state-of-the-art relational database and a standardized data format, to permit long-term management of plant safety related information. The plant design is reviewed in a step-by-step logical fashion by constructing fault trees that identify the link between undesired consequences and their causes. Each failure cause identified in a fault tree is addressed by defining functional requirements, which are in turn addressed by documenting the specific manner in which the plant complies with the requirement. The database can be used to generate up-to-date plant safety related documents, including: SAR, Systems Descriptions, Technical Specifications and plant procedures. The approach is open-minded by nature and therefore is not regulatory driven, however the plant licensing basis will also be reviewed and documented within the same database such that a Regulatory Conformance Program may be integrated with the other safety documentation. This methodology can thus reconstitute the plant design bases in a comprehensive and systematic way, while allowing to uncover weaknesses in design. The original feature of the DART methodology is that it links all the safety related documents together, facilitating the evaluation of the safety impact resulting from any plant modification. Due to its capability to retrieve the basic justifications of the plant design, it is also a useful tool for training the young generation of plant personnel. The DART methodology has been developed for application to units 2, 3 and 4 at Vattenfall's Ringhals site in Sweden. It may be applied to any nuclear power plant or industrial facility where public safety is a concern. (author)

DART - for design basis justification and safety related information management

International Nuclear Information System (INIS)

Billington, A.; Blondiaux, B.; Boucau, J.; Cantineau, B.; Mared, A.

2001-01-01

DART is the acronym for Design Analysis Re-Engineering Tool. It embodies a systematic and integrated approach to NPP safety re-assessment and configuration management, that makes use of Reverse Failure Mode and Effect Analysis in conjunction with a state-of-the-art relational database and a standardized data format, to permit long-term management of plant safety related information. The plant design is reviewed in a step-by-step logical fashion by constructing fault trees that identify the link between undesired consequences and their causes. Each failure cause identified in a fault tree is addressed by defining functional requirements, which are in turn addressed by documenting the specific manner in which the plant complies with the requirement. The database can then be used to generate up-to-date plant safety related documents, including: SAR, Systems Descriptions, Technical Specifications and plant procedures. The approach is open-minded by nature and therefore is not regulatory driven, however the plant licensing basis will also be reviewed and documented within the same database such that a Regulatory Conformance Program may be integrated with the other safety documentation. This methodology can thus reconstitute the plant design bases in a comprehensive and systematic way, while allowing to uncover weaknesses in design. The original feature of the DART methodology is that it links all the safety related documents together, facilitating the evaluation of the safety impact resulting from any plant modification. Due to its capability to retrieve the basic justifications of the plant design, it is also a useful tool for training the young generation of plant personnel. The DART methodology has been developed for application to units 2, 3 and 4 at Vattenfall's Ringhals site in Sweden. It may be applied to any nuclear power plant or industrial facility where public safety is a concern. (author)

Information System Hazard Analysis: A Method for Identifying Technology-induced Latent Errors for Safety.

Science.gov (United States)

Weber, Jens H; Mason-Blakley, Fieran; Price, Morgan

2015-01-01

Many health information and communication technologies (ICT) are safety-critical; moreover, reports of technology-induced adverse events related to them are plentiful in the literature. Despite repeated criticism and calls to action, recent data collected by the Institute of Medicine (IOM) and other organization do not indicate significant improvements with respect to the safety of health ICT systems. A large part of the industry still operates on a reactive "break & patch" model; the application of pro-active, systematic hazard analysis methods for engineering ICT that produce "safe by design" products is sparse. This paper applies one such method: Information System Hazard Analysis (ISHA). ISHA adapts and combines hazard analysis techniques from other safety-critical domains and customizes them for ICT. We provide an overview of the steps involved in ISHA and describe.

The use of information technology to enhance patient safety and nursing efficiency.

Science.gov (United States)

Lee, Tso-Ying; Sun, Gi-Tseng; Kou, Li-Tseng; Yeh, Mei-Ling

2017-10-23

Issues in patient safety and nursing efficiency have long been of concern. Advancing the role of nursing informatics is seen as the best way to address this. The aim of this study was to determine if the use, outcomes and satisfaction with a nursing information system (NIS) improved patient safety and the quality of nursing care in a hospital in Taiwan. This study adopts a quasi-experimental design. Nurses and patients were surveyed by questionnaire and data retrieval before and after the implementation of NIS in terms of blood drawing, nursing process, drug administration, bar code scanning, shift handover, and information and communication integration. Physiologic values were easier to read and interpret; it took less time to complete electronic records (3.7 vs. 9.1 min); the number of errors in drug administration was reduced (0.08% vs. 0.39%); bar codes reduced the number of errors in blood drawing (0 vs. 10) and transportation of specimens (0 vs. 0.42%); satisfaction with electronic shift handover increased significantly; there was a reduction in nursing turnover (14.9% vs. 16%); patient satisfaction increased significantly (3.46 vs. 3.34). Introduction of NIS improved patient safety and nursing efficiency and increased nurse and patient satisfaction. Medical organizations must continually improve the nursing information system if they are to provide patients with high quality service in a competitive environment.

High committee for nuclear safety transparency and information. October 8, 2009 meeting

International Nuclear Information System (INIS)

2009-10-01

The high committee for the nuclear safety transparency and information (HCTISN) is an information, consultation and debate authority devoted to the assessment of the risks linked with nuclear activities and to the analysis of their impact on public health, on the environment and on nuclear safety. Each year, the HCTISN organizes several ordinary meetings in order to analyze some specific topics of the moment. This meeting was organized around 3 main points: 1 - the progress of the different working groups work: elaboration of a communication scale, comparable to the INES scale, for the evaluation of environmental radioactivity, the realisation of a web site for the HCTISN, the question of transparency and secrecy around the maritime transportation of radioactive materials after the visit by the High Committee of two ships from the British INS company; 2 - the management of radioactive wastes with the concept of storage reversibility: political, technical and decisional aspects, position of the National Evaluation Committee for the researches and studies relative to radioactive materials and wastes management (CNE), position of the ANCLI (French national association of local information commissions), debate; 3 - the shortage of radio-physicists in France and the information of populations and patients (declaration of incidents). Some miscellaneous points are reported as well: the first draft of the first annual report of the HCTISN, development of a societal approach for the research programs of the French institute of radiation protection and nuclear safety (IRSN), validation of a collaboration proposal with the ANCLI. (J.S.)

Routine conventional karyotyping of lymphoma staging bone marrow samples does not contribute clinically relevant information.

Science.gov (United States)

Nardi, Valentina; Pulluqi, Olja; Abramson, Jeremy S; Dal Cin, Paola; Hasserjian, Robert P

2015-06-01

Bone marrow (BM) evaluation is an important part of lymphoma staging, which guides patient management. Although positive staging marrow is defined as morphologically identifiable disease, such samples often also include flow cytometric analysis and conventional karyotyping. Cytogenetic analysis is a labor-intensive and costly procedure and its utility in this setting is uncertain. We retrospectively reviewed pathological reports of 526 staging marrow specimens in which conventional karyotyping had been performed. All samples originated from a single institution from patients with previously untreated Hodgkin and non-Hodgkin lymphomas presenting in an extramedullary site. Cytogenetic analysis revealed clonal abnormalities in only eight marrow samples (1.5%), all of which were positive for lymphoma by morphologic evaluation. Flow cytometry showed a small clonal lymphoid population in three of the 443 morphologically negative marrow samples (0.7%). Conventional karyotyping is rarely positive in lymphoma staging marrow samples and, in our cohort, the BM karyotype did not contribute clinically relevant information in the vast majority of cases. Our findings suggest that karyotyping should not be performed routinely on BM samples taken to stage previously diagnosed extramedullary lymphomas unless there is pathological evidence of BM involvement by lymphoma. © 2015 Wiley Periodicals, Inc.

Enhancing operational nuclear safety

International Nuclear Information System (INIS)

Sengoku, Katsuhisa

2008-01-01

Since Chernobyl, the dictum A n accident anywhere is an accident everywhere i s a globally shared perception. The paper presents challenges to the international nuclear community: globalization, sustainable and dynamic development, secure, safe and clean energy supply, nuclear r enaissance , public concern for nuclear safety, nuclear security, and technology and management. Strong national safety infrastructures and international cooperation are required to maintain a high level of nuclear safety and security worldwide. There is an increasing number of countries thinking of going nuclear: Morocco, Indonesia, Iran, Poland, Turkey, Bangladesh, Egypt, Vietnam, Chile, Nigeria, Malaysia, Thailand, Uruguay, Tunisia, Algeria. Another serious incident will jeopardize the prospect of nuclear renaissance. Safety and security are preconditions for countries newly introducing NPP as well as for those with mature nuclear programmes. The Global Nuclear Safety Regime (GNSR) is referred to as the institutional, legal and technical framework to achieve worldwide implementation of the safety of nuclear installations. At the top of the framework is the Convention on Nuclear Safety which covers the nuclear power plants. The convention has 56 contracting parties which meet triennially where national reports are presented and subject to the review of peers. The International Atomic Energy Agency (IAEA) undertakes a programme to foster the GNSR through the establishment of IAEA safety standards and related publications. The programme provides for the application of standards for the (1) safety of nuclear installations, (2) safety of radioactive sources, (3) safe transport of radioactive material and (4) management of radioactive waste. It also provides for the security of nuclear installations, nuclear material and radioactive material. The safety standards hierarchy is as follows: safety fundamental, safety requirements and safety guides. The safety fundamentals are the bases for IAEA

A comparative review of patient safety initiatives for national health information technology

DEFF Research Database (Denmark)

Magrabi, Farah; Aarts, Jos; Nøhr, Christian

2013-01-01

OBJECTIVE: To collect and critically review patient safety initiatives for health information technology (HIT). METHOD: Publicly promulgated set of advisories, recommendations, guidelines, or standards potentially addressing safe system design, build, implementation or use were identified...... by searching the websites of regional and national agencies and programmes in a non-exhaustive set of exemplar countries including England, Denmark, the Netherlands, the USA, Canada and Australia. Initiatives were categorised by type and software systems covered. RESULTS: We found 27 patient safety initiatives...... were aimed at certification in the USA, Canada and Australia. Safety is addressed alongside interoperability in the Australian certification programme but it is not explicitly addressed in the US and Canadian programmes, though conformance with specific functionality, interoperability, security...

What does my patient's coronary artery calcium score mean? Combining information from the coronary artery calcium score with information from conventional risk factors to estimate coronary heart disease risk

Directory of Open Access Journals (Sweden)

Pletcher Mark J

2004-08-01

Full Text Available Abstract Background The coronary artery calcium (CAC score is an independent predictor of coronary heart disease. We sought to combine information from the CAC score with information from conventional cardiac risk factors to produce post-test risk estimates, and to determine whether the score may add clinically useful information. Methods We measured the independent cross-sectional associations between conventional cardiac risk factors and the CAC score among asymptomatic persons referred for non-contrast electron beam computed tomography. Using the resulting multivariable models and published CAC score-specific relative risk estimates, we estimated post-test coronary heart disease risk in a number of different scenarios. Results Among 9341 asymptomatic study participants (age 35–88 years, 40% female, we found that conventional coronary heart disease risk factors including age, male sex, self-reported hypertension, diabetes and high cholesterol were independent predictors of the CAC score, and we used the resulting multivariable models for predicting post-test risk in a variety of scenarios. Our models predicted, for example, that a 60-year-old non-smoking non-diabetic women with hypertension and high cholesterol would have a 47% chance of having a CAC score of zero, reducing her 10-year risk estimate from 15% (per Framingham to 6–9%; if her score were over 100, however (a 17% chance, her risk estimate would be markedly higher (25–51% in 10 years. In low risk scenarios, the CAC score is very likely to be zero or low, and unlikely to change management. Conclusion Combining information from the CAC score with information from conventional risk factors can change assessment of coronary heart disease risk to an extent that may be clinically important, especially when the pre-test 10-year risk estimate is intermediate. The attached spreadsheet makes these calculations easy.

The electronic security partnership of safety/security and information systems departments.

Science.gov (United States)

Yow, J Art

2012-01-01

The ever-changing world of security electronics is reviewed in this article. The author focuses on its usage in a hospital setting and the need for safety/security and information systems departments to work together to protect and get full value from IP systems.

14 CFR 193.5 - How may I submit safety or security information and have it protected from disclosure?

Science.gov (United States)

2010-01-01

... SUBMITTED INFORMATION § 193.5 How may I submit safety or security information and have it protected from... 14 Aeronautics and Space 3 2010-01-01 2010-01-01 false How may I submit safety or security information and have it protected from disclosure? 193.5 Section 193.5 Aeronautics and Space FEDERAL AVIATION...

Patient and nurse safety: how information technology makes a difference.

Science.gov (United States)

Simpson, Roy L

2005-01-01

The Institute of Medicine's landmark report asserted medical error is seldom the fault of individuals, but the result of faulty healthcare policy/procedure systems. Numerous studies have shown that information technology can shore up weak systems. For nursing, information technology plays a key role in protecting patients by eliminating nursing mistakes and protecting nurses by reducing their negative exposure. However, managing information technology is a function of managing the people who use it. This article examines critical issues that impact patient and nurse safety, both physical and professional. It discusses the importance of eliminating the culture of blame, the requirements of process change, how to implement technology in harmony with the organization and the significance of vision.

Human and organizational biases affecting the management of safety

Energy Technology Data Exchange (ETDEWEB)

Reiman, Teemu, E-mail: teemu.reiman@vtt.fi [VTT, Espoo (Finland); Rollenhagen, Carl [KTH, Stockholm (Sweden)

2011-10-15

Management of safety is always based on underlying models or theories of organization, human behavior and system safety. The aim of the article is to review and describe a set of potential biases in these models and theories. We will outline human and organizational biases that have an effect on the management of safety in four thematic areas: beliefs about human behavior, beliefs about organizations, beliefs about information and safety models. At worst, biases in these areas can lead to an approach where people are treated as isolated and independent actors who make (bad) decisions in a social vacuum and who pose a threat to safety. Such an approach aims at building barriers and constraints to human behavior and neglects the measures aiming at providing prerequisites and organizational conditions for people to work effectively. This reductionist view of safety management can also lead to too drastic a strong separation of so-called human factors from technical issues, undermining the holistic view of system safety. Human behavior needs to be understood in the context of people attempting (together) to make sense of themselves and their environment, and act based on perpetually incomplete information while relying on social conventions, affordances provided by the environment and the available cognitive heuristics. In addition, a move toward a positive view of the human contribution to safety is needed. Systemic safety management requires an increased understanding of various normal organizational phenomena - in this paper discussed from the point of view of biases - coupled with a systemic safety culture that encourages and endorses a holistic view of the workings and challenges of the socio-technical system in question. - Highlights: > Biases in safety management approaches are reviewed and described. > Four thematic areas are covered: human behavior, organizations, information, safety models. > The biases influence how safety management is defined, executed

Human and organizational biases affecting the management of safety

International Nuclear Information System (INIS)

Reiman, Teemu; Rollenhagen, Carl

2011-01-01

Management of safety is always based on underlying models or theories of organization, human behavior and system safety. The aim of the article is to review and describe a set of potential biases in these models and theories. We will outline human and organizational biases that have an effect on the management of safety in four thematic areas: beliefs about human behavior, beliefs about organizations, beliefs about information and safety models. At worst, biases in these areas can lead to an approach where people are treated as isolated and independent actors who make (bad) decisions in a social vacuum and who pose a threat to safety. Such an approach aims at building barriers and constraints to human behavior and neglects the measures aiming at providing prerequisites and organizational conditions for people to work effectively. This reductionist view of safety management can also lead to too drastic a strong separation of so-called human factors from technical issues, undermining the holistic view of system safety. Human behavior needs to be understood in the context of people attempting (together) to make sense of themselves and their environment, and act based on perpetually incomplete information while relying on social conventions, affordances provided by the environment and the available cognitive heuristics. In addition, a move toward a positive view of the human contribution to safety is needed. Systemic safety management requires an increased understanding of various normal organizational phenomena - in this paper discussed from the point of view of biases - coupled with a systemic safety culture that encourages and endorses a holistic view of the workings and challenges of the socio-technical system in question. - Highlights: → Biases in safety management approaches are reviewed and described. → Four thematic areas are covered: human behavior, organizations, information, safety models. → The biases influence how safety management is defined

A framework of risk-informed seismic safety evaluation of nuclear power plants in Japan

International Nuclear Information System (INIS)

Kondo, S.; Sakagami, M.; Hirano, M.; Shiba, M.

2001-01-01

A framework of risk-informed seismic design and safety evaluation of nuclear power plants is under consideration in Japan so as to utilize the progress in the seismic probabilistic safety assessment methodology. Issues resolved to introduce this framework are discussed after the concept, evaluation process and characteristics of the framework are described. (author)

75 FR 11988 - Notice of Request for Approval To Collect New Information: Collection of Safety Culture Data

Science.gov (United States)

2010-03-12

..., information about changes to the safety culture of the affected workplaces will be used as one of several data...: RITA-2008-0002] Notice of Request for Approval To Collect New Information: Collection of Safety Culture.... mail to Federal offices in Washington, DC, we recommend that persons consider an alternative method...

Nuclear Safety Review for the Year 2005

International Nuclear Information System (INIS)

2006-01-01

In 2005, the Agency and its Director General were awarded the Nobel Peace Prize. The Nobel Committee statement recognizes the Agency's 'efforts to prevent nuclear energy from being used for military purposes and to ensure that nuclear energy for peaceful purposes is used in the safest possible way.' The global nature of safety is reflected in the relevant international legal instruments, both binding conventions and the non-binding codes of conduct currently in place. During the year, the third review meeting of the Contracting Parties to the Convention on Nuclear Safety as well as the third meeting of the representatives of the competent authorities under the Convention on Early Notification of a Nuclear Accident and Convention on Assistance in the Case of a Nuclear Accident or a Radiological Emergency took place. Improvements have been made in national legislation and regulatory infrastructure in many Member States in 2005. However, inadequate safety management and regulatory supervision of nuclear installations and use of ionizing radiation is a continuing issue in many Member States. A continuing challenge is to collect, analyse and disseminate safety experience and knowledge. Nuclear power plant (NPP) operational safety performance remained high throughout the world in 2005. Radiation doses to workers and members of the public due to NPP operation are well below regulatory limits. Personal injury accidents and incidents are among the lowest in industry. There were no accidents that resulted in the release of radiation that could adversely impact the environment. NPPs in many parts of the world have successfully coped with severe natural disaster conditions such as earthquakes, tsunamis, widespread river flooding and hurricanes. However, operational safety performance has been on a plateau for several years and concern has been expressed in many forums regarding the need to guard against complacency in the industry. Research reactors also maintained a good

Enabling social listening for cardiac safety monitoring: Proceedings from a drug information association-cardiac safety research consortium cosponsored think tank.

Science.gov (United States)

Seifert, Harry A; Malik, Raleigh E; Bhattacharya, Mondira; Campbell, Kevin R; Okun, Sally; Pierce, Carrie; Terkowitz, Jeffrey; Turner, J Rick; Krucoff, Mitchell W; Powell, Gregory E

2017-12-01

This white paper provides a summary of the presentations and discussions from a think tank on "Enabling Social Listening for Cardiac Safety Monitoring" trials that was cosponsored by the Drug Information Association and the Cardiac Safety Research Consortium, and held at the White Oak headquarters of the US Food and Drug Administration on June 3, 2016. The meeting's goals were to explore current methods of collecting and evaluating social listening data and to consider their applicability to cardiac safety surveillance. Social listening is defined as the act of monitoring public postings on the Internet. It has several theoretical advantages for drug and device safety. First, these include the ability to detect adverse events that are "missed" by traditional sources and the ability to detect adverse events sooner than would be allowed by traditional sources, both by affording near-real-time access to data from culturally and geographically diverse sources. Social listening can also potentially introduce a novel patient voice into the conversation about drug safety, which could uniquely augment understanding of real-world medication use obtained from more traditional methodologies. Finally, it can allow for access to information about drug misuse and diversion. To date, the latter 2 of these have been realized. Although regulators from the Food and Drug Administration and the United Kingdom's Medicines and Healthcare Products Regulatory Agency participated in the think tank along with representatives from industry, academia, and patient groups, this article should not be construed to constitute regulatory guidance. Copyright © 2017 Elsevier Inc. All rights reserved.

Climate change convention

International Nuclear Information System (INIS)

Russell, D.

1992-01-01

Principles that guide Canada's Green Plan with respect to global warming are outlined. These include respect for nature, meeting environmental goals in an economically beneficial manner, efficient use of resources, shared responsibilities, federal leadership, and informed decision making. The policy side of the international Framework Convention on Climate Change is then discussed and related to the Green Plan. The Convention has been signed by 154 nations and has the long-term objective of stabilizing anthropogenic greenhouse gas concentrations in the atmosphere at levels that prevent dangerous interference with the climate system. Some of the Convention's commitments toward achieving that objective are only applicable to the developed countries. Five general areas of commitment are emissions reductions, assistance to developing countries, reporting requirements, scientific and socioeconomic research, and education. The most controversial area is that of limiting emissions. The Convention has strong measures for public accountability and is open to future revisions. Canada's Green Plan represents one country's response to the Convention commitments, including a national goal to stabilize greenhouse gas emissions at the 1990 level by the year 2000

Knowledge management: Role of the the Radiation Safety Information Computational Center (RSICC)

Science.gov (United States)

Valentine, Timothy

2017-09-01

The Radiation Safety Information Computational Center (RSICC) at Oak Ridge National Laboratory (ORNL) is an information analysis center that collects, archives, evaluates, synthesizes and distributes information, data and codes that are used in various nuclear technology applications. RSICC retains more than 2,000 software packages that have been provided by code developers from various federal and international agencies. RSICC's customers (scientists, engineers, and students from around the world) obtain access to such computing codes (source and/or executable versions) and processed nuclear data files to promote on-going research, to ensure nuclear and radiological safety, and to advance nuclear technology. The role of such information analysis centers is critical for supporting and sustaining nuclear education and training programs both domestically and internationally, as the majority of RSICC's customers are students attending U.S. universities. Additionally, RSICC operates a secure CLOUD computing system to provide access to sensitive export-controlled modeling and simulation (M&S) tools that support both domestic and international activities. This presentation will provide a general review of RSICC's activities, services, and systems that support knowledge management and education and training in the nuclear field.

Health Technology Assessment of laparoscopic compared to conventional surgery with and without mesh for incisional hernia repair regarding safety, efficacy and cost-effectiveness

Directory of Open Access Journals (Sweden)

Willich, Stefan

2008-03-01

Medical Documentation and Information (DIMDI as well as by a manual search. The former included the following electronic resources: SOMED (SM78, Cochrane Library – Central (CCTR93, MEDLINE Alert (ME0A, MEDLINE (ME95, CATFILEplus (CATLINE (CA66, ETHMED (ED93, GeroLit (GE79, HECLINET (HN69, AMED (CB85, CAB Abstracts (CV72, GLOBAL Health (AZ72, IPA (IA70, Elsevier BIOBASE (EB94, BIOSIS Previews (BA93, EMBASE (EM95, EMBASE Alert (EA08, SciSearch (IS90, Cochrane Library – CDSR (CDSR93, NHS-CRD-DARE (CDAR94, NHS-CRD-HTA (INAHTA as well as NHSEED (NHSEED. The present report includes German and English literature published until 31.08.2005. The search parameters can be found in the appendix. No limits were placed on the target population. The methodological quality of the included clinical studies was assessed using the criteria recommended by the “Scottish Intercollegiate Guidelines Network Grading Review Group“. Economic studies were evaluated by the criteria of the German Scientific Working Group Technology Assessment for Health Care. Results: The literature search identified 17 relevant medical publications. One of these studies compared laparoscopic and conventional surgery with and without mesh for incisional hernia repair, while 16 studies compared laparoscopic and conventional surgery with mesh for incisional hernia repair. Among these studies were 14 primary studies (one randomised controlled trial (RCT, two systematic reviews and one HTA-Report. The only study comparing laparoscopic and conventional surgery without mesh found substantial differences in terms of baseline characteristics between treatment groups. The outcome parameters showed decreased recurrence rates for the laparoscopic repair and similar safety of the procedures. Studies comparing laparoscopic and conventional surgery with mesh found similar outcome in terms of medical efficacy and safety. However, there was a trend towards lower recurrence rates, length of hospital stay, and postoperative

Insights from an international stakeholder consultation to identify informational needs related to seafood safety

Energy Technology Data Exchange (ETDEWEB)

Tediosi, Alice, E-mail: alice.tediosi@aeiforia.eu [Aeiforia Srl, 29027 Gariga di Podenzano (PC) (Italy); Fait, Gabriella [Aeiforia Srl, 29027 Gariga di Podenzano (PC) (Italy); Jacobs, Silke [Department of Public Health, Ghent University, 9000 Ghent (Belgium); Department of Agricultural Economics, Ghent University, 9000 Ghent (Belgium); Verbeke, Wim [Department of Agricultural Economics, Ghent University, 9000 Ghent (Belgium); Álvarez-Muñoz, Diana [Catalan Institute for Water Research (ICRA), Parc Científic i Tecnològic de la Universitat de Girona, 17003 Girona (Spain); Diogene, Jorge [IRTA, 43540 Sant Carles de la Ràpita (Spain); Reuver, Marieke [AquaTT, Dublin 2 (Ireland); Marques, António [Division of Aquaculture and Upgrading (DivAV), Portuguese Institute for the Sea and Atmosphere (IPMA), 1449-006 Lisbon (Portugal); Capri, Ettore [Università Cattolica del Sacro Cuore, 29122 Piacenza (Italy)

2015-11-15

Food safety assessment and communication have a strong importance in reducing human health risks related to food consumption. The research carried out within the ECsafeSEAFOOD project aims to assess seafood safety issues, mainly related to non-regulated priority environmental contaminants, and to evaluate their impact on public health. In order to make the research results accessible and exploitable, and to respond to actual stakeholders' demands, a consultation with international stakeholders was performed by means of a survey. The focus was on policy and decision makers, food producers and processors, and agencies (i.e. EU and National or Regional agencies related to Food Safety or Public Health) and consumer organisations. The survey considered questions related to: seafood safety assessment and mitigation strategies, availability of data, such as the level of information on different contaminants, and communication among different stakeholder groups. Furthermore, stakeholders were asked to give their opinion on how they believe consumers perceive risks associated with environmental contaminants. The survey was distributed to 531 key stakeholders and 91 responses were received from stakeholders from 30 EU and non-EU countries. The main results show that communication between different groups of stakeholders needs to be improved and that there is a deficit of information and data in the field of seafood safety. This pertains mainly to the transfer of contaminants between the environment and seafood, and to the diversity of environmental contaminants such as plastic additives, algal toxins and hormones. On-line tools were perceived to be the most useful communication channel. - Highlights: • We consulted stakeholders to identify their needs about seafood safety. • An on-line survey was prepared and sent to gather stakeholders' opinions. • Communication among stakeholders needs to be improved. • There is a deficit of information and data in the