Publication of the inspection follow-up letters of the ASN on its site web asn.gouv.fr; Publication des lettres de suite d'inspection de l'ASN sur son site web asn.gouv.fr

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

Since February 2002, the French authority of nuclear safety (ASN) publishes on its web site (http://www.asn.gouv.fr) the letters addressed to the operators of nuclear facilities at the end of its inspections. The ASN carries out about 700 inspections every year which concern the French nuclear facilities, the central services of nuclear operators or of their suppliers, and the transports of nuclear materials. Each inspection is followed by a follow-up letter which mentions all anomalies noticed during the inspection and eventually asks for some remedial actions or for some complements of information. This document brings together the letters published between february and May 2002 and concerning the on-site inspections of nuclear facilities (EdF nuclear power plants, CEA centers, Cogema facilities, other sites) and the off-site inspections (Andra, transports of nuclear materials). (J.S.)

Complementary safety assessments - Report by the French Nuclear Safety Authority

International Nuclear Information System (INIS)

2011-12-01

As an immediate consequence of the Fukushima accident, the French Authority of Nuclear Safety (ASN) launched a campaign of on-site inspections and asked operators (mainly EDF, AREVA and CEA) to make complementary assessments of the safety of the nuclear facilities they manage. The approach defined by ASN for the complementary safety assessments (CSA) is to study the behaviour of nuclear facilities in severe accidents situations caused by an off-site natural hazard according to accident scenarios exceeding the current baseline safety requirements. This approach can be broken into 2 phases: first conformity to current design and secondly an approach to the beyond design-basis scenarios built around the principle of defence in depth. 38 inspections were performed on issues linked to the causes of the Fukushima crisis. It appears that some sites have to reinforce the robustness of the heat sink. The CSA confirmed that the processes put into place at EDF to detect non-conformities were satisfactory. The complementary safety assessments demonstrated that the current seismic margins on the EDF nuclear reactors are satisfactory. With regard to flooding, the complementary safety assessments show that the complete reassessment carried out following the flooding of the Le Blayais nuclear power plant in 1999 offers the installations a high level of protection against the risk of flooding. Concerning the loss of electrical power supplies and the loss of cooling systems, the analysis of EDF's CSA reports showed that certain heat sink and electrical power supply loss scenarios can, if nothing is done, lead to core melt in just a few hours in the most unfavourable circumstances. As for nuclear facilities that are not power or experimental reactors, some difficulties have appeared to implement the CSA approach that was initially devised for reactors. Generally speaking, ASN considers that the safety of nuclear facilities must be made more robust to improbable risks which are not

ASN report on the status of nuclear safety and radiation protection in France in 2015. Extracts

International Nuclear Information System (INIS)

2016-01-01

After a recall of ASN missions, key figures and organisation, an overview of main events for 2015, and a presentation of the French law related to energy transition for a green growth, a first part of this huge document presents actions undertaken by the ASN in 2015 in different fields: ionizing radiations and risks for health and the environment, principles and actors of control of nuclear safety and radiation protection, regulation, control of nuclear activities and of exposures to ionizing radiations, emergency radiological and post-accidental situations, public information transparency and participation, international relationships, regional overview of nuclear safety and radiation protection. The second part addresses activities controlled by the ASN: medical uses of ionizing radiations, industrial, research and veterinary uses and source safety, transportation of radioactive materials, EDF nuclear power plants, installations related to nuclear fuel cycle, various industrial and research installations, safety of basic nuclear installation dismantling, radioactive wastes and polluted sites and soils

How a regulator is preparing for reviewing a license application file: The case of ASN

International Nuclear Information System (INIS)

Tanguy, Loic

2014-01-01

The French Nuclear Safety Authority (ASN) is an independent administrative authority. It prepares regulation pertaining to the management of radioactive waste, monitors the control of safety of basic nuclear installations that produce or treat waste or are involved in their disposal and performs inspections of waste producers (EDF, AREVA, CEA, hospitals, research centres, etc.) and Andra, the French National Radioactive Waste Management Agency. It regulates the overall system set up by Andra for accepting waste from producers and assesses waste management policy and the practices of radioactive waste producers. It reviews license applications and authorises commissioning of nuclear installations. In order to review technical documents, ASN benefits from the expertise of technical support organisations. The French Institute for Radiation Protection and Nuclear Safety (IRSN) is the main such organisation. ASN has been making efforts to diversify its experts for several years. In preparing its decisions, ASN also calls on the opinions and recommendations of seven Advisory Committees of Experts (GPE), with expert knowledge in the areas of waste, nuclear pressure equipment, medical exposure, non-medical radiation protection, reactors, transport, and laboratories and nuclear plants. ASN consults the GPEs in preparing its main decisions. In particular, they review the preliminary, provisional and final safety analysis reports for each nuclear installation. They can also be consulted about changes in regulations or doctrine. (authors)

[Recommendations for inspections of the French nuclear safety authority].

Science.gov (United States)

Rousse, C; Chauvet, B

2015-10-01

The French nuclear safety authority is responsible for the control of radiation protection in radiotherapy since 2002. Controls are based on the public health and the labour codes and on the procedures defined by the controlled health care facility for its quality and safety management system according to ASN decision No. 2008-DC-0103. Inspectors verify the adequacy of the quality and safety management procedures and their implementation, and select process steps on the basis of feedback from events notified to ASN. Topics of the inspection are communicated to the facility at the launch of a campaign, which enables them to anticipate the inspectors' expectations. In cases where they are not physicians, inspectors are not allowed to access information covered by medical confidentiality. The consulted documents must therefore be expunged of any patient-identifying information. Exchanges before the inspection are intended to facilitate the provision of documents that may be consulted. Finally, exchange slots between inspectors and the local professionals must be organized. Based on improvements achieved by the health care centres and on recommendations from a joint working group of radiotherapy professionals and the nuclear safety authority, changes will be made in the control procedure that will be implemented when developing the inspection program for 2016-2019. Copyright © 2015. Published by Elsevier SAS.

Additional safety assessments, follow-up of stress tests of the French nuclear power stations. Action plan of the nuclear safety authority

International Nuclear Information System (INIS)

2012-01-01

This document presents the French national action plan defined by the Nuclear Safety Authority (ASN) in compliance with the recommendations made by the ENSREG (European nuclear safety regulators group). It refers to decisions taken at the national level after the Fukushima accident, recommendations after European stress tests, and recommendations after the extraordinary meeting of contracting parties at the Convention on Nuclear Safety of August 2012. For different topics, this document recalls the recommendations made by the peer review, indicates the ASN's opinion and progress or ASN's requirements for different power stations. The first part addresses the recommendations made by peers and based on the European review. Topics concern natural hazards (effects, detection, inspections and controls related to earthquakes, margin assessment with respect to flooding and natural hazards), the loss of safety systems (cooling systems, electricity supplies, actions, instruments, training, and so on), the management of a severe accident (reference levels, measures, guides, exercises, training, management of contaminated water, radiation protection, premises). The second part deals with topics addressed within the frame of the Convention: national organisations, organisations in an emergency and post-accidental situation, international cooperation. A third part addresses the follow-up of additional measures issued by the ASN

Skills of Asn inspectors responsible for inspecting pressurised equipment

International Nuclear Information System (INIS)

Colonna, F.

2010-01-01

ASN relies on the unique competencies of its staff to assure that it can complete its mission of maintaining public health and safety. Since 1975, personnel at ASN Nuclear Pressure Equipment Department have played a major role in the oversight of pressure boundary equipment by verifying that equipment is manufactured in compliance with regulatory requirements. This has called for highly competent individuals trained in a variety of technical and regulatory backgrounds. ASN is meeting the challenge of keeping its staff trained and prepared to continue its oversight of nuclear boilers. This has included ensuring that its organization is welt suited to meet the demands, and relying on third-party experts when necessary. With the implementation of the 2006 transparency law, ASN has taken necessary steps to ensure that it will maintain its high level of expertise going forward. (author)

Management of long-lived radioactive waste: stakes and ASN actions

International Nuclear Information System (INIS)

Dandrieux, G.

2011-01-01

Due to the length of time it takes to decay, long-lived radioactive waste will remain a hazard on a timescale beyond the length of a human life, and even of several generations. In the case of this waste, long-term management solutions must be implemented to protect human health and the environment without requiring human intervention. In accordance with requirements under the Law, ANDRA (national agency for the management of radioactive waste) is carrying out research on disposal solutions in deep or subsurface geological formations. Nonetheless, until such repositories become available, ASN (authority for nuclear safety) has a duty to ensure safety at current and future interim storage facilities, as well as the safety of operations to retrieve and package this type of waste. To this end, ASN acts on several levels: it is involved in drawing up regulations and reference texts, at national and international level, it examines safety analysis reports related to radioactive waste management at basic nuclear installations, by means of inspections that it performs at every step in radioactive waste management. In its capacity as joint coordinator of the national plan for the management of nuclear waste and materials (PNGMDR) working group, ASN also plays a very active role in drawing up the provisions of the PNGMDR aimed at improving and optimising radioactive waste management. (author)

ASN report on the status of nuclear safety and radiation protection in France in 2011

International Nuclear Information System (INIS)

2012-01-01

The first part of this huge report proposes a detailed overview of ASN activities in different fields: ionizing radiations related to nuclear activities and risks for health and the environment, principles and actors of nuclear safety control, of radiation protection and of protection of the environment, regulation, control of nuclear activities and exposures to ionizing radiations, emergency situations, public information and transparency, international relationships, regional overview of nuclear safety and radiation protection. The second part addresses the activities controlled by the ASN: medical use of ionizing radiations, non medical use of ionizing radiations, transport of radioactive materials, electronuclear power stations, facilities involved in the nuclear fuel cycle, research facilities and other nuclear installations, the safety of dismantling of nuclear base installations, radioactive wastes and polluted sites and soils

External PCR, ASN's decision

International Nuclear Information System (INIS)

Anon.

2012-01-01

The French law imposes in some situations the presence of a person skilled in radiation protection (PCR). This article describes the cases when this person must belong to the staff of the enterprise or when this person may be sub-contracted. For instance in most nuclear facilities the PCR must be on the payroll, for enterprises dedicated to nuclear transport the PCR's job can be sub-contracted. A decision given by the ASN (French Nuclear Safety Authority) sets the minimal requests (in terms of training, job contract, activities) of the sub-contracted PCR. (A.C.)

The ASN and nuclear facilities: towards a strengthening of safety margins

International Nuclear Information System (INIS)

Anon.

2012-01-01

The new measures taken by the French Nuclear Safety Authority (ASN) as a consequence of the complementary safety assessments performed recently on nuclear facilities are reviewed in this article. The main measures are the following. Concerning EDF: -) the setting of a hard core of measures in order to assure a few safety-vital functions in any case, for instance one of this measures is to bunker some of the emergency diesel sets; -) the setting of a rapid intervention force able to provide any damaged nuclear plant with extra means in cooling and power in a very short time; -) a better training of the staff in case of severe accident. Concerning AREVA: the setting of robust means to assure the water supply of the fuel pool at La Hague plant and the setting of efficient means to mitigate the consequences of a leak of ClF 3 , HF, UF 6 in the premises of Eurodif, Socatri, TU5, GB 2 and Comurhex. Concerning CEA: -) the removal of fissile materials from the Masurca facility, -) the setting up of improved means concerning flood and sodium fires at the Phenix reactor, -) the setting up of improved means concerning the loss of coolant at the Osiris reactor, -) the setting up of improved means in case of flood, earthquake and loss of coolant at the Jules Horowitz reactor. (A.C.)

Assessment of ASN inspections apart from BNI (Greater South West)

International Nuclear Information System (INIS)

Menechal, Ph.

2008-01-01

After having recalled recent evolutions of the ASN's organization (the French nuclear safety authority) and its basic missions (regulation elaboration, decisions, control of nuclear activities and installations, public information), the author presents the Bordeaux ASN's department which is in charge of the south-western part of France. He indicates and comments some data illustrating the performed actions and missions. He describes the objectives and procedures of inspection which may depend on the activity (external radiotherapy, interventional radiology, research laboratories). He assesses theses inspections in terms of radioprotection organization, of risk assessment and of definition of regulated areas, of personnel classification and dosimetric follow-on, of training of exposed personnel, of medical follow-on, of radioprotection control, of training of patients to radioprotection, of source management, and of waste and effluent management

Accidental exposures in interventional radiology: lessons learned by the ASN

International Nuclear Information System (INIS)

Marchal, C.; Valero, M.

2009-01-01

The authors outline that interventional radiology often requires long duration exposures of patients to ionizing radiations and thus stress that interventional radiology must be optimized to improve radioprotection of patients and operators. They notice that investigations performed by the ASN (the French Nuclear Safety Authority) on declared events revealed in some cases a lack of knowledge of devices by users, notably of functionalities allowing the applied doses to be controlled

From crisis exercises to the management of emergency situations...The experience of a local branch of ASN

International Nuclear Information System (INIS)

Deproit, L.; Vieuble, J.

2016-01-01

The local branch of the ASN (Nuclear Safety Authority) in the Marseille region controls the nuclear activities in 13 departments and Corsica. The preparation of the crisis management relies on the involvement of various actors: representatives of public bodies, nuclear plant operators, the ASN and its technical assistance (IRSN - Institute for Radiation-protection and Nuclear Safety). Crisis exercises are necessary to check the right coordination of all the actors. The feedback of real situations involving incidents are also important because it allows all the actors to better know each other, the case of the accident of the Centraco facility is detailed as well as the robbery of a truck carrying a radioactive source or the discovery of a collection of radioactive sources in a private home. In each case the lesson learned by the local branch of ASN is to communicate quickly with local authorities in order to get the best technical response to the situation and to give authorities all the information necessary for an efficient information of the public. (A.C.)

Report by the ASN on the situation of nuclear safety and radiation protection in France in 2013

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Delmestre, Alain; Bardet, Marie-Christine; Covard, Fabienne; Javay, Olivier

2014-01-01

In its first chapters, this huge report presents the various actions undertaken by the ASN. It proposes a detailed overview of the issue of ionizing radiations and risks for health and for the environment in the field of nuclear activities, presents and comments the principles and actors of the control of nuclear safety and of radiation protection, presents the different elements of the legal framework, describes and comments the control of nuclear activities and of exposures to ionizing radiations. The next chapters address the actions controlled by the ASN: radiological and post-accidental radiological situations, present measures related to public information and transparency, overview of international relationships, regional overview of nuclear safety and radiation protection, medical use of ionizing radiations, industrial, research and veterinary uses and the issue of source safety, the issue of radioactive material transportation. Issues of nuclear safety and radiation protection are then discussed for electronuclear plants, for installations dedicated to the nuclear fuel cycle, for various research and industrial nuclear installations, for the dismantling of base nuclear installations, and for radioactive wastes and polluted sites and soils

Synthesis of the report from the IRRS evaluation mission performed at the ASN in April 2009 by 12 international experts under the IAEA coordination

International Nuclear Information System (INIS)

2009-01-01

At the request of the Government authorities of France, an international team of 24 experts visited the Autorite de Surete Nucleaire (ASN), the French regulatory authority for nuclear and radiation safety, in November 2006 to conduct the first full scope Integrated Regulatory Review Service (IRRS) mission. The purpose of the mission was to undertake a peer review of the regulatory body of France against the IAEA Safety Standards and to exchange information and experience on safety regulation. In March 2008 the Government authorities of France requested a follow-up mission to review the measures undertaken following the recommendations and suggestions presented in the report of the November 2006 IRRS mission. The scope of the IRRS follow-up mission covered the regulatory aspects of the facilities and practices regulated by ASN, nuclear power plants, research reactors, fuel cycle facilities, medical practices with further review of radiotherapy, industrial and research activities, waste facilities, decommissioning, remediation, public information and communication and, in addition, it was also extended to cover the application of the Code of Conduct of Safety and Security of Radioactive Sources. The review was conducted from March 29 to April 3 2009 by an IRRS team consisting of 12 senior regulatory experts from 11 Member States, two staff members from the IAEA, one IAEA observer and an IAEA administrative assistant. During the review the team recognized that ASN has taken a number of initiatives to improve its effectiveness and efficiency and that ASN faces new challenges. ASN supplied a package of documentation and a well prepared self-assessment, in advance of the mission, including a status report and an action plan to improve its regulatory effectiveness. Both regulatory technical and policy issues were addressed. The policy issues discussed were: regulatory independence, the relationship between ASN and IRSN and medical issues. The IRRS follow-up mission

Decision no. 2011-DC-0215 of the French nuclear safety authority from May 5, 2011, ordering ITER Organization to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the ITER Organization, operator of the ITER tokamak facility of Cadarache (France). (J.S.)

Nuclear safety in France in 2001

International Nuclear Information System (INIS)

2002-01-01

This press dossier summarizes the highlights of nuclear safety in France in 2001: the point-of-view of A.C. Lacoste, director of the French authority of nuclear safety (ASN), the new organisation of the control of nuclear safety and radiation protection, the ASN's policy of transparency, the evolutions of nuclear fuels and the consistency of the fuel cycle, the necessary evolutions of the nuclear crisis management, the harmonizing work of safety approaches carried out by the WENRA association. The following documents are attached in appendixes: the decrees relative to the reformation of the nuclear control in France, the missions of the ASN, the control of nuclear safety and radiation protection in France, the organization of ASN in March 2000, the incidents notified in 2001, the inspections performed in 2001, and the list of the main French nuclear sites. (J.S.)

Decision no. 2011-DC-0222 of the French nuclear safety authority from May 5, 2011, ordering the Comurhex company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to Comurhex company, operator of the Tricastin uranium conversion plant (France). (J.S.)

Decision no. 2011-DC-0214 of the French nuclear safety authority from May 5, 2011, ordering CIS bio international company to proceed to a complementary safety evaluation of its basic nuclear facility in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to CIS bio international company, operator of the radiopharmaceuticals fabrication facility (INB 29) of Saclay (France). (J.S.)

Reflection groups established by the ASN

International Nuclear Information System (INIS)

Fournier, M.

2009-01-01

Recent observations about tritium bio-kinetics in aquatic organisms might change our usual consideration about its radio-toxicity. In order to analyse these observations more thoroughly, the French nuclear safety authority (ASN) decided at the end of the year 2007 to create two independent reflection groups gathering scientists, nuclear operators and associations: the group 'tritium impact' has in charge the establishment of a status of the scientific knowledge relative to tritium sanitary impact, while the group 'defense in depth' has in charge the examination of the technical possibilities of tritium reprocessing and the establishment of a knowledge status of its environmental impact. First meetings of both groups took place in May 2008. Abstract only. (J.S.)

Actions of the French Nuclear Safety Authority in response to the growth in public demand for environmental transparency

International Nuclear Information System (INIS)

Clipet, N.

2010-01-01

The Nuclear Transparency and Security Act 2006-686 of 13 June 2006 (TSN Act) reinforces the integrated approach to nuclear safety, radiation protection and environmental concerns. The TSN Act guarantees 'the public's right to reliable and accessible information on nuclear security' (Article 1). ASN fosters the implementation of this information right. Concerning the environment, it ensures that the available information is accessible and shared. This concern applies first to its own information media and actions, but also to the stakeholders. ASN makes sure that the licensees fulfill the transparency duty required by the TSN Act and is watchful concerning the effectiveness of means implemented for the public access to information. ASN also promotes good practices in its annual report for the public information. With regard to the environment, ASN actions are primarily focused on limiting and supervising the effluents discharges resulting from nuclear activities; monitoring radioactivity in the environment; and preventing and managing emergency situations. One of the recent significant contributions to providing the public with reliable, centralized information is the launch of www.mesure-radioactivite.fr. This web-site issued by the national network under the aegis of ASN, gives the public access to the results of radioactivity measurements carried out by certified laboratories. ASN seeks to involve the public in projects with an important impact on the environment. It considers the Local Information Committees (CLI) as an important contributor to the 'ecological democracy' and invites periodically their representatives to take part in ASN inspections. ASN also encourages public debates. Besides, this is one of the axis of its strategic plan 2010-2012. (author)

Improving radiotherapy quality and safety: a common objective of A.S.N. and the Ile de France Regional Hospital Agency. Thoughts on successful cooperation in Ile de France

International Nuclear Information System (INIS)

Solier, N.

2009-01-01

Radiotherapy recent development in cancer treatment needs strong procedures and quality assessment to improve safety both for patients and professionals. In Ile de France territory, a coordinated action between ASN inspectors and medical doctors specialized in public health (MISP), working as civil servants in health administration, was initiated at the end of 2007. An inspection guideline was implemented in a workshop between ASN and Regional Hospital Agency (ARH). The MISP as health administrator has to verify if care organisation responds to treatment cancer regulatory framework: as a doctor he is authorized to access to patient records to know which treatment was chosen. He has to assure if the therapeutic guidelines are respected. His comprehensive approach is essentially patient-oriented. The MISP inspection coordinated with ASN inspectors is a very pertinent pluri-disciplinary approach, undeniably necessary in such a medical technic. The effectiveness of the radiotherapy pluri-disciplinary team is funded on sharing procedures and experiences, respecting different knowledge and practices in daily work. This on site audit'. seems to be very fertile both for the radiotherapy team, the MISP and ASN inspectors. Continuous quality improvement in radiotherapy in the Ile de France region is a fertile issue between ANS and ARH teams. Confronting knowledge and procedures during the 'on site audit' in a transparent way will contribute improving radiotherapy for the 30.000 Francilian patients which receive this treatment each year. This challenge is our main concern to facilitate the patients access to the best standards treatments. (author)

Fessenheim 2: ASN's green light for continuing operation - Beginning of the works for unit 1

International Nuclear Information System (INIS)

Anon.

2013-01-01

Every 10 years a nuclear power plant operator has to make a re-assessment of the nuclear safety standard of his plant. This re-assessment is made of 2 parts: first the review of the safety conformity and secondly a thorough re-examination of the safety that takes into account today's safety standards and feedback experience from similar plants. This detailed assessment of the safety aims at checking that the consequences of the different aging phenomena are well mastered for the next 10 years at least. At the end of this re-assessment, the ASN (French Nuclear Safety Authorities) decide or not the continuation of plant activity or can prescribe safety improvements. In the case of the unit 2 of the Fessenheim plant that has just finished its third decennial safety re-assessment, the ASN has prescribed the same improvements as for the unit 1, that is to say the reinforcement of the resistance to corium of the foundation raft and an improvement on the emergency cooling system. The works on the unit 1 have begun despite contestation from anti-nuclear associations that question the cost of the safety upgrading (20 to 30 millions euros) while the unit is expected to be decommissioned by end 2016. (A.C.)

Decision no. 2011-DC-0223 of the French nuclear safety authority from May 5, 2011, ordering the MELOX SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to MELOX SA company, operator of the Melox MOX fuel fabrication plant of Marcoule (France). (J.S.)

Decision no. 2011-DC-0218 of the French nuclear safety authority from May 5, 2011, ordering the EURODIF SA company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the EURODIF SA company, operator of the George Besse I uranium enrichment plant of the Tricastin site (France). (J.S.)

Decision no. 2011-DC-0219 of the French nuclear safety authority from May 5, 2011, ordering the SOCATRI company to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the SOCATRI company, operator of the nuclear dismantling and waste processing plants of the Tricastin site (France). (J.S.)

Progress report: nuclear safety and radiation protection in France in 2005

International Nuclear Information System (INIS)

2007-01-01

The Asn (Nuclear safety authority) considers that 2005 was a satisfactory year in terms of nuclear safety and radiation protection. However, further progress can and must be made. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. 2005 was marked by significant progress in the process of harmonizing national nuclear safety policies Against a backdrop of the preparation of a bill on management of radioactive materials and waste, to be presented to Parliament in March 2006, 2005 was a year of important milestones. The Asn control activities encompass the following seven areas: development of general regulations for nuclear safety and radiation protection; management of individual authorization requests and receipt of declarations; inspection of nuclear activities; organisation of radiological surveillance of individuals and of the environment; preparation for management of emergency situations and implementation if necessary; contribution to public information on nuclear safety and radiation protection; determination of the French position within international community. Main topics in 2005: government bill on transparency and security in the nuclear field; the challenges and ambitions of the Asn; controlling exposure to radon; EPR Reactor Project Safety; working towards a law on radioactive waste in 2006; I.R.R.T.: an international audit of Asn in 2006; harmonization of nuclear safety in Europe; Chernobyl: what has been achieved over the past 20 years; informing the Public; internal authorizations. (N.C.)

Decision no. 2011-DC-0224 of the French nuclear safety authority from May 5, 2011, ordering the French atomic energy and alternative energies commission (CEA) to proceed to a complementary safety evaluation of some of its basic nuclear facilities in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the French atomic energy commission (CEA). (J.S.)

Reflection groups established by the ASN; Les groupes de reflexion mis en place par l'ASN

Energy Technology Data Exchange (ETDEWEB)

Fournier, M. [ASN, 75 - Paris (France)

2009-07-01

Recent observations about tritium bio-kinetics in aquatic organisms might change our usual consideration about its radio-toxicity. In order to analyse these observations more thoroughly, the French nuclear safety authority (ASN) decided at the end of the year 2007 to create two independent reflection groups gathering scientists, nuclear operators and associations: the group 'tritium impact' has in charge the establishment of a status of the scientific knowledge relative to tritium sanitary impact, while the group 'defense in depth' has in charge the examination of the technical possibilities of tritium reprocessing and the establishment of a knowledge status of its environmental impact. First meetings of both groups took place in May 2008. Abstract only. (J.S.)

Decision no. 2011-DC-0216 of the French nuclear safety authority from May 5, 2011, ordering the Laue Langevin Institute to proceed to a complementary safety evaluation of its basic nuclear facility (high flux reactor - INB no. 67) in the eyes of the Fukushima Daiichi nuclear power plant accident

International Nuclear Information System (INIS)

2011-01-01

As a consequence of the accident of the Fukushima Daiichi nuclear power plant (Japan), the French Prime Minister entrusted the French nuclear safety authority (ASN) with the mission to carry out a safety analysis re-evaluation of the French nuclear facilities, and in particular the nuclear power plants. A decision has been addressed by the ASN to each nuclear operator with the specifications of this safety re-evaluation analysis and the list of facilities in concern. This document is the decision addressed to the Laue Langevin Institute, operator of the high flux research reactor (RHF) of Grenoble (France). (J.S.)

Complementary Safety Assessments for Research Reactors for the French Nuclear Safety Authority

International Nuclear Information System (INIS)

Kassiotis, Christophe; Rigaud, Antoine; Evrard, Lydie

2013-01-01

The 'Autorite de surete nucleaire' (ASN) requested licensees to undertake stress tests, called complementary safety assessments (CSA), of their installations on May 5th 2011, following the accident that occurred in Japan on March 11th 2011. Their mission consisted in providing feedback on the consequences of potential extreme events. In this process, all the French facilities were divided into three categories of decreasing priority, depending on two main factors: on the one hand, their vulnerability to the various phenomena that led to the Fukushima accident, and on the other hand, the amount of radioactive elements that would be dispersed in the event of a failure of the safety functions. On the 79 high-priority facilities, only five of them are research or experimental reactors (including two currently shutdown or in decommissioning) and their operators (the 'Comissariat a l'energie atomique et aux energies alternatives' (CEA) and the 'Institut Laue Langevin') submitted their reports to the ASN on September 15 th 2011. Concerning the lower-priority facilities, including three other facilities (two research reactors operated by the CEA and a facility operated by ITER Organization) the deadline was September 15 th 2012. Finally, the remaining facilities were not asked to submit a report yet, but they will have to do it later, mainly on the occasion of their next periodic safety review. The analyses of the cliff-edge effects, that may occur in extreme situations (exceptional scale event, combination of several disasters...), led to the definition of a hardened safety core concept by the 'Institut de radioprotection et de surete nucleaire' (IRSN). This hardened safety core of structures, equipment and organizational measures must ensure the ultimate protection of the concerned facilities in extreme situations : it is designed to prevent severe accidents (or curb their progression), limit large scale releases for extreme accidents, and enables the operating teams to

Progress report: nuclear safety and radiation protection in 2006

International Nuclear Information System (INIS)

2007-01-01

For the French Nuclear Safety Authority (Asn), the year 2006 was marked by two important nuclear laws being passed, one of which brought about a major change in its status. The year was a relatively satisfactory one with regard to nuclear safety, although the picture was more contrasted concerning radiation protection: in this area, more particularly in the medical field, the overall impression of good progress is offset by the declaration of a number of radiotherapy accidents. Given the benefits expected from radiotherapy treatment by the patient suffering from cancer, the conditions in which this activity is carried out are a subject of major concern for Asn, in the light of the serious risks linked to patient over-exposure. ( some important points as follows: the law on transparency and security in the nuclear field, the law on sustainable management of radioactive materials and waste, Asn: an independent administrative authority, EPR reactor project safety, I.R.R.S.: an international audit of Asn in 2006, harmonization of nuclear safety, cancer radiotherapy, improved information of the public after the T.S.N. law, taking account of organisational and human factors). (N.C.)

ASN reputation system model

Science.gov (United States)

Hutchinson, Steve; Erbacher, Robert F.

2015-05-01

Network security monitoring is currently challenged by its reliance on human analysts and the inability for tools to generate indications and warnings for previously unknown attacks. We propose a reputation system based on IP address set membership within the Autonomous System Number (ASN) system. Essentially, a metric generated based on the historic behavior, or misbehavior, of nodes within a given ASN can be used to predict future behavior and provide a mechanism to locate network activity requiring inspection. This will provide reinforcement of notifications and warnings and lead to inspection for ASNs known to be problematic even if initial inspection leads to interpretation of the event as innocuous. We developed proof of concept capabilities to generate the IP address to ASN set membership and analyze the impact of the results. These results clearly show that while some ASNs are one-offs with individual or small numbers of misbehaving IP addresses, there are definitive ASNs with a history of long term and wide spread misbehaving IP addresses. These ASNs with long histories are what we are especially interested in and will provide an additional correlation metric for the human analyst and lead to new tools to aid remediation of these IP address blocks.

Authorization Decree Application for the creation of the Flamanville-3 Basic Nuclear Installation. Executive Summary of the Technical Review

International Nuclear Information System (INIS)

2009-01-01

On 9 May 2006, Electricite de France (EDF) submitted to the Ministers for Nuclear Safety an authorization decree application for an EPR-type reactor on the site of the Flamanville Nuclear Power Plant (NPP). Article 29 of Act No. 2006-686 of 13 June 2006 on Transparency and Security in the Nuclear Field prescribes that the creation of any basic nuclear installation shall be issued by a decree taken after consultation with the Nuclear Safety Authority (Autorite de surete nucleaire - ASN). The purpose of this report is to provide ASN's Board with a summary of the technical review led by ASN services and carried out by their technical support agencies, namely the IRSN, the GPR and the Standing Nuclear Section of the CCAP between 2001 and 2006. After summing up the conclusions of the review on the safety options of the European Pressurized Reactor (EPR) Project, as carried out between 1993 and 2000, this report describes the process and modalities of the review conducted from 2001 to 2006. Besides providing the opinion of ASN's services on the creation-licence application, it also outlines the further review to be carried out, if the authorization decree is issued. (authors)

Nuclear safety in France in 2001; La surete nucleaire en France en 2001

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

This press dossier summarizes the highlights of nuclear safety in France in 2001: the point-of-view of A.C. Lacoste, director of the French authority of nuclear safety (ASN), the new organisation of the control of nuclear safety and radiation protection, the ASN's policy of transparency, the evolutions of nuclear fuels and the consistency of the fuel cycle, the necessary evolutions of the nuclear crisis management, the harmonizing work of safety approaches carried out by the WENRA association. The following documents are attached in appendixes: the decrees relative to the reformation of the nuclear control in France, the missions of the ASN, the control of nuclear safety and radiation protection in France, the organization of ASN in March 2000, the incidents notified in 2001, the inspections performed in 2001, and the list of the main French nuclear sites. (J.S.)

OECD/NEA International Conference on Global Nuclear Safety Enhancement Organised in co-operation with the Nuclear Regulation Authority (NRA) of Japan On the Occasion of the 50. Anniversary of Japan Joining the OECD

International Nuclear Information System (INIS)

Tanaka, Shunichi; Oshima, Kenzo; Fuketa, Toyoshi; Echavarri, Luis E.; ); Ostendorff, William C.; Viktorovich Ferapontov, Alexey; Lachaume, Jean-Luc; Yoo, Guk Hee; Lyons, James E.; ); Weightman, Mike; ); Gurria, Angel; ); Ishihara, Hirotaka

2014-04-01

On 8 April 2014 in Tokyo, Japan, an international conference on enhancing global nuclear safety was held by the Nuclear Energy Agency (NEA) of the Organisation for Economic Co-operation and Development(OECD), in co-operation with the Nuclear Regulation Authority (NRA) of Japan. This document brings together the 12 presentations (slides) given at this conference organized in 3 sessions: 1 - Opening Session: Opening Remarks (S. Tanaka); Statement by L.E. Echavarri; Session 1 - Global Safety Enhancements: USNRC Actions in Response to the Fukushima Nuclear Accident (W.C. Ostendorff); Synergy of National and International Regulatory Efforts to Enhance Global Nuclear Safety (A. Viktorovich Ferapontov); Global Safety Enhancements, The French Nuclear Safety Authority (ASN)'s position (J.L. Lachaume); Nuclear Safety and Security Commission builds up safety and security (G.H. Yoo); Session 2 - Learning from Experience to Improve Safety: Lessons Learned from the Fukushima Dai-ichi Accident and Responses in New Regulatory Requirements (T. Fuketa); NEA Activities to Enhance the Nuclear Regulatory Framework (L.E. Echavarri); Learning from Experience to Improve Safety - its importance, its mechanisms and its challenges (J.E. Lyons); Learning from Experience to Improve Nuclear Safety - A Perspective from the UK (M. Weightman); Conclusions and Closing Remarks (A. Gurria, H. Ishihara)

Hearing of Mrs Marie-Pierre Comets and Mr Marc Sanson, commissioners of the Nuclear Safety Authority (ASN), as well as Mrs Marie-Claude Dupuis, general manager of the National Agency for the management of radioactive wastes (ANDRA), on the nuclear events in Cadarache

International Nuclear Information System (INIS)

2009-01-01

Representatives of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire) and of the French National Agency for the Management of Radioactive Wastes (ANDRA, Agence nationale pour la gestion des dechets radioactifs) answer questions about an incident which occurred in a workshop, where MOx fuel was produced and which is now being dismantled. It appeared that the amount of plutonium present in the gloveboxes has been largely under-assessed: 8 kg were expected, 22 kg of plutonium have already been recovered, and finally 39 kg might be recovered by the end the dismantling operations. Other issues are addressed like the ANDRA's projects of radioactive material geological storage, their technical and institutional aspects, and then again about the late declaration of the Cadarache incident

Complementary safety assessments of the French nuclear power plants (European 'stress tests'). Report by the French nuclear safety authority - December 2011

International Nuclear Information System (INIS)

2011-12-01

After having recalled the organisation of nuclear safety and radiation protection regulation in France, presented the French nuclear safety regulations (acts, decrees, orders, ASN decisions, rules and guides), described the nuclear safety approach in France (the 'defense in depth' concept), and ASN's sanctions powers, this report presents the French approach to complementary safety assessments (CSAs) with their different types of specifications (those consistent with European specification, those broader than the European specifications, and those which take into account some situations resulting from a malevolent act), and with the different categories of facilities concerned by these CSAs. It presents the organisation of the targeted inspections and outlines the transparency of this action and public information. Then, after an overview of the French nuclear power plant fleet, it discusses how earthquakes, flooding, and other extreme natural phenomena related to flooding are taken into account in the design of facilities and in terms of evaluation of safety margins. It describes the consequences of some critical situations (loss of electrical power supplies and cooling systems) and how they could be dealt with. It also addresses the different aspects of a severe accident management (organisation, measures, and actions to be performed) and the conditions related to the use of outside contractors

Progress report: nuclear safety and radiation protection in France in 2005; Rapport annuel: la surete nucleaire et la radioprotection en France en 2005

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The Asn (Nuclear safety authority) considers that 2005 was a satisfactory year in terms of nuclear safety and radiation protection. However, further progress can and must be made. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. 2005 was marked by significant progress in the process of harmonizing national nuclear safety policies Against a backdrop of the preparation of a bill on management of radioactive materials and waste, to be presented to Parliament in March 2006, 2005 was a year of important milestones. The Asn control activities encompass the following seven areas: development of general regulations for nuclear safety and radiation protection; management of individual authorization requests and receipt of declarations; inspection of nuclear activities; organisation of radiological surveillance of individuals and of the environment; preparation for management of emergency situations and implementation if necessary; contribution to public information on nuclear safety and radiation protection; determination of the French position within international community. Main topics in 2005: government bill on transparency and security in the nuclear field; the challenges and ambitions of the Asn; controlling exposure to radon; EPR Reactor Project Safety; working towards a law on radioactive waste in 2006; I.R.R.T.: an international audit of Asn in 2006; harmonization of nuclear safety in Europe; Chernobyl: what has been achieved over the past 20 years; informing the Public; internal authorizations. (N.C.)

The Bacillus subtilis and Bacillus halodurans Aspartyl-tRNA Synthetases Retain Recognition of tRNA(Asn).

Science.gov (United States)

Nair, Nilendra; Raff, Hannah; Islam, Mohammed Tarek; Feen, Melanie; Garofalo, Denise M; Sheppard, Kelly

2016-02-13

Synthesis of asparaginyl-tRNA (Asn-tRNA(Asn)) in bacteria can be formed either by directly ligating Asn to tRNA(Asn) using an asparaginyl-tRNA synthetase (AsnRS) or by synthesizing Asn on the tRNA. In the latter two-step indirect pathway, a non-discriminating aspartyl-tRNA synthetase (ND-AspRS) attaches Asp to tRNA(Asn) and the amidotransferase GatCAB transamidates the Asp to Asn on the tRNA. GatCAB can be similarly used for Gln-tRNA(Gln) formation. Most bacteria are predicted to use only one route for Asn-tRNA(Asn) formation. Given that Bacillus halodurans and Bacillus subtilis encode AsnRS for Asn-tRNA(Asn) formation and Asn synthetases to synthesize Asn and GatCAB for Gln-tRNA(Gln) synthesis, their AspRS enzymes were thought to be specific for tRNA(Asp). However, we demonstrate that the AspRSs are non-discriminating and can be used with GatCAB to synthesize Asn. The results explain why B. subtilis with its Asn synthetase genes knocked out is still an Asn prototroph. Our phylogenetic analysis suggests that this may be common among Firmicutes and 30% of all bacteria. In addition, the phylogeny revealed that discrimination toward tRNA(Asp) by AspRS has evolved independently multiple times. The retention of the indirect pathway in B. subtilis and B. halodurans likely reflects the ancient link between Asn biosynthesis and its use in translation that enabled Asn to be added to the genetic code. Copyright © 2016 The Authors. Published by Elsevier Ltd.. All rights reserved.

Regulatory framework and safety requirements for new (gen III) reactors

International Nuclear Information System (INIS)

Mourlon, Sophie

2014-01-01

Sophie Mourlon, ASN Deputy General Director, described the international process to enhance safety between local safety authorities through organizations such as WENRA. Then she explained to the participants the regulatory issues for the next generation of NPPs

The national plan of radioactive materials and wastes management. ASN's notice about the choice of the sites to be investigated in view of the setting up of a disposal facility for low activity/long living wastes

International Nuclear Information System (INIS)

2009-07-01

This short presentation, given by the national safety authority (ASN) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), presents, first, the second French national plan of radioactive materials and wastes management (PNGMDR) with its main priorities, and then, the choice of the sites to survey in view of the setting up of a disposal facility for low level/long living wastes. The ASN expresses its opinion about the criteria retained by the ANDRA (the national agency of radioactive waste management) to select the most suitable sites. (J.S.)

ASN takes position in the in-service follow-up programs of primary and secondary loops of EdF's nuclear power plants

International Nuclear Information System (INIS)

2002-01-01

This decision from the French authority of nuclear safety (ASN) aims at fixing the conditions to be respected by Electricite de France (EdF) during its in-service follow-up programs for the monitoring and preventive maintenance of the primary and secondary cooling loops of EdF's PWR reactors. The components and the particular points to be controlled are listed in appendixes. (J.S.)

The ASN imposes on EDF complementary requirements for the setting of the hard-core unit

International Nuclear Information System (INIS)

Anon.

2014-01-01

In January 2014, the ASN (French Authority for Nuclear Safety) published a list of 19 decisions concerning the implementation of a 'post-Fukushima' hard-core unit in each EDF nuclear power plant. The purpose of the hard-core unit is to have structures and equipment able to resist very extreme events and able to assure the vital functions necessary for the reactor safety. The 19 decisions detail the rules for the design of the hard-core unit. For example the hard-core unit will have to resist earthquakes for which the probability of occurrence is about 1 every 20.000 years while the probability taking into account for the design of the reactor is only 1 every 1000 or 10.000 years

Decree nr 2013-440 of the 28 May 2013 modifying the decree of the 5 February 1980 authorizing the creation by Electricite de France of two units of the Blayais nuclear power station, in the district of Gironde, and authorizing Electricite de France to use fuel containing plutonium in the INB nr 110 - Opinion nr 2012-AV-0165 of the Nuclear Safety Authority of the 9 October 2012

International Nuclear Information System (INIS)

Ayrault, Jean-Marc; Batho, Delphine

2013-01-01

While referring to various legal European and French texts (treaty, codes, decrees, and so on), this decree indicates modifications to a previous decree. These modifications notably concern the fuel type, and arrangements concerning the operator. These modifications are also made, based on a text published by the ASN (nuclear safety authority)

Progress report: nuclear safety and radiation protection in 2006; Rapport annuel: la surete nucleaire et la radioprotection en France en 2006

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

For the French Nuclear Safety Authority (Asn), the year 2006 was marked by two important nuclear laws being passed, one of which brought about a major change in its status. The year was a relatively satisfactory one with regard to nuclear safety, although the picture was more contrasted concerning radiation protection: in this area, more particularly in the medical field, the overall impression of good progress is offset by the declaration of a number of radiotherapy accidents. Given the benefits expected from radiotherapy treatment by the patient suffering from cancer, the conditions in which this activity is carried out are a subject of major concern for Asn, in the light of the serious risks linked to patient over-exposure. ( some important points as follows: the law on transparency and security in the nuclear field, the law on sustainable management of radioactive materials and waste, Asn: an independent administrative authority, EPR reactor project safety, I.R.R.S.: an international audit of Asn in 2006, harmonization of nuclear safety, cancer radiotherapy, improved information of the public after the T.S.N. law, taking account of organisational and human factors). (N.C.)

The transport safety of radioactive matters

International Nuclear Information System (INIS)

Landier, D.; Louet, Ch.A.; Robert, Ch.; Binet, J.; Malesys, P.; Pourade, C.; Le Meur, A.; Robert, M.; Turquet de Beauregard, G.Y.; Hello, E.; Laumond, A.; Regnault, Ph.; Gourlay, M.; Bruhl, G.; Malvache, P.; Dumesnil, J.; Cohen, B.; Sert, G.; Pain, M.; Green, L.; Hartenstein, M.; Stewart, J.; Cottens, E.; Liebens, M.; Marignac, Y.

2007-01-01

Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

Nuclear safety and radiation protection in France in 2011

International Nuclear Information System (INIS)

2012-01-01

The first part of this voluminous report describe the different ASN (Nuclear Safety Authority) actions: nuclear activities (ionising radiation and health and environmental risks), principles and stakeholders in nuclear safety regulation, radiation protection and protection of the environment, regulation, regulation of nuclear activities and exposure to ionizing radiation, radiological emergencies, public information and transparency, international relations. It also gives an overview of nuclear safety and radiation protection activities in the different French regions. The second part addresses activities regulated by the ASN: medical uses of ionizing radiation, non-medical uses of ionizing radiation, transport of radioactive materials, nuclear power plants, nuclear fuel cycle installations, nuclear research facilities and various nuclear installations, safe decommissioning of basic nuclear installations, radioactive waste and contaminated sites and soils

Flamanville 3 EPR, Safety Assessment and On-site Inspections

International Nuclear Information System (INIS)

Piedagnel, Corinne; Tarallo, Francois; Monnot, Bernard

2011-01-01

As a Technical Support Organisation of the French Safety Authority (ASN), the IRSN carries out the safety assessment of EPR project design and participates in the ASN inspections performed at the construction site and in factories. The design assessment consists in defining the safety functions which should be ensured by civil structures, evaluating the EPR Technical Code for Civil works (ETC-C) in which EdF has defined design criteria and construction rules, and carrying out a detailed assessment of a selection of safety-related structures. Those detailed assessments do not consist of a technical control but of an analysis whose objectives are to ensure that design and demonstrations are robust, in accordance with safety and regulatory rules. Most assessments led IRSN to ask EdF to provide additional justification sometimes involving significant modifications. In the light of those complementary justifications and modifications, IRSN concluded that assessments carried out on design studies were globally satisfactory. The participation of IRSN to the on-site inspections led by ASN is a part of the global control of the compliance of the reactor with its safety objectives. For that purpose IRSN has defined a methodology and an inspection program intended to ASN: based on safety functions associated with civil works (confinement and resistance to aggressions), the corresponding behaviour requirements are identified and linked to a list of main civil works elements. During the inspections, deviations to the project's technical specifications or to the rules of the art were pointed out by IRSN. Those deviations cover various items, such as concrete fabrication, concrete pouring methodology, lack of reinforcement in some structures, unadapted welding procedures of the containment leak-tight steel liner and unsatisfactory treatment of concreting joints. The analysis of those problems has revealed flaws in the organisation of the contractors teams together with an

Demand of authorization to create the 'Flamanville 3' Basis Nuclear Installation. Synthesis report of the technical examination

International Nuclear Information System (INIS)

2007-02-01

The present report has for objective to present to the College of Asn a synthesis of the technical instruction piloted by the services of Asn and realized by their technical supports (I.R.S.N., G.P.R., S.P.N.) during the period 2001-2006. After a reminder of the conditions of the examination of the safety options of the project EPR made between 1993 and 2000, this report explains the progress and the modalities of the instruction realized from 2001 till 2006. It draws up then, besides a notice of the Asn services at request of creation authorization, a synthesis of the technical examination realized according to axes presented on the fig 1. Finally, it presents the main lines of the examination that it would stay to realize if the creation authorization was delivered. (N.C.)

Control of doses delivered to patients in medical imagery. Progress report of the program of actions recommended by the ASN. January 2015

International Nuclear Information System (INIS)

2015-01-01

This report proposes an overview and an assessment of the various actions recommended by the ASN (the French Nuclear Safety Authority) for a better management of doses delivered to patients in the case of medical imagery. It indicates and discusses the progress noticed: actions which have been already performed, actions which are currently in progress, and actions which are still to be launched. These actions concern various aspects: the practice quality and safety (quality and safety management), the organisation, human resources and training, equipment and installation safety, radio-vigilance practices, relationships with patients, knowledge of practices and of exposures of patients and workers. Some highlights are outlined: some persistent lacks in human resources, some encouraging initiatives in the field of training, some progresses in the field of practice quality and safety, and some limited results regarding equipment (notably MRI) and installation safety

Effects of Asn318 and Asp87Asn318 mutations on signal transduction by the gonadotropin-releasing hormone receptor and receptor regulation.

Science.gov (United States)

Awara, W M; Guo, C H; Conn, P M

1996-02-01

GnRH receptor (GnRH-R) contains Asn87 and Asp318 instead of the more frequently observed Asp87 and Asn318 found in other G protein-coupled receptors. In the present study, site-directed mutagenesis was used to introduce Asn318 and Asp87Asn318 into GnRH-R. The effect on coupling and regulation of GnRH-R was studied by stable expression of wild and mutant mouse GnRH-R in the lactotropic GH3 cells; these normally release PRL in response to TRH stimulation. The responses to Buserelin (a metabolically stable GnRH analog) in three different cell lines, M1, N8, and ND1 (expressing wild-type, Asn318 mutant, and Asp87Asn318 mutant mouse GnRH-R, respectively) were compared with that observed in the previously characterized GGH3-1' cells, which stably express rat GnRH-R. The Asn318 and Asp87Asn318 mutations had no measurable effect on ligand binding, but abolished the initial down-regulation of receptor that was observed in M1 and GGH3-1' cells, suggesting that the normal location of Asn87 and Asp318 in GnRH-R is involved in the regulation of GnRH-R. In N8 and ND1 cells, Buserelin-stimulated inositol phosphate (IP) production was attenuated, but the release of both cAMP and PRL was stimulated in a dose- and time-dependent manner. These mutations apparently impaired the coupling between GnRH-R and G proteins involved in IP production, but not those involved in cAMP release. In M1 cells, Buserelin stimulation produced a significant increase in IP production, but neither cAMP nor PRL release was significantly stimulated. These findings are consistent with the previous suggestion that GnRH-stimulated PRL release is mediated by a cAMP second messenger system in transfected GGH3 cells.

The nuclear law: safety. 2006-2010

International Nuclear Information System (INIS)

Bringuier, P.

2010-01-01

The author discusses the legal evolutions related to nuclear safety between 2006 and 2010. He identifies three main topics of unequal importance. Firstly, he comments the implementation of an international reference framework which has been completed at the European level and which aims at the harmonization of safety and security rules. Secondly, he comments the creation of the French Nuclear Safety Authority (ASN, Autorite de Surete Nucleaire). Thirdly, he comments the recast of the standard framework in order to update the French law with respect to the international reference framework. This leaded to a new distribution of power and authority, to more complete and constraining procedures, and to the definition of procedures for each step of an installation life cycle

32 CFR 775.12 - Delegation of authority.

Science.gov (United States)

2010-07-01

... 32 National Defense 5 2010-07-01 2010-07-01 false Delegation of authority. 775.12 Section 775.12... FOR IMPLEMENTING THE NATIONAL ENVIRONMENTAL POLICY ACT § 775.12 Delegation of authority. (a) The ASN... instruction as deemed appropriate. (b) The ASN (RD&A) delegation of authority for approval and signature of...

Asn12 and Asn278: Critical Residues for In Vitro Biological Activity of Reteplase

Directory of Open Access Journals (Sweden)

Naganath Mandi

2010-01-01

Full Text Available Reteplase (rPA is a thrombolytic agent used for the treatment of acute myocardial infarction. We studied the expression of rPA and its selected asparagine mutants after integration into the Pichia genome. Though methanol induction of the native and the rPA mutants showed similar expression levels (~200–250 mg/L, the mutants displayed significant loss of protease activity. Strikingly, the clot lysis activities of these mutants were considerably different. While mutation of Asn12 (N12P of the Kringle 2 domain showed delayed clot lysis activity (1/2=38 min compared to the native rPA (1/2=33 min, a faster rate of clot lysis (1/2=27 min was observed when the Asn278 (N278S of the serine protease domain was mutated. Interestingly, the slowest clot lysis activity (1/2=49 min demonstrated by the double mutant (N12P, N278S suggests the dominant role of Asn12 in regulating the fibrinolytic activity of rPA. The results presented in this paper indicate that the fibrinolytic and the proteolytic activities of rPA are independent of each other.

High committee for transparency and information on nuclear safety: meeting of April 29, 2010

International Nuclear Information System (INIS)

2010-01-01

The committee members first discuss the report project concerning the State minister's and OPECST (parliamentary office of scientific and technological choices) chairman's submission regarding the transparency of the nuclear fuel cycle. They discuss the project of a portal web site gathering information on French nuclear power plant operations. They comment the 2009 ASN assessment on medical nuclear activities, the implementation of the Cancer Plan (presentation by the minister of public health, statements by the French nuclear safety authority or ASN, the French institute for radiation protection and nuclear safety or IRSN, and by associations of patients). They discuss the presentation by the ASN of a return on experience after the ATPu event and the presentation by the IRSN of technical form on the criticality risk. Other topics are addressed: extensions of storage sites under construction in La Hague, modification of the Grenelle II bill to improve public consultation in some procedures regarding base nuclear installations

Annual report ''nuclear safety in France''

International Nuclear Information System (INIS)

2001-01-01

This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

Impact of the Disruption of ASN3-Encoding Asparagine Synthetase on Arabidopsis Development

Directory of Open Access Journals (Sweden)

Laure Gaufichon

2016-02-01

Full Text Available The aim of this study was to investigate the role of ASN3-encoded asparagine synthetase (AS, EC 6.3.5.4 during vegetative growth, seed development and germination of Arabidopsis thaliana. Phenotypic analysis of knockout (asn3-1 and knockdown (asn3-2 T-DNA insertion mutants for the ASN3 gene (At5g10240 demonstrated wild-type contents of asparagine synthetase protein, chlorophyll and ammonium in green leaves at 35 days after sowing. In situ hybridization localized ASN3 mRNA to phloem companion cells of vasculature. Young siliques of the asn3-1 knockout line showed a decrease in asparagine but an increase in glutamate. The seeds of asn3-1 and asn3-2 displayed a wild-type nitrogen status expressed as total nitrogen content, indicating that the repression of ASN3 expression had only a limited effect on mature seeds. An analysis of amino acid labeling of seeds imbibed with (15N ammonium for 24 h revealed that asn3-1 seeds contained 20% less total asparagine while 15N-labeled asparagine ((2-15Nasparagine, (4-15Nasparagine and (2,4-15Nasparagine increased by 12% compared to wild-type seeds. The data indicate a fine regulation of asparagine synthesis and hydrolysis in Arabidopsis seeds.

The transport safety of radioactive matters; La surete des transports des matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

Landier, D.; Louet, Ch.A.; Robert, Ch. [Autorite de Surete Nucleaire, 75 - Paris (France); Binet, J. [Commission europeenne, DG Energie et transports, Bruxelles (Belgium); Malesys, P. [TN International, 75 - Paris (France); Pourade, C. [Societe Dangexpress, 78 - St Remy l' Honore (France); Le Meur, A.; Robert, M. [Societe Nationale des Chemins de fer Francais, 75 - Paris (France); Turquet de Beauregard, G.Y.; Hello, E. [CIS bio, 91 - Gif sur Yvette (France); Laumond, A. [Electricite de France (EDF), 75 - Paris (France); Regnault, Ph.; Gourlay, M. [AREVA NC, 78 - Velizy Villacoublay (France); Bruhl, G. [CEA Fontenay-aux-Roses, Dir. de la Protection et de la Surete Nucleaire, 92 (France); Malvache, P.; Dumesnil, J. [CEA Saclay, Dir. de l' Energie Nucleaire (DEN), 91 - Gif sur Yvette (France); Cohen, B. [Agence Nationale pour la Gestion des Dechets Radioactifs (ANDRA), 92 - Chatenay Malabry (France); Sert, G. [Institut de Radioprotection et de Surete Nucleaire (IRSN), 92 - Clamart (France); Pain, M. [Ministere de l' Interieur, et de l' Amenagement du Territoire, Dir. de la Defense et la Securite Civiles, 75 - Paris (France); Green, L.; Hartenstein, M. [World Nuclear Transport Institute, London (United Kingdom); Stewart, J. [Ministere des Transport, Royaume Uni (United Kingdom); Cottens, E.; Liebens, M. [Agence Federale de Controle Nucleaire (Belgium); Marignac, Y. [Wise, 75 - Paris (France)

2007-02-15

Since the control of transport of radioactive materials was given to A.S.N. 10 years ago, A.S.N. has strengthened the radioactive material transport inspections, in particular of the designers, manufacturers, carriers and consignors. A.S.N. has implemented INES scale for incidents during transport. It has participated as much as possible to IAEA working groups in order to improve the international regulatory framework. And, supported by I.R.S.N., A.S.N. has performed a periodic safety review of existing package models and has approved new models incorporating innovative design features. Finally, A.S.N. has tested its emergency responses to procedures to an accident involving the transport of radioactive materials. All these actions taken together have led to improvement in and reinforcement of the safety culture among the transport operators; this has been acknowledged by a recent audit T.R.A.N.S.A.S. performed by IAEA. In spite of all these actions, there are not approved by the competent authority. As A.S.N. is in charge of every field in radioprotection, this should help to intensify the control. In addition, the different kinds of transport are also tackled as rail transport with S.N.C.F. radiological risk training, air transport through nuclear medicine. Some experience feedback are given such radioactive waste transport to the storage facilities in the Aube or how to protect the population after a nuclear transport incident with the O.R.S.E.C.-T.M.S. plans. (N.C.)

to control the nuclear safety and the radiation protection

International Nuclear Information System (INIS)

Lacoste, A.C.; Bordarier, Ph.; Saint-Raymond, Ph.; Repussard, J.; Gouze, J.R.; Degos, L.; Massart, S.; Wiroth, P.; Thezee, Ch.; Petit, G.; Cahen, B.; Hubert, I.; Wiroth, P.; Thezee, Ch.; Petit, G.; Kaufer, B.; Taniguchi, T.; Revol, H.

2005-01-01

Publishing this dossier, the aim is to present the principles and the variety of issues linked to nuclear safety and radiation protection supervision, and the main strategic choices made to use efficiently and effectively A.S.N. supervision means. A.S.N. is responsible for nuclear safety and radiation protection supervision. A.S.N. has to be itself evaluated and supervised by external bodies. The Parliament Office for Evaluation of Scientific and Technological Options (O.P.E.C.S.T.) supervises it; the foreign peers watch and A.S.N. has to be the object of an international audit conducted by its peers under the leadership of I.A.E.A. by the beginning of 2007. (N.C.)

Order of the 29. of January 2010 approving the decision n. 2009-DC-0146 made on the 16. of July 2010 by the Nuclear Safety Authority (ASN), modified by the decision n. 2009-DC-0162 of the 20. of October 2009, defining the list electric equipment generating X rays which are hold or used for purposes of biomedical research or medical, dental, forensics or veterinary diagnosis and submitted to a declaration regime on the account of the first paragraph of the article R. 1333-19 of the Public Health code and abrogating the 23 April 1969 order related to equipment and installations using ionizing radiations on medical purposes

International Nuclear Information System (INIS)

2010-01-01

This legal document indicates the list of equipment which must now be declared to the ASN (the French Nuclear Safety Authority), specifies that any use of these equipment in conditions other than normal requires an authorization on the account of an article of the Public Health Code. A list of equipment is given which are used in medical and forensics radio-diagnosis, in biomedical research, in dental and veterinary radio-diagnosis

Order of the 29. of January 2010 approving the decision n. 2009-DC-0146 made on the 16. of July 2010 by the Nuclear Safety Authority (ASN), modified by the decision n. 2009-DC-0162 of the 20. of October 2009, defining the list electric equipment generating X rays which are hold or used for purposes of biomedical research or medical, dental, forensics or veterinary diagnosis and submitted to a declaration regime on the account of the first paragraph of the article R. 1333-19 of the Public Health code and abrogating the 23 April 1969 order related to equipment and installations using ionizing radiations on medical purposes

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

This legal document indicates the list of equipment which must now be declared to the ASN (the French Nuclear Safety Authority), specifies that any use of these equipment in conditions other than normal requires an authorization on the account of an article of the Public Health Code. A list of equipment is given which are used in medical and forensics radio-diagnosis, in biomedical research, in dental and veterinary radio-diagnosis

The risk of shortage of radioelements at medical use must not lead to overlook the reactors safety that produce them

International Nuclear Information System (INIS)

2009-01-01

As the reactors supplying the world production of radioelements for medical use have over 40 years of operation, the nuclear safety authority alerts the stake holders on the necessity to prevent the conflicts between public health and nuclear safety in the production of these elements; Asn estimates that the solution is not to extend the lifetime of the reactors but goes for a new international concerted approach. The most of the present production comes from five old reactors: N.R.U. at Chalk river (Canada, 40%), H.F.R. at Petten (Netherlands, 30%), Safari at Pelindaba (South Africa, 10%) B.R.2 at Mol (Belgium, 9%) and Osiris at Saclay (France, 5%). In this context, Asn organised in january 2009 a seminar on the safety-availability of facilities of radio-isotopes production with safety authorities of the concerned countries. Nea organised a seminar on the radiopharmaceuticals supply at the end of january 2009. (N.C.)

An International Peer Review of the Safety Options Dossier of the Project for Disposal of Radioactive Waste in Deep Geological Formations (Cigéo). Final Report of the IAEA International Review Team November 2016

International Nuclear Information System (INIS)

2017-07-01

The French Nuclear Safety Authority (Autorité de sûreté nucléaire, ASN) is preparing the evaluation of a licence application for the creation of a deep geological disposal facility in 2018, called Cigéo, for intermediate level, high level and long lived radioactive waste. This licence is preceded by the submission of a Safety Options Dossier to ASN, which provides the French National Radioactive Waste Management Agency (Agence nationale pour la gestion des déchets radioactifs, Andra) the possibility to receive advice from ASN on the preparation of the licence application on the safety principles and approach. The Safety Options Dossier sets out the chosen objectives, concepts and principles for ensuring the safety of the facility. ASN requested the IAEA to organize an international peer review of the Safety Options Dossier. This publication presents the consensus view of the international group of experts convened by the IAEA to conduct the review against the relevant IAEA safety standards and proven international practice and experience. The experts acted in a personal capacity and the views expressed do not necessarily reflect those of the IAEA, the governments of the nominating Member States or the nominating organizations. The basis of this peer review is the set of documents provided by Andra, as the agency responsible for the development of the Cigéo project and for its safety. Consequently, the findings of the reviews are addressed directly to Andra. This publication, however, is primarily submitted to ASN to review the outcomes of the Andra project.

The decisions taken in 2012 by the ASN: additional requirements

International Nuclear Information System (INIS)

Lacoste, Andre-Claude; Comets, Marie-Pierre; Dumont, Jean-Jacques; Bourguignon, Michel; Jamet, Philippe

2012-01-01

After the publication of conclusions of the Additions Safety Assessments (ECS, evaluations complementaires de surete), this document gathers 32 decisions taken by the ASN in June 2012 which specify additional requirements for EDF nuclear power plants, AREVA installations, and some CEA reactors. These measures will lead to a significant strengthening of safety margins beyond their sizing. These decisions impose huge works to operators. They comprise the implementation of an organisation and the construction of premises resistant to a big event which would affect several installations. Other measures concern a deeper training of agents intervening in case of earthquake or severe accident, robust means of power supply for warehousing pools, efficient means to reduce accidental leakage of different compounds, the storing of fissile materials in an installation sufficiently strong to resist earthquakes, and improvements regarding the flood risk management and sodium fire risk management

The role of the safety authority

International Nuclear Information System (INIS)

Gelder, P. de

2004-01-01

The original programme of the Belgium Workshop did not include a scheduled talk by a representative of the safety authority. However, because of the interest expressed by FSC delegates in this player, a speaker stepped forward. Pieter De Gelder, division head of AVN spoke of the role of the safety authority in the local dialogue. He recalled that in Belgium a safety authority in the modern sense of the word was founded only in the mid 1990's. The safety authority is a federal agency (FANC), while AVN is a private company, a contractor to FANC. Mr. De Gelder highlighted that the regulators are not formal members of the partnerships and do not attend each meeting. However, from time to time, partnerships invite experts from FANC and AVN to give presentations on specific topics. In particular, these experts have provided information on their roles and activities in the process, on legal and authorization procedures, and on the evaluation of ONDRAF/NIRAS dossiers. Mr. De Gelder observed that they found a very motivated local audience and they have committed themselves to continued interaction with the partnerships. Finally, he stressed that this type of public interaction around the repository issue is new to the regulator. (author)

[Conformation analysis of the N-glycosylation site Asn-X-Thr/Ser in glycoproteins].

Science.gov (United States)

Avanov, A Ia; Lipkind, G M

1990-03-01

Theoretical conformational analysis of oligopeptides CH3CO-Asn-X-Thr-NHCH3 (X = Gly, Ala, Pro), modelling N-glycosylation site, and their glycosylated derivatives CH3CO-(GlcNAc beta 1-4GlcNAc beta 1) Asn-X-Thr-NHCH3 has been carried out. Active conformations of the site are found, corresponding to structural prerequisities of N-glycosylation: Asn residue's position in beta-turn and hydrogen bond formation between side chains of Asn and Thr/Ser residues. In this case the L conformation of the central residue X is most probable. Since Pro residue does not possess this conformation, sequences with X = Pro are not glycosylated. It is shown that glycosylation of the above-mentioned sites is accompanied by reorientation of the Asn residue's side chains.

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

Reports by the Parliamentary Office for scientific and technological assessments. Thursday, June 16, 2011. Transparency in nuclear safety

International Nuclear Information System (INIS)

2011-06-01

In a first session dedicated to modalities of transparency in the field of nuclear safety, members of the French Parliament hear and discuss the interventions of representatives of the French nuclear safety authority (ASN), AREVA, EDF, the CEA, the French institute of radiation protection and nuclear safety (IRSN), of the High committee for transparency and information on nuclear safety (HCTISN). The second session addresses the improvement of transparency and comprised interventions by representatives of the OECD and of local commissions of information (ANCCLI)

Opinion nr 2012-AV-0172 by the Nuclear Safety Authority on November 6, 2012 on the decree project authorizing the ITER international organization to create a basic nuclear installation named 'ITER' on the territory of Saint-Paul-lez-Durance (Bouches-du-Rhone)

International Nuclear Information System (INIS)

Lacoste, A.C.; Bourguignon, M.; Comets, M.P.; Dumont, J.J.; Jamet, P.

2012-01-01

This official text (published in the French 'Journal Officiel') expresses the positive opinion of the ASN about the decree project authorizing the creation of the ITER basic nuclear installation. It also contains the decree text which notably indicates the nuclear and non-nuclear buildings, presents the installation characteristics (operation limits, operation phases), and measures aiming at preventing accidents, basic safety functions (confinement control, limitation of exposure to ionizing radiation), gives an overview of measures aiming at protecting the installation against various risks (proper to the installation operation or induced by its environment), addresses issues concerning the operation (general rules, intervener training and information, protection systems, radioactive, chemical, liquid and gaseous effluents, waste management)

Safety culture competition - expectations of a regulatory authority

International Nuclear Information System (INIS)

Keil, D.; Gloeckle, W.

2000-01-01

The accident at the Chernobyl nuclear power station on April 26, 1986 influenced the development of reactor safety and promulgated two basic concepts especially in Germany. On the one hand, extensive measures of in-plant accident management have greatly reduced the so-called residual risk. On the other hand, a comprehensive safety approach has been initiated which comprises the nuclear power plant as a system together with people, technology, and organization and also includes safety culture. In a modern regulatory concept based on the dynamic development of safety, the authority's classical regulatory function of controlling is supplemented by the objective of promoting safety. While preserving the division of responsibilities between the regulatory authority and plant operators, the authority uses 'constructive critical dialog' as a tool to enhance safety. Besides the regulatory assessment of safety culture on the basis of indications or indicators, also the continuous promotion of safety culture in a dialog with plant operators is seen as one of the duties of a regulatory authority. Continued efforts are necessary to maintain the high level of safety culture in German nuclear power plants. Operators are expected to establish a safety management which assigns top priority to safety issues, and which pursues the goal of supervising and promoting safety culture. Developments on the deregulated electricity markets must not lead to safety aspects ranking second to economic aspects. Moreover, also under changed boundary conditions, only the safe operation of nuclear power plants ensures economic viability. (orig.) [de

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.)

Fault Tree Analysis for Safety/Security Verification in Aviation Software

Directory of Open Access Journals (Sweden)

Andrew J. Kornecki

2013-01-01

Full Text Available The Next Generation Air Traffic Management system (NextGen is a blueprint of the future National Airspace System. Supporting NextGen is a nation-wide Aviation Simulation Network (ASN, which allows integration of a variety of real-time simulations to facilitate development and validation of the NextGen software by simulating a wide range of operational scenarios. The ASN system is an environment, including both simulated and human-in-the-loop real-life components (pilots and air traffic controllers. Real Time Distributed Simulation (RTDS developed at Embry Riddle Aeronautical University, a suite of applications providing low and medium fidelity en-route simulation capabilities, is one of the simulations contributing to the ASN. To support the interconnectivity with the ASN, we designed and implemented a dedicated gateway acting as an intermediary, providing logic for two-way communication and transfer messages between RTDS and ASN and storage for the exchanged data. It has been necessary to develop and analyze safety/security requirements for the gateway software based on analysis of system assets, hazards, threats and attacks related to ultimate real-life future implementation. Due to the nature of the system, the focus was placed on communication security and the related safety of the impacted aircraft in the simulation scenario. To support development of safety/security requirements, a well-established fault tree analysis technique was used. This fault tree model-based analysis, supported by a commercial tool, was a foundation to propose mitigations assuring the gateway system safety and security. 

Consejo de Seguridad Nuclear: the Spanish safety authority

International Nuclear Information System (INIS)

Gonzalez, E.

1993-01-01

The Spanish Authority in Nuclear Safety and Radiological Protection was created by special law in 1981. The Consejo de Seguridad Nuclear (CNS) was established independent of the Government and reporting direct to Congress. This five-member commission is responsible for assisting the Government and other institutions in safety matters, with the the authority to impose safety conditions on all activities related to radioactive materials, and particularly on the nuclear power plants. (author) 1 fig

Safety requirements for long term operation of NPPs

International Nuclear Information System (INIS)

Houdre, T.; Osouf, N.; Juvin, J.-C.

2012-01-01

In the future, the reactors operating at present will run alongside reactors of the EPR type or their equivalent, designed for a significantly higher level of safety. This raises the question of the acceptability of continued operation of reactors beyond 40 years when there is an available technology that is safer. Two objectives are therefore imperative. First, a re-evaluation of the safety level in the light of that required of EPR type reactors or their equivalent is necessary, with proposals to bring about significant and relevant improvements to the reactors. R and D work in France and elsewhere is already indicating orientations that could lead to answers, and improvements that would provide significant reductions in release in case of severe accident are being studied. Second, strict compliance of the reactors with the applicable regulations must be demonstrated. At the same time, ageing and obsolescence of the equipment will have to be managed. Where these two points are concerned, ASN expects far-reaching proposals from the licensee. With a view to a request for continued operation beyond 40 years, ASN has referred the matter to the Advisory Committee for nuclear reactors which will meet at the end of 2011 to establish the safety requirements for reactors at their fourth ten-yearly outage. (author)

TSO support to safety authorities in new reactor licensing

Energy Technology Data Exchange (ETDEWEB)

Numark, N.J.; Bowling, M.L. [Numark Associates, Inc., Washington, DC (United States)

2013-07-01

Technical Support Organizations (TSOs) can provide review assistance to a safety authority in a cost-effective and timely manner. TSO scope tailored to safety authority needs. TSOs must understand and adhere to safety authority priorities and culture. TSOs must be flexible in regulatory approaches, work locations, time zones, and languages. Safety authorities have varying technical support needs. For instance, authorities may have substantial staff and expertise on various types of commercial Nuclear Power Plants (NPP), substantial staff and expertise on a single type of commercial NPP, limited staff but with expertise on commercial NPPs or limited staff and no expertise on commercial NPPs.

Assessment of patient radiation protection in external radiotherapy departments after inspections performed by the ASN 2008

International Nuclear Information System (INIS)

Franchi, Vincent; Marchal, Carole

2009-10-01

This report proposes an assessment of patient radiation protection in external radiotherapy. It is based on inter-regional syntheses of inspections performed by the ASN in external radiotherapy departments during 2008. It addresses 6 main themes related to patient radiation protection: human and material resources, organisation of medical physics, training in patient radiation protection, mastering of equipment (maintenance, internal quality controls of medical devices), safety and care quality management (formalization of the patient care process and definition of responsibilities, patient identity control, treatment preparation, and treatment execution), and risk management (a priori risk analysis, declaration, recording and internal processing of dysfunctions, improvements of care quality and safety management system)

Complementary assessment of the safety of French nuclear power plants

International Nuclear Information System (INIS)

Camarcat, N.; Pouget-Abadie, X.

2011-01-01

As an immediate consequence of the Fukushima accident the French nuclear safety Authority (ASN) asked EDF to perform a complementary safety assessment for each nuclear power plant dealing with 3 points: 1) the consequences of exceptional natural disasters, 2) the consequences of total loss of electrical power, and 3) the management of emergency situations. The safety margin has to be assessed considering 3 main points: first a review of the conformity to the initial safety requirements, secondly the resistance to events overdoing what the facility was designed to stand for, and the feasibility of any modification susceptible to improve the safety of the facility. This article details the specifications of such assessment, the methodology followed by EDF, the task organization and the time schedule. (A.C.)

Demand of authorization to create the 'Flamanville 3' Basis Nuclear Installation. Synthesis report of the technical examination; Demande d'autorisation de creation de l'INB 'Flamanville 3'. Rapport de synthese de l'examen technique

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-02-15

The present report has for objective to present to the College of Asn a synthesis of the technical instruction piloted by the services of Asn and realized by their technical supports (I.R.S.N., G.P.R., S.P.N.) during the period 2001-2006. After a reminder of the conditions of the examination of the safety options of the project EPR made between 1993 and 2000, this report explains the progress and the modalities of the instruction realized from 2001 till 2006. It draws up then, besides a notice of the Asn services at request of creation authorization, a synthesis of the technical examination realized according to axes presented on the fig 1. Finally, it presents the main lines of the examination that it would stay to realize if the creation authorization was delivered. (N.C.)

Labour inspection in nuclear power plant

International Nuclear Information System (INIS)

Vallet, J.; Polge, Ch.

2009-01-01

The French nuclear safety authority is in charge of labour inspection in nuclear power plants due to historical reasons. Thus, fifteen agents of ASN are acting simultaneously as nuclear inspectors and labour inspectors: they fulfill in the fifty eight reactor operated by EDF. ASN labour inspectors have the same rights ant duties than labour inspectors who fulfill in other French administrations. The regulatory domain is exactly the same. The work of ASN labour inspectors is divided in two main parts checking, on the one hand health and safety regulation requirements and on the other hand, social laws requirements. ASN labour inspectors assume, on their own, most of the decision they have to bring out. Nevertheless, ASN labour inspectors meet each other four times a year in order to share experiences. ASN labour inspectors and nuclear safety inspectors work together in the nuclear power plant. Its the principal benefit of this organisation. A high nu-clear safety level can not be reach without a good work conditions and social dialogue with labour unions. (author)

The safety of radioactive materials transport; La surete des transports de matieres radioactives

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The rule of the radioactive materials transport contains two different objectives: the safety, or physical protection, consists in preventing the losses, the disappearances, the thefts and the diversions of the nuclear materials (useful materials for weapons); the high civil servant of defence near the Minister of Economy, Finance and Industry is the responsible authority; the safety consists in mastering the risks of irradiation, contamination and criticality presented by the radioactive and fissile materials transport, in order that man and environment do not undergo the nuisances. The control of the safety is within the competence of the Asn. (N.C.)

Annual report ''nuclear safety in France''; Le rapport annuel ''la surete nucleaire en France''

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

The Inspector General's report on Nuclear Safety and Radiation Protection 2010

International Nuclear Information System (INIS)

2010-01-01

This document is proposed in French and in English. The author reports, comments and discusses the observations he made during 2010 on different aspects or examples regarding nuclear safety management and radioprotection in the EDF Group, the world's largest nuclear operator with 73 reactors in service: safety management, radioprotection, relationship with the French nuclear safety authority (ASN), skills and training, the implementation and action of an integrated nuclear engineering force, the relationship between safety and business efficiency, actors of the health care sector, the case of the Flamanville EPR reactor, the relationships with contractors, fire hazards, and projects aimed at raising standards. He also addresses observations and information about what is going on in the United Kingdom. He comments a radioprotection incident, the case of an uncontrolled dilution, and a railway accident which occurred in 2006. He gives a brief report of missions in China and in the United States

Reports by the Parliamentary Office for scientific and technological assessments. Tuesday, May 31, 2011. Hearing opened to the press on the organization of nuclear safety

International Nuclear Information System (INIS)

2011-05-01

Members of the French Parliament, and representatives of the French nuclear safety authority (ASN), of the European Nuclear Safety Regulators Group (ENSREG), of the IAEA, of the World Association of Nuclear Operators (WANO), of the French institute for radiation protection and nuclear safety (IRSN) first address the international dimension of nuclear safety control. They describe, comment and discuss the situation of the Fukushima nuclear plant, the impact of this accident on France (cooperation with Japan, atmospheric measurement in France), the different national approaches to nuclear safety, the specifications for the audit of the French nuclear power plants and the security assessments foreseen for the European nuclear stock, the issue of international standard elaboration, the activity of the WANO in the field of international cooperation. In a second part, members of Parliament and representatives of the ASN, the IRSN, EDF, and AREVA and of the French committee of certification of companies for the training and monitoring of personnel working under ionizing radiation (CEFRI) describe, comment and discuss the nuclear safety modalities in France

N-Glycosylation analysis of yeast Carboxypeptidase Y reveals the ultimate removal of phosphate from glycans at Asn368.

Science.gov (United States)

B S, Gnanesh Kumar; Surolia, Avadhesha

2017-05-01

Carboxypeptidase Y from Saccharomyces cerivisiae was characterized for its site specific N-glycosylation through mass spectrometry. The N-glycopeptides were derived using non specific proteases and are analysed directly on liquid chromatography coupled to ion trap mass spectrometer in tandem mode. The evaluation of glycan fragment ions and the Y 1 ions (peptide+HexNAc) +n revealed the glycan sequence and the corresponding site of attachment. We observed the microheterogeneity in N-glycans such as Man 11-15 GlcNAc 2 at Asn 13 , Man 8-12 GlcNAc 2 at Asn 87 , Man 9-14 GlcNAc 2 at Asn 168 and phosphorylated Man 12-17 GlcNAc 2 as well as Man 11-16 GlcNAc 2 at Asn 368 . The presence of N-glycans with Man <18 GlcNAc 2 indicated that in vacuoles the steady release of mannose/phospho mannose residues from glycans occurs initially at Asn 13 or Asn 168 followed by at Asn 368 . However, glycans at Asn 87 which comprises Man 8-12 residues as reported earlier remain intact suggesting its inaccessibility for a similar processing. This in turn indicates the interaction of the glycan at Asn 87 with the polypeptide chain implicating it in the folding of the protein. Copyright © 2017 Elsevier B.V. All rights reserved.

The risk of shortage of radioelements at medical use must not lead to overlook the reactors safety that produce them; Le risque de penurie de radioelements a usage medical ne doit pas conduire a faire l'impasse sur la surete des reacteurs qui les produisent

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

As the reactors supplying the world production of radioelements for medical use have over 40 years of operation, the nuclear safety authority alerts the stake holders on the necessity to prevent the conflicts between public health and nuclear safety in the production of these elements; Asn estimates that the solution is not to extend the lifetime of the reactors but goes for a new international concerted approach. The most of the present production comes from five old reactors: N.R.U. at Chalk river (Canada, 40%), H.F.R. at Petten (Netherlands, 30%), Safari at Pelindaba (South Africa, 10%) B.R.2 at Mol (Belgium, 9%) and Osiris at Saclay (France, 5%). In this context, Asn organised in january 2009 a seminar on the safety-availability of facilities of radio-isotopes production with safety authorities of the concerned countries. Nea organised a seminar on the radiopharmaceuticals supply at the end of january 2009. (N.C.)

Nuclear Safety Authority independence, progresses to be considered

International Nuclear Information System (INIS)

Delzangles, Hubert

2013-01-01

The Nuclear Safety Authority is an independent administrative body. Nevertheless, functional and organic independence from operators and government can have different degrees. Having a look on the actual context, where government holds a large part of the main nuclear French operators, independence has to be maximal in order to avoid any conflict of interest that could attempt to nuclear safety. In a global point of view, it is possible to think about the risks or the benefits of the institutionalized cooperation between national regulators on the necessary independence of the Nuclear Safety Authority

Organizing a complex transport while guaranteeing safety and transparency: the example of vitrified wastes sent back to Germany

International Nuclear Information System (INIS)

Krochmaluk, Julie; Lebrun, Marc; Delmestre, Alain; Barbey, Pierre; Bonvalot, Vanessa; Belleville, Didier; Rollinger, Patrice; Alter, Ulrich

2012-01-01

This chapter is made of several small articles entitled: - 'Les controles avant le depart du convoi franco-allemand' (Controls before the departure of the French-German convoy); - 'La supervision des transports de matieres radioactives: une approche extensive de la surete des operations' (The supervision of radioactive material transports: an extended approach of operation safety); - 'Le dispositif d'information du public sur le transport des substances radioactives mis en place par l'ASN' (The plan implemented by the ASN for public information on nuclear materials transport); - 'Le recours de l'ASN a l'expertise de l'ACRO sur le convoi de colis de dechets vitrifies vers l'Allemagne' (The appeal of the ASN to the ACRO's expertise on the vitrified parcel convoy to Germany); - 'La participation du collectif STOP-EPR a l'inspection de l'ASN du convoi de colis de dechets vitrifies vers l'Allemagne' (The participation of the STOP-EPR collective to the control by the ASN of the vitrified parcel convoy to Germany); - 'La securite et la surete: des valeurs que le Groupe SNCF partage' (Security and safety: values which are shared by the SNCF Group); - 'Le transport de matieres nucleaires entre la France et l'Allemagne au cours des 40 dernieres annees' (Transport of nuclear materials between France and Germany during the last 40 years). Addressing the case of vitrified wastes transported back to Germany, the articles indicate the controls performed in France before convoy departure, discuss the approach adopted for the safety of radioactive material transport, comment the management of public information by the ASN for such transports, comment the intervention of the ACRO (Association for the control of radioactivity in western France) on the request of the ASN and the participation of a collective group (STOP-EPR) to the inspection of a convoy, outline the commitment of the French Railways (SNCF) in terms of security and safety, and give a qualitative and quantitative

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

International Nuclear Information System (INIS)

Khazanov, A.L.

2005-01-01

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

Determination of discharge authorizations for French basic nuclear installations 58 and public information

International Nuclear Information System (INIS)

Tabard, Laurence; Conte, Dorothee

2013-01-01

The determination of discharge authorized limits for a French nuclear site is initiated by the request of the operator, based on the maximum nuclear and chemical inventory that could be released during normal operating conditions, accompanied with justifications. Request and justifications are analyzed and discussed by the ASN and the IRSN, taking into account nuclear and chemical inventories expected inside BNI, current regulations (BNI specific regulation, environment code, public health code), operating feedback (release feedback for an operating BNI, feedback coming from other nuclear sites or installations, etc.) and best available technologies that can be used to treat liquid or gaseous waste before release. After taking into account potential suggestions coming from public information or public enquiry concerning the operator request, the discharge authorized limits are settled down in specific ASN prescriptions that have to be ratified by the State secretaries in charge of nuclear safety. The whole process runs through 2 or 3 years to be achieved. Communication has revealed to be quite an uneasy task, even for administrative procedures. This aspect is mostly tested while communicating about events. Consequences of this communication can hardly be foreseen because of multiple external parameters like: news on the front pages at the same moment; historic communication difficulties still in the public mind; technical vocabulary not easily understood; public fear of things being hidden; power of ecologist or non-governmental associations. (authors)

Days on safety of industrial radiographic controls

International Nuclear Information System (INIS)

2008-01-01

This program is divided in three parts: the context and the regulations, the preparation and the implementation, the tools of prevention and the initiatives and the perspectives.In the first part devoted to the context and regulation are: the context by the Authority of nuclear safety (A.S.N.), the regulation referential, the transport of gamma-graphs; in the second part are the distribution of liabilities, materials and associated requirements, the feedback of incidents and exploitation of it, training and base requirements, works of S.F.R.P./C.O.F.R.E.N.D. and the A.S.N. position; the third part includes help to evaluation of risks at working places of industry radiologists, dosimetry study of a working place, guide to evaluate oneself; the fourth part devoted to the initiatives and the perspectives are: regional experiences charters of good practices in industry radiography, integration of works and deployment by the members of the C.O.F.R.E.N.D., perspectives in matter of prevention of occupational risks in the area of industry radiography. (N.C.)

Asparaginase treatment side-effects may be due to genes with homopolymeric Asn codons (Review-Hypothesis)

Science.gov (United States)

BANERJI, JULIAN

2015-01-01

The present treatment of childhood T-cell leukemias involves the systemic administration of prokary-otic L-asparaginase (ASNase), which depletes plasma Asparagine (Asn) and inhibits protein synthesis. The mechanism of therapeutic action of ASNase is poorly understood, as are the etiologies of the side-effects incurred by treatment. Protein expression from genes bearing Asn homopolymeric coding regions (N-hCR) may be particularly susceptible to Asn level fluctuation. In mammals, N-hCR are rare, short and conserved. In humans, misfunctions of genes encoding N-hCR are associated with a cluster of disorders that mimic ASNase therapy side-effects which include impaired glycemic control, dislipidemia, pancreatitis, compromised vascular integrity, and neurological dysfunction. This paper proposes that dysregulation of Asn homeostasis, potentially even by ASNase produced by the microbiome, may contribute to several clinically important syndromes by altering expression of N-hCR bearing genes. By altering amino acid abundance and modulating ribosome translocation rates at codon repeats, the microbiomic environment may contribute to genome decoding and to shaping the proteome. We suggest that impaired translation at poly Asn codons elevates diabetes risk and severity. PMID:26178806

Asparaginase treatment side-effects may be due to genes with homopolymeric Asn codons (Review-Hypothesis).

Science.gov (United States)

Banerji, Julian

2015-09-01

The present treatment of childhood T-cell leukemias involves the systemic administration of prokaryotic L-asparaginase (ASNase), which depletes plasma Asparagine (Asn) and inhibits protein synthesis. The mechanism of therapeutic action of ASNase is poorly understood, as are the etiologies of the side-effects incurred by treatment. Protein expression from genes bearing Asn homopolymeric coding regions (N-hCR) may be particularly susceptible to Asn level fluctuation. In mammals, N-hCR are rare, short and conserved. In humans, misfunctions of genes encoding N-hCR are associated with a cluster of disorders that mimic ASNase therapy side-effects which include impaired glycemic control, dislipidemia, pancreatitis, compromised vascular integrity, and neurological dysfunction. This paper proposes that dysregulation of Asn homeostasis, potentially even by ASNase produced by the microbiome, may contribute to several clinically important syndromes by altering expression of N-hCR bearing genes. By altering amino acid abundance and modulating ribosome translocation rates at codon repeats, the microbiomic environment may contribute to genome decoding and to shaping the proteome. We suggest that impaired translation at poly Asn codons elevates diabetes risk and severity.

Nuclear Safety and Radiation Protection in France in 2005

International Nuclear Information System (INIS)

2006-04-01

In 2005, the Asn pursued its significant investment in radiation protection and reaffirms its ambition to become as efficient in radiation protection as it is in nuclear safety as of 2009. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. The Asn plans to step up its efforts to ensure better monitoring of patient exposure to ionizing radiation and to provide better management of radon-related risks, particularly in housing. Fully aware that its newfound power in this area requires outside evaluation, the Asn has asked the International Atomic Energy Agency (IAEA) to organize an I.R.R.S. (Integrated Regulatory Review Service) assignment consisting of a peer-conducted audit. The IAEA has confirmed that this audit will take place in November 2006. (N.C.)

ASN1-encoded asparagine synthetase in floral organs contributes to nitrogen filling in Arabidopsis seeds.

Science.gov (United States)

Gaufichon, Laure; Marmagne, Anne; Belcram, Katia; Yoneyama, Tadakatsu; Sakakibara, Yukiko; Hase, Toshiharu; Grandjean, Olivier; Clément, Gilles; Citerne, Sylvie; Boutet-Mercey, Stéphanie; Masclaux-Daubresse, Céline; Chardon, Fabien; Soulay, Fabienne; Xu, Xiaole; Trassaert, Marion; Shakiebaei, Maryam; Najihi, Amina; Suzuki, Akira

2017-08-01

Despite a general view that asparagine synthetase generates asparagine as an amino acid for long-distance transport of nitrogen to sink organs, its role in nitrogen metabolic pathways in floral organs during seed nitrogen filling has remained undefined. We demonstrate that the onset of pollination in Arabidopsis induces selected genes for asparagine metabolism, namely ASN1 (At3g47340), GLN2 (At5g35630), GLU1 (At5g04140), AapAT2 (At5g19950), ASPGA1 (At5g08100) and ASPGB1 (At3g16150), particularly at the ovule stage (stage 0), accompanied by enhanced asparagine synthetase protein, asparagine and total amino acids. Immunolocalization confined asparagine synthetase to the vascular cells of the silique cell wall and septum, but also to the outer and inner seed integuments, demonstrating the post-phloem transport of asparagine in these cells to developing embryos. In the asn1 mutant, aberrant embryo cell divisions in upper suspensor cell layers from globular to heart stages assign a role for nitrogen in differentiating embryos within the ovary. Induction of asparagine metabolic genes by light/dark and nitrate supports fine shifts of nitrogen metabolic pathways. In transgenic Arabidopsis expressing promoter Ca MV 35S ::ASN1 fusion, marked metabolomics changes at stage 0, including a several-fold increase in free asparagine, are correlated to enhanced seed nitrogen. However, specific promoter Napin2S ::ASN1 expression during seed formation and a six-fold increase in asparagine toward the desiccation stage result in wild-type seed nitrogen, underlining that delayed accumulation of asparagine impairs the timing of its use by releasing amide and amino nitrogen. Transcript and metabolite profiles in floral organs match the carbon and nitrogen partitioning to generate energy via the tricarboxylic acid cycle, GABA shunt and phosphorylated serine synthetic pathway. © 2017 The Authors The Plant Journal © 2017 John Wiley & Sons Ltd.

Report on transparency and nuclear safety 2015 - Saclay

International Nuclear Information System (INIS)

2016-06-01

This document proposes, first, a presentation of the Saclay CEA centre, of its activities and installations. Then it gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. Next, it reports significant events related to safety and to radiation protection which occurred in 2015 and which have been declared to the French nuclear safety authority (ASN). It discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. Finally, it addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre. It indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and environment. Nature and quantities of warehoused wastes are specified. Remarks and recommendations of the Health, Safety and Working Conditions Committee (CHSCT) are given

Report on transparency and nuclear safety 2015 - Grenoble

International Nuclear Information System (INIS)

2016-06-01

This document proposes, first, a presentation of the Grenoble CEA centre, of its activities and installations. Then it gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. Next, it reports significant events related to safety and to radiation protection which occurred in 2015 and which have been declared to the French nuclear safety authority (ASN). It discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. Finally, it addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre. It indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and environment. Nature and quantities of warehoused wastes are specified. Remarks and recommendations of the Health, Safety and Working Conditions Committee (CHSCT) are given

Structural insight into gene transcriptional regulation and effector binding by the Lrp/AsnC family

NARCIS (Netherlands)

Thaw, P.; Sedelnikova, S.E.; Muranova, T.; Wiese, S.; Ayora, S.; Alonso, J.C.; Brinkman, A.B.; Akerboom, A.P.; Oost, van der J.; Rafferty, J.B.

2006-01-01

The Lrp/AsnC family of transcriptional regulatory proteins is found in both archaea and bacteria. Members of the family influence cellular metabolism in both a global (Lrp) and specific (AsnC) manner, often in response to exogenous amino acid effectors. In the present study we have determined both

Transposon mutagenesis of probiotic Lactobacillus casei identifies asnH, an asparagine synthetase gene involved in its immune-activating capacity.

Science.gov (United States)

Ito, Masahiro; Kim, Yun-Gi; Tsuji, Hirokazu; Takahashi, Takuya; Kiwaki, Mayumi; Nomoto, Koji; Danbara, Hirofumi; Okada, Nobuhiko

2014-01-01

Lactobacillus casei ATCC 27139 enhances host innate immunity, and the J1 phage-resistant mutants of this strain lose the activity. A transposon insertion mutant library of L. casei ATCC 27139 was constructed, and nine J1 phage-resistant mutants out of them were obtained. Cloning and sequencing analyses identified three independent genes that were disrupted by insertion of the transposon element: asnH, encoding asparagine synthetase, and dnaJ and dnaK, encoding the molecular chaperones DnaJ and DnaK, respectively. Using an in vivo mouse model of Listeria infection, only asnH mutant showed deficiency in their ability to enhance host innate immunity, and complementation of the mutation by introduction of the wild-type asnH in the mutant strain recovered the immuno-augmenting activity. AsnH protein exhibited asparagine synthetase activity when the lysozyme-treated cell wall extracts of L. casei ATCC 27139 was added as substrate. The asnH mutants lost the thick and rigid peptidoglycan features that are characteristic to the wild-type cells, indicating that AsnH of L. casei is involved in peptidoglycan biosynthesis. These results indicate that asnH is required for the construction of the peptidoglycan composition involved in the immune-activating capacity of L. casei ATCC 27139.

Transposon mutagenesis of probiotic Lactobacillus casei identifies asnH, an asparagine synthetase gene involved in its immune-activating capacity.

Directory of Open Access Journals (Sweden)

Masahiro Ito

Full Text Available Lactobacillus casei ATCC 27139 enhances host innate immunity, and the J1 phage-resistant mutants of this strain lose the activity. A transposon insertion mutant library of L. casei ATCC 27139 was constructed, and nine J1 phage-resistant mutants out of them were obtained. Cloning and sequencing analyses identified three independent genes that were disrupted by insertion of the transposon element: asnH, encoding asparagine synthetase, and dnaJ and dnaK, encoding the molecular chaperones DnaJ and DnaK, respectively. Using an in vivo mouse model of Listeria infection, only asnH mutant showed deficiency in their ability to enhance host innate immunity, and complementation of the mutation by introduction of the wild-type asnH in the mutant strain recovered the immuno-augmenting activity. AsnH protein exhibited asparagine synthetase activity when the lysozyme-treated cell wall extracts of L. casei ATCC 27139 was added as substrate. The asnH mutants lost the thick and rigid peptidoglycan features that are characteristic to the wild-type cells, indicating that AsnH of L. casei is involved in peptidoglycan biosynthesis. These results indicate that asnH is required for the construction of the peptidoglycan composition involved in the immune-activating capacity of L. casei ATCC 27139.

Safety assessment of smoke flavouring primary products by the European Food Safety Authority

NARCIS (Netherlands)

Theobald, A.; Arcella, D.; Carere, A.; Croera, C.; Engel, K.H.; Gott, D.; Gurtler, R.; Meier, D.; Pratt, I.; Rietjens, I.M.C.M.; Simon, R.; Walker, R.

2012-01-01

This paper summarises the safety assessments of eleven smoke flavouring primary products evaluated by the European Food Safety Authority (EFSA). Data on chemical composition, content of polyaromatic hydrocarbons and results of genotoxicity tests and subchronic toxicity studies are presented and

Summary of the report A.S.N. n. 2006 ENSTR 019 - IGAS n. RM 2007-015P on the Epinal radiotherapy accident; Resume du rapport ASN n. 2006 ENSTR 019 - IGAS n. RM 2007-015P sur l'accident de radiotherapie d'Epinal

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The Nuclear Safety Authority (A.S.N.) and the General Inspection of Social Affairs (I.G.A.S.) have been in charge by the Ministry of an inquiry on the accident that has lead to the overdose of 23 patients irradiated for a prostate cancer at the Hospital of Epinal. This event constitutes the most important accident implying the ionizing radiations occurring in France. In may 2004, the protocol of conformal radiotherapy applied to the prostate cancers has been modified, it uses dynamics corners in place of static corners. This change supposes to modify the parameters definition that gives the calculation of irradiation intensity, that will not not be made for some of patients. This mistake could be changed if the in vivo dosimetry that allows to check the real dose received by the patients had been kept. but this line of safety has been removed, the use of dynamic corners making it ineffective. The period of over irradiation has been from the 6. may 2004 to the 1. august 2005. During the summer 2005, the radiotherapist and radio physicist find the overdose error by examining the patients files again. On the 15. september 2005, the two doctors of the service warn the director of the C.H.J.M. (hospital center of Jean Monnet) of the accident that informs D.D.A.S.S. (departmental direction of sanitary and social affairs) and A.R.H. (regional agencies of hospitalization). But the national authorities (A.F.S.S.A.P.S., A.S.N., I.R.S.N.) have not been warned, and so nobody can recognize the unsuitable character of the decided measures. Only seven patients are informed of the overdose of radiations they received during the last trimester 2005. The assistance to the victims is not organised the first year. All the patients have received usual treatments when they should receive a treatment by graft of mesenchymatous stem cells. Between september 2005 and september 2006 four patients died and ten present serious complications. propositions have been made to help the victims and

Changes in FGFR2 amino-acid residue Asn549 lead to Crouzon and Pfeiffer syndrome with hydrocephalus

Directory of Open Access Journals (Sweden)

Caroline Apra

2016-10-01

Full Text Available Mutations in Fibroblast Growth Factor Receptor II (FGFR2 have been identified in patients with Crouzon and Pfeiffer syndrome, among which rare mutations of the intracellular tyrosine kinase domain. Correlating subtle phenotypes with each rare mutation is still in progress. In Necker-Enfants Malades Hospital, we identified three patients harboring three different pathogenic variants of the same amino acid residue Asn-549 located in this domain: in addition to a very typical crouzonoid appearance, they all developed clinically relevant hydrocephalus, which is an inconstant feature of Crouzon and Pfeiffer syndrome. Overall, FGFR2 tyrosine kinase domain mutations account for 5/67 (7.4% cases in our hospital. We describe a novel mutation, p.Asn549Ser, and new cases of p.Asn549His and p.Asn549Thr mutations, each reported once before. Our three cases of Asn-549 mutations, alongside with rare previously reported cases, show that these patients are at higher risk of hydrocephalus. Clinical and imaging follow-up, with possible early surgery, may help prevent secondary intellectual disability.

Operational safety of geological disposal: IRSN project 'EXREV' for developing a safety assessment strategy for the operation and reversibility of a geological repository

International Nuclear Information System (INIS)

Tichauer, M.; Pellegrini, D.; Serres, C.; Besnus, F.

2014-01-01

A high-level waste geological disposal facility is envisioned by the legislator in the French Planning Act no. 2006-739 of 28 June 2006. This act sets major milestones for the operator (Andra) in 2013 (public debate), 2015 (licensing) and 2025 (operation). In the framework of the regulatory review process, IRSN's mission is to conduct an assessment of the safety case provided by Andra at every stage of the process for the French regulator, namely the Nuclear Safety Authority (ASN). In 2005, IRSN gathered more than twenty years of research and expertise in order to provide a comprehensive appraisal of the 'Dossier 2005' prepared by Andra, related to the feasibility of a geological disposal in the Callovo-Oxfordian clay formation. At this time, the description of the operational phase was only at a preliminary stage, but this step paved the way for developing an assessment strategy of the operational phase. In this perspective, IRSN set up the EXREV project in 2008 in order to build up a doctrine and to identify key safety issues to be dealt with. (authors)

Annual report ''nuclear safety in France''; Le rapport annuel ''la surete nucleaire en France''

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

This document is the 2001 annual report of the French authority of nuclear safety (ASN). It summarizes the highlights of the year 2000 and details the following aspects: the nuclear safety in France, the organization of the control of nuclear safety, the regulation relative to basic nuclear facilities, the control of facilities, the information of the public, the international relations, the organisation of emergencies, the radiation protection, the transport of radioactive materials, the radioactive wastes, the PWR reactors, the experimental reactors and other laboratories and facilities, the nuclear fuel cycle facilities, and the shutdown and dismantling of nuclear facilities. (J.S.)

The protein C omega-loop substitution Asn2Ile is associated with reduced protein C anticoagulant activity.

LENUS (Irish Health Repository)

Preston, Roger J S

2012-02-01

We report a kindred with heritable protein C (PC) deficiency in which two siblings with severe thrombosis showed a composite type I and IIb PC deficiency phenotype, identified using commercial PC assays (proband: PC antigen 42 u\\/dl, amidolytic activity 40 u\\/dl, anticoagulant activity 9 u\\/dl). The independent PROC nucleotide variations c.669C>A (predictive of Ser181Arg) and c.131C>T (predictive of Asn2Ile) segregated with the type I and type IIb PC deficiency phenotypes respectively, but co-segregated in the siblings with severe thrombosis. Soluble thrombomodulin (sTM)-mediated inhibition of plasma thrombin generation from an individual with PC-Asn2Ile was lower (endogenous thrombin potential (ETP) 56 +\\/- 1% that of ETP determined without sTM) than control plasma (ETP 15 +\\/- 2%) indicating reduced PC anticoagulant activity. Recombinant APC-Asn2Ile exhibited normal amidolytic activity but impaired anticoagulant activity. Protein S (PS)-dependent anticoagulant activity of recombinant APC-Asn2Ile and binding of recombinant APC-Asn2Ile to endothelial protein C receptor (EPCR) were reduced compared to recombinant wild-type APC. Asn2 lies within the omega-loop of the PC\\/APC Gla domain and this region is critical for calcium-induced folding and subsequent interactions with anionic phospholipids, EPCR and PS. The disruption of these interactions in this naturally-occurring PC variant highlights their collective importance in mediating APC anticoagulant activity in vivo.

Relations between the safety authority and the nuclear power plant operators

International Nuclear Information System (INIS)

Laverie, M.; Flandrin, R.

1991-01-01

The French experience has led the safety authority to pay particular attention to the competence of a nuclear operator and to the exercise of his responsibility. In this context, safety does not seem to be improved by the imposition of too many regulations and control activities. On the contrary, an excessive regulatory framework may blunt the operator's awareness of his responsibility. It is the duty of the safety authority to fix the safety objectives. It is the operator's duty to establish the practical conditions for attaining these objectives and to justify these conditions to the safety authority. It is also his duty to implement them correctly. The authority must then verify the quality of this implementation by random inspection methods. Each of the two partners, each conforming to his role and exercise of his particular responsibilities, must remain vigilant. These different actions necessitate a permanent technical dialogue which is not in contradiction with the exercise of strict regulatory control. (orig.)

Creating a safety culture in the regulatory authority: The Cuban experience

International Nuclear Information System (INIS)

Ferro Fernandez, R.; Guillen Campos, A.

2002-01-01

The Cuban regulatory authority has been working during several years for the fostering and development of a high Safety Culture level in nuclear activities in the country. As starting point to achieve this objective the assessment of the Safety Culture level in the regulatory authority performance was considered an important issue. For this purpose a preliminary diagnosis was carried out by means of a national survey that allowed identifying some areas of the regulatory activity that required improvements in order to achieve a higher Safety Culture and to immediately implement appropriate actions. Two of the most important actions undertaken were: the statement of the regulatory authority Safety Policy which governs and determines the performance of this organization and its staff and also the implementation of a new interaction practice at top level between the regulatory authority and the utilities of the nuclear sector through the Annual Regulatory Conference. The present paper summarizes these two introduced practices into the Cuban regulatory activity. (author)

Polymorphisms in XPD (Asp312Asn and Lys751Gln) genes, sunburn and arsenic-related skin lesions.

Science.gov (United States)

McCarty, Kathleen M; Smith, Thomas J; Zhou, Wei; Gonzalez, Ernesto; Quamruzzaman, Quazzi; Rahman, Mahmuder; Mahiuddin, Golam; Ryan, Louise; Su, Li; Christiani, David C

2007-08-01

Single-nucleotide polymorphisms in genes related to DNA repair capacity and ultraviolet exposure have not been well investigated in relation to skin lesions associated with arsenic exposure. This population based case-control study, of 600 cases and 600 controls, frequency matched on age and gender in Pabna, Bangladesh, in 2001-2002, investigated the association and potential effect modification between polymorphisms in Xeroderma Pigmentosum complementation group D (XPD) (Lys751Gln and Asp312Asn) genes, tendency to sunburn and arsenic-related skin lesions. Unconditional logistic regression was used to estimate odds ratios (ORs) and 95% confidence intervals (CIs). No significant association was observed between skin lesions and the XPD 312 Asp/Asn (adjusted OR = 0.87, 95% CI = 0.65-1.15) Asn/Asn (adjusted OR = 0.76, 95% CI = 0.50-1.15) (referent Asp/Asp); XPD 751 Lys/Gln (adjusted OR = 0.92, 95% CI = 0.69-1.23) Gln/Gln (adjusted OR = 0.98, 95% CI = 0.66-1.45) (referent Lys/Lys). While we did not observe any evidence of effect modification of these polymorphisms on the association between well arsenic concentration and skin lesions, we did observe effect modification between these polymorphisms and sunburn tendency and arsenic-related skin lesions. Individuals with the heterozygote or homozygote variant forms (Asp/Asn or Asn/Asn) had half the risk of skin lesions (OR = 0.45, 95% CI = 0.29-0.68) compared with those with the wild-type XPDAsp312Asn genotype (Asp/Asp) and individuals with heterozygote or homozygote variant forms (Lys/Gln or Gln/Gln) had half the risk of skin lesions (OR = 0.47, 95% CI = 0.31-0.72) compared with those with the wild-type XPDLys751Gln genotype (Lys/Lys), within the least sensitive strata of sunburn severity. We observed effect modification on the multiplicative scale for XPD 751 and XPD 312. XPD polymorphisms modified the relationship between tendency to sunburn and skin lesions in an arsenic exposed population. Further study is necessary

Reports by the Parliamentary Office for scientific and technological assessments. Thursday, June 16, 2011. Transparency in nuclear safety; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 16 juin 2011. Transparence en matiere de surete nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-06-15

In a first session dedicated to modalities of transparency in the field of nuclear safety, members of the French Parliament hear and discuss the interventions of representatives of the French nuclear safety authority (ASN), AREVA, EDF, the CEA, the French institute of radiation protection and nuclear safety (IRSN), of the High committee for transparency and information on nuclear safety (HCTISN). The second session addresses the improvement of transparency and comprised interventions by representatives of the OECD and of local commissions of information (ANCCLI)

Medical radio-physics. Quality assurance. Transparency; Radiophysique medicale. Assurance de la qualite. Transparence

Energy Technology Data Exchange (ETDEWEB)

Krembel, D.

2009-07-15

This short presentation, given by the national safety authority (ASN) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), recalls, first, the missions of the ASN in the medical domain (radiation protection, control and inspections). Then it presents the reactions of the ASN in response to the increase of the number of radiological accidents since 2005: regulation reminder, circular letters, guidebooks, communication to the public and to the mass media. Finally, it defines the main priorities of the ASN with respect to radiotherapy: increase of human resources (radio-physicists shortage), declaration of incidents/accidents, quality assurance for the control of radiation doses delivered to patients, inspection of radiotherapy centres, expertise of new devices, improvement of softwares safety and ergonomics. (J.S.)

Medical radio-physics. Quality assurance. Transparency

International Nuclear Information System (INIS)

Krembel, D.

2009-07-01

This short presentation, given by the national safety authority (ASN) at the meeting of July 1, 2009 of the high committee for the nuclear safety transparency and information (HCTISN), recalls, first, the missions of the ASN in the medical domain (radiation protection, control and inspections). Then it presents the reactions of the ASN in response to the increase of the number of radiological accidents since 2005: regulation reminder, circular letters, guidebooks, communication to the public and to the mass media. Finally, it defines the main priorities of the ASN with respect to radiotherapy: increase of human resources (radio-physicists shortage), declaration of incidents/accidents, quality assurance for the control of radiation doses delivered to patients, inspection of radiotherapy centres, expertise of new devices, improvement of softwares safety and ergonomics. (J.S.)

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)

Decree no. 2005-78 from January 26, 2005, authorizing the Atomic Energy Commission to proceed to the definitive shutdown and dismantling operations of the nuclear facility no.20, named Siloe reactor, in the Grenoble city territory (Isere)

International Nuclear Information System (INIS)

2005-02-01

On March 19, 2003, the French atomic energy commission (CEA) addressed an authorization demand for the definitive shutdown and dismantling of the Siloe reactor. After a technical and administrative instruction of this demand by the French nuclear safety authority (ASN), a project of decree has been presented on July 6, 2004 at the permanent section of the inter-ministry commission of basic nuclear facilities. The commission gave its favourable judgment which is the object of this decree. (J.S.)

Control of the Saclay CEA's base nuclear installations - Inspection n. INS-2010-CEASAC-0006 31 May 2010-4 June 2010 - Safety management

International Nuclear Information System (INIS)

2010-01-01

This document reports an inspection dedicated to safety management, and performed by the ASN (the French Nuclear Safety Authority) on several nuclear installations present on the CEA's Saclay site. The inspected installations have been the INBs (base nuclear installations) number 35 (STEL), 40 (Osiris), 49 (LHA), 50 (LECI), 77 (Poseidon) and 101 (Orphee), and four departments (CCSIMN, USL2TI, SP2S and DANS) involved in safety or in charge of it. The report describes the requested corrective actions about the quality of the internal diagnosis, about the follow-up of actions and directives, about internal authorizations, about the follow-up of commitments, about second level control, about the management of the return on experience, about interesting events, about the control of subcontractors. Some additional information requests are also formulated

Summary of the report A.S.N. n. 2006 ENSTR 019 - IGAS n. RM 2007-015P on the Epinal radiotherapy accident

International Nuclear Information System (INIS)

2007-01-01

The Nuclear Safety Authority (A.S.N.) and the General Inspection of Social Affairs (I.G.A.S.) have been in charge by the Ministry of an inquiry on the accident that has lead to the overdose of 23 patients irradiated for a prostate cancer at the Hospital of Epinal. This event constitutes the most important accident implying the ionizing radiations occurring in France. In may 2004, the protocol of conformal radiotherapy applied to the prostate cancers has been modified, it uses dynamics corners in place of static corners. This change supposes to modify the parameters definition that gives the calculation of irradiation intensity, that will not not be made for some of patients. This mistake could be changed if the in vivo dosimetry that allows to check the real dose received by the patients had been kept. but this line of safety has been removed, the use of dynamic corners making it ineffective. The period of over irradiation has been from the 6. may 2004 to the 1. august 2005. During the summer 2005, the radiotherapist and radio physicist find the overdose error by examining the patients files again. On the 15. september 2005, the two doctors of the service warn the director of the C.H.J.M. (hospital center of Jean Monnet) of the accident that informs D.D.A.S.S. (departmental direction of sanitary and social affairs) and A.R.H. (regional agencies of hospitalization). But the national authorities (A.F.S.S.A.P.S., A.S.N., I.R.S.N.) have not been warned, and so nobody can recognize the unsuitable character of the decided measures. Only seven patients are informed of the overdose of radiations they received during the last trimester 2005. The assistance to the victims is not organised the first year. All the patients have received usual treatments when they should receive a treatment by graft of mesenchymatous stem cells. Between september 2005 and september 2006 four patients died and ten present serious complications. propositions have been made to help the victims and

National Assembly - 2012-2013 regular session, 255. sitting, Sitting of Thursday 30 May 2013, verbatim record: Debate on nuclear safety

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Repussard, Jacques; Miniere, Dominique; Chanteguet, Jean-Paul; Batho, Delphine; Baupin, Denis; Chassaigne, Andre; Bouillon, Christophe; Mariton, Herve; Sas, Eva; Reynier, Franck; Roig, Frederic; Lambert, Francois-Michel; Valter, Clotilde; Massonneau, Veronique; Pompili, Barbara; Laponche, Bernard; Molac, Paul

2013-01-01

This document publishes the verbatim of a debate on nuclear safety in the French National Assembly. Interveners who belong to different parties and to different bodies and institutions (notably ASN, IRSN, EDF), of researchers, notably discussed the degradation of nuclear safety in France, the necessary review of the French nuclear safety framework, the implication of the ASN in the debate on energy transition, the nuclear plant lifetime, the present governance of nuclear safety, the ageing issue, the renewal of personnel abilities and qualifications, the issue of subcontracting, the possibility of a nuclear accident in France, the role of the different bodies and institutions, the evolution of the French nuclear fleet. Questions and answers are also reported

Technical nuclear safety in France. Control by the governmental authority

International Nuclear Information System (INIS)

1991-12-01

In publishing this latest edition, we have endeavoured to provide the reader with the information necessary to obtain a full understanding of the regulatory system applied to ensure technical nuclear safety in France. As the reader will discover in the following pages, technical nuclear safety is a matter which must be settled in advance of the actual operation of civil nuclear installations; the primary requirement is to mobilize those involved to anticipate and prevent. The fundamental options on which the French system is based, the relationship between the operator and the safety authority must be clearly stated: independence of judgement and decision, complementarity of responsibilities. It is for the governmental authorities to determine the technical nuclear safety objectives, which are becoming more and more consistent if not unified throughout the world. It is for the operator to propose technical provisions in order to achieve these objectives. It is for the governmental authorities to verify, by technical safety analyses, the adequacy of the provisions in terms of the defined objectives. It is for the operator to properly implement these approved provisions. And, finally, it is for the governmental authorities to verify, by sampling, the quality of their implementation and to make from them the necessary regulatory inferences. This sequence of events requires permanent frank in-depth dialogue. The effectiveness of the regulatory action must therefore reside not in close technical restraint but in the interactions between responsible partners

Technical nuclear safety in France. Control by the governmental authority

Energy Technology Data Exchange (ETDEWEB)

NONE

1991-12-15

In publishing this latest edition, we have endeavoured to provide the reader with the information necessary to obtain a full understanding of the regulatory system applied to ensure technical nuclear safety in France. As the reader will discover in the following pages, technical nuclear safety is a matter which must be settled in advance of the actual operation of civil nuclear installations; the primary requirement is to mobilize those involved to anticipate and prevent. The fundamental options on which the French system is based, the relationship between the operator and the safety authority must be clearly stated: independence of judgement and decision, complementarity of responsibilities. It is for the governmental authorities to determine the technical nuclear safety objectives, which are becoming more and more consistent if not unified throughout the world. It is for the operator to propose technical provisions in order to achieve these objectives. It is for the governmental authorities to verify, by technical safety analyses, the adequacy of the provisions in terms of the defined objectives. It is for the operator to properly implement these approved provisions. And, finally, it is for the governmental authorities to verify, by sampling, the quality of their implementation and to make from them the necessary regulatory inferences. This sequence of events requires permanent frank in-depth dialogue. The effectiveness of the regulatory action must therefore reside not in close technical restraint but in the interactions between responsible partners.

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.)

Days on safety of industrial radiographic controls; Securite des controles radiographiques industriels

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

This program is divided in three parts: the context and the regulations, the preparation and the implementation, the tools of prevention and the initiatives and the perspectives.In the first part devoted to the context and regulation are: the context by the Authority of nuclear safety (A.S.N.), the regulation referential, the transport of gamma-graphs; in the second part are the distribution of liabilities, materials and associated requirements, the feedback of incidents and exploitation of it, training and base requirements, works of S.F.R.P./C.O.F.R.E.N.D. and the A.S.N. position; the third part includes help to evaluation of risks at working places of industry radiologists, dosimetry study of a working place, guide to evaluate oneself; the fourth part devoted to the initiatives and the perspectives are: regional experiences charters of good practices in industry radiography, integration of works and deployment by the members of the C.O.F.R.E.N.D., perspectives in matter of prevention of occupational risks in the area of industry radiography. (N.C.)

Decree no. 2005-79 from January 26, 2005, authorizing the Atomic Energy Commission to proceed to the definitive shutdown and dismantling operations of the nuclear facility no.21, named Siloette research reactor, in the Grenoble city territory (Isere)

International Nuclear Information System (INIS)

2005-02-01

On May 26, 2003, the French atomic energy commission (CEA) addressed an authorization demand for the definitive shutdown and dismantling of the Siloette research reactor. After a technical and administrative instruction of this demand by the French nuclear safety authority (ASN), a project of decree has been presented on July 6, 2004 at the permanent section of the inter-ministry commission of basic nuclear facilities. The commission gave its favourable judgment which is the object of this decree. (J.S.)

N-linked glycosylation at Asn152 on CD147 affects protein folding and stability: promoting tumour metastasis in hepatocellular carcinoma.

Science.gov (United States)

Li, Jiang-Hua; Huang, Wan; Lin, Peng; Wu, Bo; Fu, Zhi-Guang; Shen, Hao-Miao; Jing, Lin; Liu, Zhen-Yu; Zhou, Yang; Meng, Yao; Xu, Bao-Qing; Chen, Zhi-Nan; Jiang, Jian-Li

2016-11-21

Cluster of differentiation 147 (CD147), also known as extracellular matrix metalloproteinase inducer, is a transmembrane glycoprotein that mediates oncogenic processes partly through N-glycosylation modifications. N-glycosylation has been demonstrated to be instrumental for the regulation of CD147 function during malignant transformation. However, the role that site-specific glycosylation of CD147 plays in its defective function in hepatocellular carcinomacells needs to be determined. Here, we demonstrate that the modification of N-glycosylation at Asn152 on CD147 strongly promotes hepatocellular carcinoma (HCC) invasion and migration. After the removal of N-glycans at Asn152, CD147 was more susceptible to degradation by ER-localized ubiquitin ligase-mediated endoplasmic reticulum-associated degradation (ERAD). Furthermore, N-linked glycans at Asn152 were required for CD147 to acquire and maintain proper folding in the ER. Moreover, N-linked glycans at Asn152 functioned as a recognition motif that was directly mediated by the CNX quality control system. Two phases in the retention-based ER chaperones system drove ER-localized CD147 trafficking to degradation. Deletion of N-linked glycosylation at Asn152 on CD147 significantly suppressed in situ tumour metastasis. These data could potentially shed light on the molecular regulation of CD147 through glycosylation and provide a valuable means of developing drugs that target N-glycans at Asn152 on CD147.

Electronuclear reactors - EDF - Orientations of generic studies to be performed for the safety re-examination of 1300 MWe reactors associated to their third decennial inspection

International Nuclear Information System (INIS)

2011-01-01

This report expresses the ASN's opinion on the framework and objectives of the EDF program concerning the generic studies of the safety re-examination of the 1300 MWe reactors associated with their third decennial inspection. This comprises lessons from the Fukushima accident, the improvement of the 'internal explosion' referential by using a probabilistic study, the application of the seismic margin assessment approach as soon as possible, checking the absence of any 'cliff effect' for cooling functions, a deepened re-examination of hurricane frequencies in France. Other request by the ASN concern the verification of the pertinence of release authorizations, taking the TSN law into account, taking the AP1300 project into account, the expansion of the complementary domain, the project of reactor lifetime extension. Some technical requests are discussed in appendix

Reports by the Parliamentary Office for scientific and technological assessments. Tuesday, May 31, 2011. Hearing opened to the press on the organization of nuclear safety; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Mardi 31 mai 2011. Audition, ouverte a la presse, sur l'organisation de la securite nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-05-15

Members of the French Parliament, and representatives of the French nuclear safety authority (ASN), of the European Nuclear Safety Regulators Group (ENSREG), of the IAEA, of the World Association of Nuclear Operators (WANO), of the French institute for radiation protection and nuclear safety (IRSN) first address the international dimension of nuclear safety control. They describe, comment and discuss the situation of the Fukushima nuclear plant, the impact of this accident on France (cooperation with Japan, atmospheric measurement in France), the different national approaches to nuclear safety, the specifications for the audit of the French nuclear power plants and the security assessments foreseen for the European nuclear stock, the issue of international standard elaboration, the activity of the WANO in the field of international cooperation. In a second part, members of Parliament and representatives of the ASN, the IRSN, EDF, and AREVA and of the French committee of certification of companies for the training and monitoring of personnel working under ionizing radiation (CEFRI) describe, comment and discuss the nuclear safety modalities in France

French safety authority projects in the field of research and test reactors

International Nuclear Information System (INIS)

Saint Raymond, P.; Duthe, M.; Abou Yehia, H.

2001-01-01

This paper gives an outline of some actions initiated by the French safety authority in the field of research and test reactors. An important action concerns the definition of the authorisation criteria for the implementation of experiments in these reactors. In particular, it is necessary to define clearly in which conditions an experiment may be authorised internally by the operating organisation or needs a formal approval by the safety authority. The practice related to the systematic safety reassessment of old facilities and the regulatory provisions associated with the decommissioning are presented after a discussion on the ageing issues. (author)

Radiation protection databases of nuclear safety regulatory authority

International Nuclear Information System (INIS)

Janzekovic, H.; Vokal, B.; Krizman, M.

2003-01-01

Radiation protection and nuclear safety of nuclear installations have a common objective, protection against ionising radiation. The operational safety of a nuclear power plant is evaluated using performance indicators as for instance collective radiation exposure, unit capability factor, unplanned capability loss factor, etc. As stated by WANO (World Association of Nuclear Operators) the performance indicators are 'a management tool so each operator can monitor its own performance and progress, set challenging goals for improvement and consistently compare performance with that of other plants or industry'. In order to make the analysis of the performance indicators feasible to an operator as well as to regulatory authorities a suitable database should be created based on the data related to a facility or facilities. Moreover, the international bodies found out that the comparison of radiation protection in nuclear facilities in different countries could be feasible only if the databases with well defined parameters are established. The article will briefly describe the development of international databases regarding radiation protection related to nuclear facilities. The issues related to the possible development of the efficient radiation protection control of a nuclear facility based on experience of the Slovenian Nuclear Safety Administration will be presented. (author)

Cyclization of the N-Terminal X-Asn-Gly Motif during Sample Preparation for Bottom-Up Proteomics

DEFF Research Database (Denmark)

Zhang, Xumin; Højrup, Peter

2010-01-01

We, herein, report a novel -17 Da peptide modification corresponding to an N-terminal cyclization of peptides possessing the N-terminal motif of X-Asn-Gly. The cyclization occurs spontaneously during sample preparation for bottom-up proteomics studies. Distinct from the two well-known N-terminal ......We, herein, report a novel -17 Da peptide modification corresponding to an N-terminal cyclization of peptides possessing the N-terminal motif of X-Asn-Gly. The cyclization occurs spontaneously during sample preparation for bottom-up proteomics studies. Distinct from the two well-known N......-terminal cyclizations, cyclization of N-terminal glutamine and S-carbamoylmethylcysteine, it is dependent on pH instead of [NH(4)(+)]. The data set from our recent study on large-scale N(α)-modified peptides revealed a sequence requirement for the cyclization event similar to the well-known deamidation of Asn to iso...

Significant event of patient radiation protection in radiotherapy (criterion 2.1): declaration and rating on the ASN-SFRO scale - ASN guide nr 16 - Release of the 01/01/2010

International Nuclear Information System (INIS)

2010-01-01

This document brings together all the tools for the management of a significant event in radiation protection concerning a patient in radiotherapy. It contains the declaration form, a model for the reporting of significant events, and the ASN-SFRO scale which allows the event to be rated. After a presentation of the regulatory context and references, of the scope of application, this guide addresses the declaration of a significant event: general principles, definition of the 2.1 criterion, examples, delays and modalities of declaration, addressees of a declaration. It addresses the reporting of a significant event: general principles, sending delays and modalities. It addresses the rating on the ASN-SFRO scale: general principles, scale, and rating process. The last part deals with public information

Significant event of patient radiation protection in radiotherapy (criterion 2.1): declaration and rating on the ASN-SFRO scale - ASN guide no. 16 - Release of 17/07/2015

International Nuclear Information System (INIS)

2015-01-01

This document is an update of the previous version from October 2010. It brings together all the tools for the management of a significant event in radiation protection concerning a patient in radiotherapy. It contains the declaration form, a model for the reporting of significant events, and the ASN-SFRO scale which allows the event to be rated. After a presentation of the regulatory context and references, of the scope of application, this guide addresses the declaration of a significant event: general principles, definition of the 2.1 criterion, examples, delays and modalities of declaration, addressees of a declaration. It addresses the reporting of a significant event: general principles, sending delays and modalities. It addresses the rating on the ASN-SFRO scale: general principles, scale, and rating process. The last part deals with public information

The control of base nuclear facilities (I.N.B.); Le controle des installations nucleaires de base (INB)

Energy Technology Data Exchange (ETDEWEB)

Anon

2009-02-15

The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear basic installations during august, september, october 2008, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

The control of base nuclear installations; Le controle des installations nucleaires de base (INB)

Energy Technology Data Exchange (ETDEWEB)

Anon

2009-04-15

The Authority of Nuclear Safety ( A.S.N). presents in this column the current events of the control of the nuclear base installations during november, december 2008 and january 2009, classified by nuclear site. This information is also available in real-time on the A.S.N. web site, www.asn.fr, in the column 'news'. We can consult all the notices of significant incident published as well as the following letters of inspection, the notices of information about the reactors shutdown, press releases and the A.S.N. information notes. (N.C.)

Pump performance and reliability follow-up by the French Safety Authorities

International Nuclear Information System (INIS)

Clausner, J.P.; De La Ronciere, X.; Scott de Martinville, E.; Courbiere, P.

1990-12-01

This paper will present, through actual examples, the methodology of the performance and reliability safety-related pumps evaluation applied by the French Safety Authorities and the lessons drawn from this evaluation

Structural investigations of the active-site mutant Asn156Ala of outer membrane phospholipase A: Function of the Asn-His interaction in the catalytic triad

NARCIS (Netherlands)

Snijder, H.J.; van Eerde, J.H.; Kalk, K.H.; Dekker, N.; Egmond, M.R.; Dijkstra, B.W.

2010-01-01

Outer membrane phospholipase A (OMPLA) from Escherichia coli is an integral-membrane enzyme with a unique His-Ser-Asn catalytic triad. In serine proteases and serine esterases usually an Asp occurs in the catalytic triad; its role has been the subject of much debate. Here the role of the uncharged

ILK statement about the regulatory authorities' perception of operators' self-assessment of safety culture

International Nuclear Information System (INIS)

2005-01-01

Over the past few years, German licensing and supervisory authorities have devoted increasing attention to safety management and safety culture issues. At present, German plant operators are introducing systems for self-assessment of the safety culture in their plants, such as the Safety Culture Assessment System developed by VGB Power Tech (VGB-SBS). In its statement, the International Committee on Nuclear Technology (ILK) addresses an effective approach of the authorities in evaluating the self-assessment of safety culture conducted by operators. ILK proposes a total of ten recommendations for evaluating the self-assessment system of the operators by the authority. The regulatory authorities should see to it that the operators establish a self-assessment system for aspects of organization and personnel, and use it continuously. The measures derived from this self-assessment by the operators, and the reasons underlying them, should be discussed with the authorities. In addition to the operators, also the regulatory authorities and the technical expert organizations commissioned by them should carry out self-assessments of their respective supervisory activities, taking into account also special events, such as changes in government, and develop appropriate programs of measures to be taken. In evaluating safety culture, the regulatory authorities should strive to support the activities of operators in improving their safety culture. A spirit of mutual confidence and cooperation should exist between operators and authorities. The recommendations expressed in the statement deliberately leave room for detailed implementation by the parties concerned. (orig.)

High committee for nuclear safety transparency and information. November 20, 2009 meeting of the High Committee

International Nuclear Information System (INIS)

2009-11-01

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, and, depending on the events, some extraordinary meetings. This document is the proceedings of an extraordinary meeting about the information and transparency in relation with the management of nuclear materials and wastes at all stages of the fuel cycle. The reason of this meeting is a request from the French Minister of ecology, energy, sustainable development and sea (MEEDDM) after the broadcast of a TV documentary entitled 'wastes: the nuclear industry nightmare' and the publication of a press article affirming that 'our nuclear wastes are hidden in Siberia'. The Minister expressed his wish to have the question of the international trade of nuclear materials examined by the HCTISN. The document is organized as follows: a first part presents the hearings of the general direction of energy and climate (DGEC), of the nuclear safety authority (ASN), of EdF, of Areva, of the CEA, of the senior official for the defense and security of the MEEDDM, of Rosatom company and of Greenpeace organisation. A second part examines the incident which took place in October 2009 at the plutonium technology workshop (ATPu) of Cadarache, where about 22 to 39 kg of plutonium powder were discovered in the gloveboxes of this facility, decommissioned in 2005 and undergoing dismantlement today. This part presents the hearings of the CEA, of AREVA, of the Institute of radiation protection and nuclear safety (IRSN), of the ASN, of the hygiene, safety and labour conditions committee (CHSCT) of Areva and CEA, and of the local information commission (CLI) of Cadarache, in relation with

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

2002-05-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

Safety assessment plans for authorization and inspection of radiation sources

International Nuclear Information System (INIS)

1999-09-01

The objective of this TECDOC is to enhance the efficacy, quality and efficiency of the whole regulatory process. It provides advice on good practice administrative procedures for the regulatory process for preparation of applications, granting of authorizations, inspection, and enforcement. It also provides information on the development and use of standard safety assessment plans for authorization and inspection. The plans are intended to be used in conjunction with more detailed advice related to specific practices. In this sense, this TECDOC provides advice on a systematic approach to evaluations of protection and safety while other IAEA Safety Guides assist the user to distinguish between the acceptable and the unacceptable. This TECDOC covers administrative advice to facilitate the regulatory process governing authorization and inspection. It also covers the use of standard assessment and inspection plans and provides simplified plans for the more common, well established uses of radiation sources in medicine and industry, i.e. sources for irradiation facilities, industrial radiography, well logging, industrial gauging, unsealed sources in industry, X ray diagnosis, nuclear medicine, teletherapy and brachytherapy

Elimination of effluents and wastes contaminated by radionuclides produced in installations authorized on the account of the Public Health Code - ASN guide nr 18 - Release of the 26/01/2012

International Nuclear Information System (INIS)

2012-01-01

This document aims at specifying the modalities of application of a decision taken by the ASN in January 2008 regarding the technical rules which the elimination of effluents and wastes contaminated by radionuclides must comply with. First, it describes the objective of the 'waste zoning' concept. Then, it addresses the management of contaminated wastes: general rules, wastes contaminated by radionuclides of very short period (less than 100 days) and of period longer than 100 days, and the management of wastes with 'hybrid risks'. It addresses the management of contaminated effluents: radioactive liquid effluent with a period either shorter or longer than 100 days, radioactive gaseous effluents. It addresses the warehousing conditions (premise design, exploitation rules). The other parts deal with the convention between several establishments within a same site (notably in the case of nuclear medicine departments), with the management plan, and with the agenda for the implementation of the ASN decision

Nuclear risk and communication: the essential role of safety authorities

International Nuclear Information System (INIS)

Hautin, N.

1998-01-01

Full text of publication follows: whether concerning mad cow disease, asbestos, nuclear, OGM or now, dioxin in French meat, public health risks have been making the headlines of newspapers for a while. And, firms whose activity is associated with these risks are in effect in the defendants box. Therefore, communicating becomes difficult: their word is suspect and, debates quite rapidly exceed the firm competencies to become a socio-cultural conflict. This paper explores in nuclear fields the essential role of safety authorities in such communication cases. Our surveys and the comparative case study between the pipe at La Hague and 'contaminated' nuclear transports in France are eloquent: the messages of nuclear firms is perceived through their image of a State within the State built from the past and reinforced by the negative prism of the news. Regular and technical arguments (the respect of norms) entertain the debate rather than hush it. That is why we could infer an objective, and independent opinion is required, one different from the firm, the public and ministries: its role of referee could allow a constructive dialog between the public and the firm. Risk communication nature and efficiency depend on that (cf. the diagram). As a solution, we think about a legitimate authority organization identified by the public first, but by other actors as well. From the public point of view, if we see the place of pressure groups (e.g. Greenpeace) in the debate as a measure of the lack of trust in the independence of safety authorities, we can infer that it is a reaffirmation of democracy which is demanded by the French public, which could be satisfied with powerful safety authorities. That is why safety authorities have an essential role to play, beyond this of control, in nuclear risk communication towards the public. Diagram: communication path between a nuclear firm and the public during conflict. (author)

Expertise of safety of the Flamanville EPR reactor. Manche inhabitants worry, the Institute answer them

International Nuclear Information System (INIS)

2014-01-01

A first article gives some examples of activities and of the influence of experts who, at each step of the construction of the EPR in Flamanville and until its operation, check whether safety requirements are met. For example, strain gauges are used to control the behaviour of the containment all along its construction. Safety objectives for the EPR have been defined by French and German authorities who decided some design evolutions: number of emergency generators, use of a new water resource to cool the fuel in case of accident, safety systems. In a brief interview, the EDF technical manager evokes the lessons learned from Fukushima from a technical point of view as well as in terms of personnel, and evokes some modifications of the EPR project. A brief article evokes the participation of the IRSN to the Finnish EPR project. A last article addresses the cooperative activities of the local information commissions and other involved actors (IRSN, ASN, EDF, Areva) about the safety of the installation

Cooperation between the French and German safety authorities: a process of progress

International Nuclear Information System (INIS)

Lacoste, A.C.; Hennenhoefer, G.

1996-01-01

Considerable efforts are devoted in several countries worldwide for the designing of a new generation of electro-nuclear reactors with noticeable safety improvements with respect to the existing units. The EPR (European Pressurized water Reactor) project is the first example of a joint survey and collaboration effort between two countries, France and Germany, both characterized by a strong nuclear industry and competence. Franco-German relations have considerably expanded in recent years, enabling the French and German electricians, manufacturers (EDF, Siemens, Framatome..), and safety authorities (DSIN, IPSN, BMU, GRS..) to adopt common positions and decisions on fundamental topics about technical aspects of safety. This kind of collaboration and alignment was obviously only possible because two conditions were fulfilled: the discussion concerned future reactors and not those already built for which safety rules and provisions are not easily modified; and a common industrial project existed and had consequently to comply with jointly defined safety objectives. These two conditions are still fulfilled, so it should be possible for the work between French and German safety authorities to continue successfully, even in the next more delicate stage, involving definition of common positions on more detailed technical provisions. Finally, it is unthinkable that this important work undertaken by France and Germany could be carried out without frequent consultation of the safety authorities of other nuclear countries, notably in Europe. (J.S.). 1 fig

High committee for transparency and information on nuclear safety: meeting of September 10, 2010

International Nuclear Information System (INIS)

2010-01-01

After the approval of its rules of procedure and the designation of the High committee office, the members of the committee discuss the following topics: the High committee communication rules, various issues regarding radioactive wastes (activity of the low level waste work group, recent decisions made by the government on the process of selection of a low level waste storage site, perspectives and modalities of a public hearing organised by the committee according to the mission defined in the waste bill). Then, they discuss the environmental monitoring issue: organisation and strategy of radioactivity control in France by the French nuclear safety authority (ASN) and by the French institute for radiation protection and nuclear safety (IRSN), assessment of the radio-ecological status at the vicinity of basic nuclear installations

EDF - The Inspector General's report on Nuclear Safety and Radiation Protection 2009

International Nuclear Information System (INIS)

2010-01-01

After a first chapter in which the Inspector General states his own vision of facts and results regarding nuclear safety and radiation protection for 2009, the relationship with the ASN (Nuclear safety authority), and also gives his own impression on the whole EDF nuclear system, the next chapters more particularly address the following topics: safety management, radiation protection of interveners, abilities and education for new challenges, the exploitation quality, the implementation of new regulatory arrangements, the extension of exploitation duration, the EPR project, the doctors as actors of safety management, service providing or subcontracting companies and fleet performance, prevention and struggle against fire, the activity of British Energy which is part of the EDF group, events which occurred within the EDF group (exposure of an intervener, incidents involving fuel components, biases in work monitoring, a fire on a turbo generator, an incident in Dungeness), lessons drawn from other industrial events (in a Russian hydroelectric station and in a refinery in Texas), and visits in China and in Japan

Report on transparency and nuclear safety 2015 - Fontenay-aux-Roses CEA centre

International Nuclear Information System (INIS)

2016-06-01

This document proposes, first, a presentation of the Fontenay-aux-Roses CEA centre, of its activities and installations. Then it gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. Next, it reports significant events related to safety and to radiation protection which occurred in 2015 and which have been declared to the French nuclear safety authority (ASN). It discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. Finally, it addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre. It indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and environment. Nature and quantities of warehoused wastes are specified. Remarks and recommendations of the Health, Safety and Working Conditions Committee (CHSCT) are given

The governance of nuclear safety - Quotes and questions. National debate on energy transition. Taking the risk of nuclear accident into account. Note to the CNDTE 'Governance' group

International Nuclear Information System (INIS)

Laponche, Bernard

2013-01-01

After an overview of electricity production from nuclear energy and of its risks, this report first describes the responsibilities in the field of nuclear safety: main responsibilities, role of the ASN and IRSN, responsibility of the government and role of the Parliament. In the second part, the author identifies and discusses examples of inadequacies in the definition of responsibilities in different respects: practice of responsibility of control of nuclear safety, ambiguity about the transfer of responsibilities in a situation of emergency, management of modifications in basic nuclear installations, extension of the operation duration of nuclear power plants, operation duration and decennial inspections, shutdown and definitive shutdown of an electronuclear reactor. In the final part, the author makes some propositions and recommendations regarding the responsibility of political authorities, independence, transparency and democracy

Expectations of the Swiss safety authorities

International Nuclear Information System (INIS)

Naegelin, R.

1994-01-01

On the one hand, nuclear energy can contribute significantly to our energy supply without much environmental consequences. On the other hand, there is a potential for large environmental consequences. The nuclear power plants are vastly different from conventional industrial activities where much has been learned through trial and error processes leading to slow improvements in their safety performance. Hence one cannot afford to learn from mistakes as an approach to safety improvement. It is more important to think ahead and precautions must be taken through proper design and operation before accidents can occur. The precondition for such an approach is what one now refers to as 'safety culture'. This requires a prerequisite frame of mind to 'desire' safety. In addition, the necessary technical 'ability' is also required, without which any culture cannot be realized. Culture is a human reaction to its environment so that it can live in harmony with the real or imaginary world. In the course of human history, different cultures, e.g. hunters and farmers, have evolved to adopt with the prevailing habitats. The term culture is also associated with a humane form of pre-industrial and industrial society. These cultures were, at least partially, the result of pressure to perform suitable actions. However, in the present modern times, things function quite well with less apparent pressure. Thereby positive values in the working culture become questionable. The traits that are endangered include thoroughness, carefulness and sense of duty in ones daily work habits. Also the removal of work from its central position in human life is involved, threatening care by pressure or time and costs. (author)

Cell Cycle-Dependent Recruitment of Polycomb Proteins to the ASNS Promoter Counteracts C/ebp-Mediated Transcriptional Activation in Bombyx mori

Science.gov (United States)

Li, Zhiqing; Cheng, Daojun; Mon, Hiroaki; Zhu, Li; Xu, Jian; Tatsuke, Tsuneyuki; Lee, Jae Man; Xia, Qingyou; Kusakabe, Takahiro

2013-01-01

Epigenetic modifiers and transcription factors contribute to developmentally programmed gene expression. Here, we establish a functional link between epigenetic regulation by Polycomb group (PcG) proteins and transcriptional regulation by C/ebp that orchestrates the correct expression of Bombyx mori asparagine synthetase (BmASNS), a gene involved in the biosynthesis of asparagine. We show that the cis-regulatory elements of YY1-binding motifs and the CpG island present on the BmASNS promoter are required for the recruitment of PcG proteins and the subsequent deposition of the epigenetic repression mark H3K27me3. RNAi-mediated knockdown of PcG genes leads to derepression of the BmASNS gene via the recruitment of activators, including BmC/ebp, to the promoter. Intriguingly, we find that PcG proteins and BmC/ebp can dynamically modulate the transcriptional output of the BmASNS target in a cell cycle-dependent manner. It will be essential to suppress BmASNS expression by PcG proteins at the G2/M phase of the cell cycle in the presence of BmC/ebp activator. Thus, our results provide a novel insight into the molecular mechanism underlying the recruitment and regulation of the PcG system at a discrete gene locus in Bombyx mori. PMID:23382816

Safety and Availability Checking for User Authorization Queries in RBAC

Directory of Open Access Journals (Sweden)

Jian-feng Lu

2012-09-01

Full Text Available This paper introduces the notion of safety and availability checking for user authorization query processing, and develop a recursive algorithm use the ideas from backtracking-based search techniques to search for the optimal solution. For the availability checking, we introduce the notion of max activatable set (MAS, and show formally how MAS can be determined in a hybrid role hierarchy. For the safety checking, we give a formal definition of dynamic separation-of-duty (DSoD policies, and show how to reduce the safety checking for DSoD to a SAT instance.

Controlling safety at all stage of parcel lifetime

International Nuclear Information System (INIS)

Sert, Gilles; Aguilar, Jacques; Clemente, Colette; Sauron, Claire; Labergri, Fabien; Jacob, Emmanuel; Sallit, George; Lourtie, Guy

2012-01-01

This chapter is made of several small articles entitled: - 'L'etude des risques lies aux situations extremes pouvant survenir lors du transport des substances radioactives' (The investigation of risks related to extreme situations which may occur during radioactive material transport); - 'Une necessaire diversification de l'expertise: le role du Groupe permanent d'experts pour les transports' (A required diversification of expertise: the role of the permanent group of experts for transports); - 'Vers un nouveau consensus sur les methodes et les parametres de reference a retenir lors des agrements des modeles de colis destines au transport' (Towards a new consensus on methods and reference parameters to be retained during agreements of models of parcels designed for transport); - 'Le controle de la fabrication des emballages par l'ASN' (Control of packaging manufacturing by the ASN); - 'Concevoir et realiser un emballage destine au transport de substances radioactives: l'exemple de la societe ROBATEL' (Designing and manufacturing a package for nuclear material transport: the example of the ROBATEL company); - 'Les transports internes dans les installations nucleaires de base secretes' (Internal transports within secrete base nuclear installations); - 'Les operations de transport interne sur les sites nucleaires' (Transport operations within nuclear sites); - 'Cooperation entre les Autorites competentes britanniques et francaises en matiere de regulation de la surete du transport des substances radioactives' (Cooperation between British and French Authorities in charge of radioactive material transport safety regulation); - 'Inspections et sanctions en Belgique' (Inspections and sanctions in Belgium). While evoking regulations and research studies, the first article comments the various risks (mechanical and thermal risks, and risks related to radiation leakage) associated with radioactive material transport. In an interview, the chairman of the permanent group of

Report on transparency and nuclear safety - 2015. Nuclear facilities exploited by CEA Marcoule

International Nuclear Information System (INIS)

Guiberteau, Philippe

2016-01-01

This report presents the different basic nuclear installations (INB) of the Marcoule CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and results, main events). It reports the significant events related to safety and radiation protection which occurred in 2015 and which were declared to the nuclear safety authority (ASN), and discusses how experience feedback has been used. It reports and comments the results of measurements of gaseous and liquid effluents, of their impact on the environment, and of surveys of the environment. It also presents the environmental management approach. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. Remarks and recommendations of the health, safety and work conditions committee (CHSCT) are given

Position adopted by the government about the safety options of the EPR reactor project; Prise de position du gouvernement concernant les options de surete du projet de reacteur EPR

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-10-01

On September 28, 2004, on behalf of the French ministers in charge of nuclear safety, the general director of nuclear safety and radiation protection addressed to the president of Electricite de France (EdF) a letter presenting the government's position about the safety options of the EPR (European Pressurized Reactor) project. On the basis of the examination carried out by the nuclear safety authority (ASN) and by the permanent group of reactor experts, the government has considered these options as satisfactory with respect to the safety improvement objectives. Therefore, the government requested EdF to comply with these technical rules for any future reactor development. This dossier includes: the letter of the government, the technical directives for the design and construction of the next generation of PWR-type reactors, the technical rules relative to the design of the main primary and secondary coolant circuits of PWR-type reactors, and the technical file about the safety of the EPR project reprinted from the 2003 report of nuclear safety and radiation protection authority. (J.S.)

French nuclear safety authorities: for a harmonization of nuclear safety at the European level

International Nuclear Information System (INIS)

Anon.

2004-01-01

The European Commission is working on 2 directives concerning nuclear energy: the first one is dedicated to nuclear safety and the second to the management of radioactive wastes and spent fuels. In the context of the widening of the European Union and of the inter-connection of the different electric power grids throughout Europe, the harmonization of the rules in the nuclear safety field is seen by manufacturers as a mean to achieve a fair competition between nuclear equipment supplying companies and by the French nuclear safety authorities (FNSA) as a mean to keep on improving nuclear safety and to be sure that competitiveness does not drive safety standards down. According to FNSA the 2 European directives could give a legal framework to the harmonization and should contain principles that reinforce the responsibility of each state. FNSA considers that the EPR (European pressurized water reactor) may be an efficient tool for the harmonization because of existing industrial cooperation programs between France and Germany and between France and Finland. (A.C.)

Nuclear fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management facilities safety. Lessons learned from events notified between 2005 and 2008

International Nuclear Information System (INIS)

2001-01-01

Maintaining high levels of safety in nuclear facilities requires constant vigilance by everyone involved, especially by plant operators who are first and foremost responsible for safety in their facilities. Safety can never be taken for granted; constant efforts must be made to improve it, by taking new knowledge and available operating feedback into account. In this respect, a substantial part of operating feedback is made up of lessons learned from analysing events, incidents or accidents occurring in France or in similar facilities abroad. To encourage the diffusion of operating feedback, IRSN has produced a report concerning events notified to the Nuclear Safety Authority (ASN) by operators of LUDD facilities between 2005 and 2008. The main objective is to make general lessons for safety in this type of facility available based on a cross-disciplinary analysis of notified events and noted evolution trends. IRSN has had tools for managing information concerning events occurring in France and abroad for many years. These tools are used to analyse the events in order to take into account the relevant lessons learned in the safety assessments performed on behalf of ASN and also to define study and research programmes to maintain its expertise and expand its knowledge. The report has 4 sections: - the first section (chapters 2 to 4) presents the LUDD facilities so that the facilities themselves, their diversity and the main associated risks can be better understood. It also includes a brief reminder of plant operator obligations in notifying events and describes the database used by the Institute to manage the data relating to the notified events; - the second section (chapter 5) summarises the main changes noted in the events notified to ASN during 2005 to 2008 and provides an overall assessment of the consequences of these events for the environment, the population and the workers; - the third section (chapter 6) describes significant events occurring in France

Safety of laboratories, plants, facilities being dismantled, waste processing, interim storage and disposal facilities. Lessons learned from events reported in 2009 and 2010

International Nuclear Information System (INIS)

2013-01-01

This report presents the cross-disciplinary analysis performed by IRSN relating to significant events reported to the French Nuclear Safety Authority (ASN) during 2009 - 2010 for LUDD-type facilities (laboratories, plants, facilities being dismantled, and waste processing, interim storage and disposal facilities). It constitutes a follow-up to DSU Report 215 published in December 2009, relating to events reported to ASN during 2005 to 2008. The main developments observed since the analysis presented in that report have been underlined here, in order to highlight improvements, opportunities for progress and the main areas requiring careful attention. The present report is a continuation of DSU Report 215. Without claiming to be exhaustive, it presents lessons from IRSN's cross-disciplinary analysis of events reported to ASN during 2009 and 2010 at LUDD facilities while highlighting major changes from the previous analysis in order to underline improvements, areas where progress has been made, and main points for monitoring. The report has four sections: - the first gives a brief introduction to the various kinds of LUDD facilities and highlights changes with DSU Report 215; - the second provides a summary of major trends involving events reported to ASN during 2007-2010 as well as overall results of consequences of events reported during 2009 and 2010 for workers, the general public and the environment; - the third section gives a cross-disciplinary analysis of significant events reported during 2009 and 2010, performed from two complementary angles (analysis of main types of events grouped by type of risk and analysis of generic causes). Main changes from the analysis given in DSU Report 215 are considered in detail; - the last section describes selected significant events that occurred in 2009 and 2010 in order to illustrate the cross-disciplinary analysis with concrete examples. IRSN will publish this type of report periodically in coming years in order to

Nuclear Safety and Radiation Protection in France in 2005; La surete nucleaire et la radioprotection en France en 2005. Dossier de presse

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-04-15

In 2005, the Asn pursued its significant investment in radiation protection and reaffirms its ambition to become as efficient in radiation protection as it is in nuclear safety as of 2009. 2005 was a year of great progress for the Asn as it consolidated its organisation and working methods, in accordance with the 2005-2007 strategic plan it set for itself. The Asn continued progress in the field of radiation protection has given rise to various new regulations to improve the legislative and regulatory framework in this area. The Asn plans to step up its efforts to ensure better monitoring of patient exposure to ionizing radiation and to provide better management of radon-related risks, particularly in housing. Fully aware that its newfound power in this area requires outside evaluation, the Asn has asked the International Atomic Energy Agency (IAEA) to organize an I.R.R.S. (Integrated Regulatory Review Service) assignment consisting of a peer-conducted audit. The IAEA has confirmed that this audit will take place in November 2006. (N.C.)

Safety culture as an element of contact and cooperation between utilities, research and safety authorities

International Nuclear Information System (INIS)

Hoegberg, L.

1994-01-01

The safety culture approach may simply be seen as a recognition of the close interdependence between safety and organisational processes: achievement of technical safety objectives will largely depend on the quality of the implementation processes in the organisations concerned. With a slight modification of the original INSAG formulation, SKI defines safety culture as 'a consciously formulated and implemented set of values in an organisation, which establishes that, as an overriding priority, safety issues receive the attention warranted by their significance'. In practice, a high level of safety culture means the systematic organisation and implementation of a number of activities aimed at creating a high quality defence in depth against both technical and human failures that may cause accidents. An enquiring and learning attitude is a key element of such a safety culture. For example, to prevent accidents, the organisation always needs to be reactive to incidents, by performing proper root cause analysis of both technical and organisational factors, and taking appropriate corrective actions. The long term organisational objective should be to be proactive and identify deficiencies in technology and organisation that may lead to serious incidents or, at worst, accidents and take corrective action even before actual occurrence of incidents of substantial safety significance. (author) 13 refs

Review of declarations received by the AFSSAPS and the ASN on the account of radio-vigilance (external radiotherapy). July 2007 - June 2008

International Nuclear Information System (INIS)

2009-09-01

After a presentation of the procedure of declaration of significant radiation protection events, of the ASN-SFRO event scale, and of the indication procedure related to material vigilance, this report proposes a review and an analysis of significant radioprotection and material vigilance events which have been declared between July 2007 and June 2008. The assessment of radiation protection events declared to the ASN is as well quantitative (distribution in time, geographical distribution, status of declaring centres, declaration delays, classification according to the ASN-SFRO scale) as qualitative (origin, event typology, stage of the treatment process at which the event occurred and has been detected, personnel having detected the event, communication about events). The analysis of material vigilance events addresses the evolution of their number, their distribution in terms of declarer type, of radiotherapy equipment, or of criticality level, and so on. A review of hybrid accidents is proposed (concerned equipment, declarer origin, consequences of the declarations, classification on the ASN-SFRO scale)

EURODIF company - Tricastin gaseous diffusion plant. Requests following the safety re-evaluation of the facility after 20 years of operation

International Nuclear Information System (INIS)

2000-01-01

This decision from the French authority of nuclear safety (ASN) concerns the safety reevaluation of the EURODIF plant ('Georges Besse plant') of the Tricastin site at Pierrelatte (France) which uses the gaseous diffusion process to separate the uranium isotopes. Since the last safety reevaluation in 1988, several points have been improved: reduction of the frequency and importance of uranium hexafluoride leaks (control of the pitting corrosion in the exchangers), no incident linked with exo-thermal reactions or explosions, a mastery of the exposure to ionizing radiations etc.. On the other hand, several points need improvement: the prevention of criticality risks, the earthquake resistance of some structures, and the integration of some accident scenarios (aircraft crash, UF 6 leak) in the emergency plan to avoid the fast release of toxic materials in the environment. These points are detailed in the document. (J.S.)

High committee for nuclear safety transparency and information. September 23, 2008 meeting; Haut comite pour la transparence et l'information sur la securite nucleaire. Reunion du 23 septembre 2008

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-09-15

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 points: 1 - the terms of the High Committee operation and the internal rules for the meetings; 2 - the plutonium imports and transportation between Great Britain and France (contracts status, ship safety report, plutonium grade, return of plutonium-derived wastes): hearing of Areva, of the general direction of infrastructures, transports and sea (DGITM), of Greenpeace organisation, debate; 3 - the follow-up of the July 7, 2008 incident at the Socatri facility (Tricastin site (France)) where the overflow of a storage tank led to the spillage of a uraniferous solution on the ground: hearing of Areva (remedial action, re-start up of the facility, environmental monitoring, communication and transparency), hearing of the nuclear safety authority (ASN), of the institute of radiation protection and nuclear safety (IRSN), of the local commission of information (CIGEET), of the hygiene, safety and labour conditions committee (CHSCT) of Socatri company, of the direction of civil safety (DSC), debate about the information dissemination around this incident; 4 - Opinion of the High Committee about the plutonium transportation between Great Britain and France, and about the Socatri incident; 5 - referral to the High Committee of the radioecological follow up of all nuclear sites and of the quality of the information given to the public: ASN's reports about the radioecological follow-up of surface and ground waters and of the ancient radioactive waste storage sites, ASND's answer (Nuclear safety authority of defense), IRSN

DARHT: INTEGRATION OF AUTHORIZATION BASIS REQUIREMENTS AND WORKER SAFETY

International Nuclear Information System (INIS)

MC CLURE, D. A.; NELSON, C. A.; BOUDRIE, R. L.

2001-01-01

This document describes the results of consensus agreements reached by the DARHT Safety Planning Team during the development of the update of the DARHT Safety Analysis Document (SAD). The SAD is one of the Authorization Basis (AB) Documents required by the Department prior to granting approval to operate the DARHT Facility. The DARHT Safety Planning Team is lead by Mr. Joel A. Baca of the Department of Energy Albuquerque Operations Office (DOE/AL). Team membership is drawn from the Department of Energy Albuquerque Operations Office, the Department of Energy Los Alamos Area Office (DOE/LAAO), and several divisions of the Los Alamos National Laboratory. Revision 1 of the DARHT SAD had been written as part of the process for gaining approval to operate the Phase 1 (First Axis) Accelerator. Early in the planning stage for the required update of the SAD for the approval to operate both Phase 1 and Phase 2 (First Axis and Second Axis) DARHT Accelerator, it was discovered that a conflict existed between the Laboratory approach to describing the management of facility and worker safety

IRSN-ANCCLI partnership. Work session on Complementary safety assessments - November 2011

International Nuclear Information System (INIS)

Lachaume, Jean-Luc; Lheureux, Yves; Sene, Monique; Sene, Raymond; Jorel, Martial; Lavarenne, Caroline; Rousseau, Jean-Marie; Rebour, Vincent; Baumont, David; Dupuy, Patricia

2011-11-01

After an overview by the ASN of complementary safety assessments and an assessment of 'post-Fukushima' inspections of basic nuclear installations, the contributions (Power Point presentations) of this seminar proposed: the opinion of the Gravelines CLI (local information commission) on the Gravelines complementary safety assessment report, an analysis and discussion by the GSIEN on reports of complementary assessment of safety of nuclear installations with respect to the Fukushima accident, an analysis by the IRSN of complementary safety assessments performed by operators, the IRSN approach to analyze complementary safety assessments, reports on installation conditions, external flooding and seismic hazard, 'meltdown prevention' aspects in the management of accidental situations in EDF reactors

TSO Role in Supporting the Regulatory Authority in View of Safety Culture

International Nuclear Information System (INIS)

Khamaza, A.; Vasilishin, A.

2016-01-01

Human and organizational factors are always of paramount importance at nuclear and radiation safety as well as in the safety regulation provision. Major NPP accidents occurred merely reaffirm this fact. The role of an authority that regulates nuclear safety increases each time in the aftermath of accidents perceived as a shock together with the importance of scientific and technical support. SEC NRS was established in 1987, the next year after the Chernobyl NPP accident aiming to strengthen supervision over works carried out at the nuclear industry enterprises. Currently SEC NRS provides comprehensive scientific and technical support to Rostechnadzor including safety review and regulatory legal documents development to regulate safety along with safety culture.

Quality and safety of nuclear plants: the role of the administrative authorities

International Nuclear Information System (INIS)

Queniart, D.

1977-10-01

After specifying the notions of 'safety' and 'quality', the terms and conditions governing the intervention of the public authorities in the matter of safety of nuclear plants are described: individual permits, the establishing and application of technical rules of a general character, surveillance of the plants. The criteria and regulations guiding the evaluation of safety and quality and, in conclusion, insisting on the necessity for permanent discussions among the various organizations concerned are presented

Lack of association between urotensin-II (UTS2 gene polymorphisms (Thr21Met and Ser89Asn and migraine

Directory of Open Access Journals (Sweden)

Betül Ozan

2017-08-01

Full Text Available Migraine is a common neurovascular brain disorder with heterogeneous clinical presentation, including recurrent headache attacks. The pathophysiology of migraine is complex, and a number of genomic regions have been associated with the development of migraine. In this study, we analyzed the allele and genotype frequencies of the urotensin-II gene (UTS2 polymorphisms, Thr21Met and Ser89Asn, among Turkish patients with migraine. A total of 146 patients with migraine (14 with aura [MA group] and 132 without aura [MO group] were genotyped for Thr21Met and Ser89Asn polymorphisms and compared with 154 age- and sex-matched healthy controls. The UTS2 gene polymorphisms were analyzed by polymerase chain reaction-restriction fragment length polymorphism (PCR-RFLP. No significant differences were observed in allele and genotype frequencies for Thr21Met and Ser89Asn polymorphisms between the patients with migraine and control group. Similarly, we did not observe significant differences in allele and genotype frequencies between MA and MO and control group. Moreover, the haplotype analysis showed no association between UTS2 gene haplotypes (MN, MS, TN, and TS and migraine. In summary, Thr21Met and Ser89Asn polymorphisms of the UTS2 gene are not risk factors for migraine in our sample of Turkish migraine patients.

Scanning Tunneling Microscopy study and unusual transport properties of the topological semimetal a-Sn

Science.gov (United States)

Ruan, Jiawei

Weyl semimetals are new states of quantum matter with topological Weyl nodes near Fermi level in the bulk and Fermi arcs at the surface, which are paid a lot attention in recently years. Here#¬we report another topological semimetal a-Sn., which is double Weyl semimetal in the magnetic field and Dirac semimetal in an appropriate in-plane strain. By combing Landau level spectroscopy and quasiparticle interference, we obtain the linear dispersion near the Dirac point within strain while quadratic band dispersion near Γpoint without strain. We also observe the negative longitudinal magnetoresistance (LMR) in both two system, which is caused by chiral anomaly. However ,the LMR profiles of strained a-Sn have a little rise and then descend while the unstrained one drop directly, which is due to the different type of Weyl semimetal and further confirm our prediction.

Authorization Basis Safety Classification of Transfer Bay Bridge Crane at the 105-K Basins

International Nuclear Information System (INIS)

CHAFFEE, G.A.

2000-01-01

This supporting document provides the bases for the safety classification for the K Basin transfer bay bridge crane and the bases for the Structures, Systems, and Components (SSC) safety classification. A table is presented that delineates the safety significant components. This safety classification is based on a review of the Authorization Basis (AB). This Authorization Basis review was performed regarding AB and design baseline issues. The primary issues are: (1) What is the AB for the safety classification of the transfer bay bridge crane? (2) What does the SSC safety classification ''Safety Significant'' or ''Safety Significant for Design Only'' mean for design requirements and quality requirements for procurement, installation and maintenance (including replacement of parts) activities for the crane during its expected life time? The AB information on the crane was identified based on review of Department of Energy--Richland Office (RL) and Spent Nuclear Fuel (SNF) Project correspondence, K Basin Safety Analysis Report (SAR) and RL Safety Evaluation Reports (SERs) of SNF Project SAR submittals. The relevant correspondence, actions and activities taken and substantive directions or conclusions of these documents are provided in Appendix A

The French nuclear safety authority's experience with radioactive transport inspection

International Nuclear Information System (INIS)

Jacob, E.; Aguilar, J.

2004-01-01

About 300,000 radioactive material packages are transported annually in France. Most consist of radioisotopes for medical, pharmaceutical or industrial use. On the other hand, the nuclear industry deals with the transport of fuel cycle materials (uranium, fuel assemblies, etc.) and waste from power plants, reprocessing plants and research centers. France is also a transit country for shipments such as spent fuel packages from Switzerland or Germany, which are bound for Sellafield in Great Britain. The French nuclear safety authority (DGSNR: Directorate General for Nuclear Safety and Radioprotection) has been responsible since 1997 for the safety of radioactive material transport. This paper presents DGNSR's experience with transport inspection: a feedback of key points based on 300 inspections achieved during the past five years is given

The role of a second-shell residue in modifying substrate and inhibitor interactions in the SHV beta-lactamase: a study of ambler position Asn276.

Science.gov (United States)

Drawz, Sarah M; Bethel, Christopher R; Hujer, Kristine M; Hurless, Kelly N; Distler, Anne M; Caselli, Emilia; Prati, Fabio; Bonomo, Robert A

2009-06-02

Inhibitor-resistant class A beta-lactamases of the TEM and SHV families that arise by single amino acid substitutions are a significant threat to the efficacy of beta-lactam/beta-lactamase inhibitor combinations. To better understand the basis of the inhibitor-resistant phenotype in SHV, we performed mutagenesis to examine the role of a second-shell residue, Asn276. Of the 19 variants expressed in Escherichia coli, only the Asn276Asp enzyme demonstrated reduced susceptibility to ampicillin/clavulanate (MIC increased from 50/2 --> 50/8 microg/mL) while maintaining high-level resistance to ampicillin (MIC = 8192 microg/mL). Steady-state kinetic analyses of Asn276Asp revealed slightly diminished k(cat)/K(m) for all substrates tested. In contrast, we observed a 5-fold increase in K(i) for clavulanate (7.4 +/- 0.9 microM for Asn276Asp vs 1.4 +/- 0.2 microM for SHV-1) and a 40% reduction in k(inact)/K(I) (0.013 +/- 0.002 microM(-1 )s(-1) for Asn276Asp vs 0.021 +/- 0.004 microM(-1) s(-1) for SHV-1). Timed electrospray ionization mass spectrometry of clavulanate-inhibited SHV-1 and SHV Asn276Asp showed nearly identical mass adducts, arguing for a similar pathway of inactivation. Molecular modeling shows that novel electrostatic interactions are formed between Arg244Neta2 and both 276AspOdelta1 and Odelta2; these new forces restrict the spatial position of Arg244, a residue important in the recognition of the C(3)/C(4) carboxylate of beta-lactam substrates and inhibitors. Testing the functional consequences of this interaction, we noted considerable free energy costs (+DeltaDeltaG) for substrates and inhibitors. A rigid carbapenem (meropenem) was most affected by the Asn276Asp substitution (46-fold increase in K(i) vs SHV-1). We conclude that residue 276 is an important second-shell residue in class A beta-lactamase-mediated resistance to substrates and inhibitors, and only Asn is able to precisely modulate the conformational flexibility of Arg244 required for successful

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.)

Intervention of French safety authorities during the design and construction phases of the Creys-Malville plant

International Nuclear Information System (INIS)

Orzoni, G.

1985-01-01

The intervention of French safety authorities during the design and construction phases of the Creys-Malville plant has been made by the different means of technical regulation, of several successive authorizations bound to different steps, and of numerous surveillance visits. Some safety-related problems have been met. Some of them are detailed, relating to the basis accident for containment design, decay heat removal, polar crane of reactor building, seismic resistance of main vessel internals, core cover plug, design and fabrication of steam generators. The main problems met during the design reviews and the construction phase of the plant have been solved in time; the safety level reached is provisionally judged acceptable by the French safety authorities

IRSN-ANCCLI partnership. IRSN-ANCCLI seminar - Safety challenges after the Fukushima accident - January 2012

International Nuclear Information System (INIS)

Compagnat, Gilles; Revol, H.; Rousselet, Yannick; Sene, Monique; Lheureux, Yves; Laurent, Michel; Lavarenne, Caroline; Jorel, M.; Houdre, Thomas; Lachaume, Jean-Luc

2012-01-01

After a synthesis, this document contains the contributions (Power Point presentations) of a seminar which addressed the following topics: remarks by the HCTISN on the process of complementary safety assessments, analysis and discussion by the GSIEN on reports of complementary assessment of safety of nuclear installations with respect to the Fukushima accident, opinion of the Gravelines local information commission (CLI) on the complementary safety assessment report for the Gravelines nuclear power plant, stage point of the Manche INTERCLI work-group on the safety of nuclear installations after Fukushima, presentation by the IRSN of the complementary safety assessments, and opinion of the ASN on complementary safety assessments (ECS) of priority nuclear installations

Genetic polymorphisms of xeroderma pigmentosum group D gene Asp312Asn and Lys751Gln and susceptibility to prostate cancer: a systematic review and meta-analysis.

Science.gov (United States)

Ma, Qingtong; Qi, Can; Tie, Chong; Guo, Zhanjun

2013-11-10

Many studies have reported the role of xeroderma pigmentosum group D (XPD) with prostate cancer risk, but the results remained controversial. To derive a more precise estimation of the relationship, a meta-analysis was performed. Odds ratios (ORs) with 95% confidence intervals (CIs) were estimated to assess the association between XPD Asp312Asn and Lys751Gln polymorphisms and prostate cancer risk. A total of 8 studies including 2620 cases and 3225 controls described Asp312Asn genotypes, among which 10 articles involving 3230 cases and 3582 controls described Lys751Gln genotypes and were also involved in this meta-analysis. When all the eligible studies were pooled into this meta-analysis, a significant association between prostate cancer risk and XPD Asp312Asn polymorphism was found. For Asp312Asn polymorphism, in the stratified analysis by ethnicity and source of controls, prostate cancer risk was observed in co-dominant, dominant and recessive models, while no evidence of any associations of XPD Lys751Gln polymorphism with prostate cancer was found in the overall or subgroup analyses. Our meta-analysis supports that the XPD Asp312Asn polymorphism contributed to the risk of prostate cancer from currently available evidence. However, a study with a larger sample size is needed to further evaluate gene-environment interaction on XPD Asp312Asn and Lys751Gln polymorphisms and prostate cancer risk. © 2013.

Safety guidebook relative to the disposal of radioactive wastes in deep geologic formation

International Nuclear Information System (INIS)

2008-01-01

The French nuclear safety authority (ASN) initiated in 2003 a revision process of the objectives to be considered during the research and work steps of the implementation of a radioactive waste storage facility in deep geologic formations. The purpose of this document is to define the safety objectives that have to be retained at each step of this implementation, from the site characterization to the closure of the facility. This update takes into account the works carried out by the ANDRA (French national agency of radioactive wastes) in the framework of the law from December 30, 1991, and the advices of the permanent experts group about these works. It takes also into consideration the international research works in this domain and the choices defined in the program law no 2006-739 from June 28, 2006 relative to the sustainable management of radioactive materials and wastes. The main modifications concern: the notion of reversibility, the definition of the safety functions of disposal components, the safety goals and the design principles assigned to waste packages, the control of nuclear materials and the monitoring objectives of the facility. The documents treats of the following points: 1 - the objectives of public health and environment protection; 2 - the safety principles and the safety-related design bases of the facility; and 3 - the method used for demonstrating the disposal safety. (J.S.)

Developments related to the National Nuclear Safety Authority of Romania

International Nuclear Information System (INIS)

Baciu, Florin

1998-01-01

The contribution presents the status of the National Commission for Nuclear Activity Control (CNCAN) as indicated by the provisions of a Romanian Government Decision of May 1998. As specified in the art.3 the main tasks of the Commission are the following: to issue authorization and exercise permits of activities in nuclear field; to supervise the applications of the provisions stipulated by the law concerning development in safety conditions of nuclear activities; to develop instructions as well as nuclear safety regulations to ensure the quality assurance and functioning in safety conditions of the nuclear facilities and plants, the protection against nuclear radiation of the professionally exposed personnel, of the population, of the environment and of the material goods, the physical protection, the records, preservation and transport of radioactive material and of fissionable materials as well as the management of radioactive waste; organizes expert and is responsible for the state control concerning the integrated application of the law provisions in the field of quality constructions in which nuclear installations of national interest are located, during all the phases and for all the components of the quality system in this field; issues specialty and information documentation specific to its own activity, provides the information of the public through official publication, official statements to the press and other specific form of information; carries out any other tasks provided by law in the field of regulations and control of nuclear activity. Author presents also the CNCAN staff number evolution, the new structure, the staff distribution at headquarters, local agencies and national radiation monitoring network. Finally, the author discusses the legal provisions related to management manual procedures

Solid state chemistry of new polysulphides in A/Sn/S (A = Na, K, Rb ...

Indian Academy of Sciences (India)

Administrator

Solid state chemistry of new polysulphides in A/Sn/S (A = Na, K,. Rb) systems. M SUSEELA DEVI and K VIDYASAGAR. Department of Chemistry, Indian Institute of Technology Madras,. Chennai 600 036, India. Ternary polychalcogenides containing chalocogen–chalcogen bonds are metastable compounds that have been ...

Mining and mining authorities in Saarland 2016. Mining economy, mining technology, occupational safety, environmental protection, statistics, mining authority activities. Annual report

International Nuclear Information System (INIS)

2016-01-01

The annual report of the Saarland Upper Mining Authority provides an insight into the activities of mining authorities. Especially, the development of the black coal mining, safety and technology of mining as well as the correlation between mining and environment are stressed.

THE NATIONAL AUTHORITY FOR ANIMAL HEALTH AND FOOD SAFETY, THE MAIN BODY INVOLVED IN FOOD SAFETY IN ROMANIA

Directory of Open Access Journals (Sweden)

PETRUTA-ELENA ISPAS

2012-05-01

Full Text Available This paper is intended to present the role, functions and responsibilities of the National Authority for Animal Health and Food Safety as the main body involved in food safety in Romania. It will be also exposed the Regulation 178/2002 of the European Parliament and the Council, the general food ”law” in Europe, and Law 150/2004, which transposed into Romanian legislation Regulation 178/2002.

Decree no. 2005-78 from January 26, 2005, authorizing the Atomic Energy Commission to proceed to the definitive shutdown and dismantling operations of the nuclear facility no.20, named Siloe reactor, in the Grenoble city territory (Isere); Decret no. 2005-78 du 26 janvier 2005, autorisant le Commissariat a l'energie atomique a proceder aux operations de mise a l'arret definitif et de demantelement de l'installation nucleaire de base no.20 denommee reacteur Siloe sur le territoire de la commune de Grenoble (Isere)

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-02-15

On March 19, 2003, the French atomic energy commission (CEA) addressed an authorization demand for the definitive shutdown and dismantling of the Siloe reactor. After a technical and administrative instruction of this demand by the French nuclear safety authority (ASN), a project of decree has been presented on July 6, 2004 at the permanent section of the inter-ministry commission of basic nuclear facilities. The commission gave its favourable judgment which is the object of this decree. (J.S.)

NMR structure determination of a synthetic analogue of bacillomycin Lc reveals the strategic role of L-Asn1 in the natural iturinic antibiotics

Science.gov (United States)

Volpon, Laurent; Tsan, Pascale; Majer, Zsuzsa; Vass, Elemer; Hollósi, Miklós; Noguéra, Valérie; Lancelin, Jean-Marc; Besson, Françoise

2007-08-01

Iturins are a group of antifungal produced by Bacillus subtilis. All are cyclic lipopeptides with seven α-amino acids of configuration LDDLLDL and one β-amino fatty acid. The bacillomycin L is a member of this family and its NMR structure was previously resolved using the sequence Asp-Tyr-Asn-Ser-Gln-Ser-Thr. In this work, we carefully examined the NMR spectra of this compound and detected an error in the sequence. In fact, Asp1 and Gln5 need to be changed into Asn1 and Glu5, which therefore makes it identical to bacillomycin Lc. As a consequence, it now appears that all iturinic peptides with antibiotic activity share the common β-amino fatty acid 8- L-Asn1- D-Tyr2- D-Asn3 sequence. To better understand the conformational influence of the acidic residue L-Asp1, present, for example in the inactive iturin C, the NMR structure of the synthetic analogue SCP [cyclo ( L-Asp1- D-Tyr2- D-Asn3- L-Ser4- L-Gln5- D-Ser6- L-Thr7-β-Ala8)] was determined and compared with bacillomycin Lc recalculated with the corrected sequence. In both cases, the conformers obtained were separated into two families of similar energy which essentially differ in the number and type of turns. A detailed analysis of both cyclopeptide structures is presented here. In addition, CD and FTIR spectra were performed and confirmed the conformational differences observed by NMR between both cyclopeptides.

A.F.S.S.A.P.S. contribution to the enhancement of the safety and the quality of radiotherapy procedures

International Nuclear Information System (INIS)

Berthier, G.; Marliac, N.

2009-01-01

AFSSAPS, the French Health Products Safety Agency, has been confronted, in 2006 and 2007, as other health institutions, with two major accidents which have shaken French radiotherapy. Those accidents have highlighted difficulties met by this profession in a strong technologic innovation context of the used medical devices and deficit of medical physicists. This situation has led to an unprecedented mobilization of all involved authorities and health care professionals, within the framework of a 'Road-map' established by the minister of health. AFSSAPS has thus strongly committed itself in the security and quality aspects of medical devices used in the execution of radiotherapy acts. Every step of the concerned medical devices life cycle profited from this commitment. This work has also enabled the reinforcement of the collaboration and the synergy between AFSSAPS and ASN. (authors)

Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA)

DEFF Research Database (Denmark)

Leuschner, R. G. K.; Robinson, T. P.; Hugas, M.

2010-01-01

Qualified Presumption of Safety (QPS) is a generic risk assessment approach applied by the European Food Safety Authority (EFSA) to notified biological agents aiming at simplifying risk assessments across different scientific Panels and Units. The aim of this review is to outline the implementation...... and value of the QPS assessment for EFSA and to explain its principles such as the unambiguous identity of a taxonomic unit, the body of knowledge including potential safety concerns and how these considerations lead to a list of biological agents recommended for QPS which EFSA keeps updated through...

What are the external consulting needs?

International Nuclear Information System (INIS)

Limousin, S.; Crombez, S.; Monin, L.

2010-01-01

Obtaining and maintaining a high level of competence for designing, manufacturing and operating nuclear pressure equipment is the responsibility of manufacturers and licensees. However to make comprehensive and sound decisions a regulator needs independent expertise. ASN has just created a new 'standing committee' on nuclear pressure equipment. Added to that, ASN relies on his historical technical support IRSN, in particular on safety related topics or during reactor outages, when decisions need to be made in a short time. In the field of nuclear pressure equipment, it is often useful to compare practices with those in non nuclear industry. In such cases, ASN can contract with other technical support. For the conformity assessment of new equipment, French regulations states that ASN can delegate to accredited third party bodies part or the entire conformity assessment. (authors)

Barriers to Safety Event Reporting in an Academic Radiology Department: Authority Gradients and Other Human Factors.

Science.gov (United States)

Siewert, Bettina; Swedeen, Suzanne; Brook, Olga R; Eisenberg, Ronald L; Hochman, Mary

2018-05-15

Purpose To investigate barriers to reporting safety concerns in an academic radiology department and to evaluate the role of human factors, including authority gradients, as potential barriers to safety concern reporting. Materials and Methods In this institutional review board-approved, HIPAA-compliant retrospective study, an online questionnaire link was emailed four times to all radiology department staff members (n = 648) at a tertiary care institution. Survey questions included frequency of speaking up about safety concerns, perceived barriers to speaking up, and the annual number of safety concerns that respondents were unsuccessful in reporting. Respondents' sex, role in the department, and length of employment were recorded. Statistical analysis was performed with the Fisher exact test. Results The survey was completed by 363 of the 648 employees (56%). Of those 363 employees, 182 (50%) reported always speaking up about safety concerns, 134 (37%) reported speaking up most of the time, 36 (10%) reported speaking up sometimes, seven (2%) reported rarely speaking up, and four (1%) reported never speaking up. Thus, 50% of employees spoke up about safety concerns less than 100% of the time. The most frequently reported barriers to speaking up included high reporting threshold (69%), reluctance to challenge someone in authority (67%), fear of disrespect (53%), and lack of listening (52%). Conclusion Of employees in a large academic radiology department, 50% do not attain 100% reporting of safety events. The most common human barriers to speaking up are high reporting threshold, reluctance to challenge authority, fear of disrespect, and lack of listening, which suggests that existing authority gradients interfere with full reporting of safety concerns. © RSNA, 2018.

New Promotion Patterns in Italian Universities: Less Seniority and More Productivity? Data from ASN

Science.gov (United States)

Marini, Giulio

2017-01-01

The new habilitation (ASN), established in Italy in 2010 and launched in 2012, was introduced to filter eligible candidates in the competition of associate and full professorships. Its purpose is to cut off poor candidates on the basis of individual scientific productivity before they might be hired in competitions where patronage may favor them.…

The big interview - Fukushima: 'Collectively, the international nuclear security system has failed'; Grand entretien - Fukushima 'Collectivement, le systeme de surete nucleaire international a failli...'

Energy Technology Data Exchange (ETDEWEB)

Niel, J.C. [Autorite de surete nucleaire - ASN, 6, place du Colonel Bourgoin, 75012 Paris (France); ASN, 10, Route du Panorama 92266 Fontenay-aux-Roses cedex (France); Seillan, Hubert

2011-11-15

In an interview the ASN (the French Nuclear Safety Authority) manager summarizes his professional career, describes the ASN missions and outlines the independence of this institution as it is defined and practically exists, gives his opinion and analysis on the Fukushima accident, evokes the meaning of stress tests, discusses the information obtained through inspections of the French nuclear power plants, evokes the desirable evolutions at the international level, explains why terrorism has not been integrated in the stress test procedure, comments the implications of the European level on French safety studies. Some actors are briefly presented: the CEA, AREVA, EDF, the World association of nuclear operators (WANO)

The big interview - Fukushima: 'Collectively, the international nuclear security system has failed'

International Nuclear Information System (INIS)

Niel, J.C.; Seillan, Hubert

2011-01-01

In an interview the ASN (the French Nuclear Safety Authority) manager summarizes his professional career, describes the ASN missions and outlines the independence of this institution as it is defined and practically exists, gives his opinion and analysis on the Fukushima accident, evokes the meaning of stress tests, discusses the information obtained through inspections of the French nuclear power plants, evokes the desirable evolutions at the international level, explains why terrorism has not been integrated in the stress test procedure, comments the implications of the European level on French safety studies. Some actors are briefly presented: the CEA, AREVA, EDF, the World association of nuclear operators (WANO)

Colloquium / Preparation for nuclear post-accident. Citizens and local authorities involvement in major risks governance - proceedings

International Nuclear Information System (INIS)

Pascal, Michel; Villers, Anita; Sene, Monique; Godin, Francois; Quilichini, Jean-Michel; Rollinger, Francois; Delalonde, Jean-Claude; Mehl-Auget, Isabelle; Autret, Jean-Claude; Heriard Dubreuil, Gilles; Petitfrere, Michael; Lochard, Jacques; Demet, Michel; Boucherie, Jean-Claude; Calafat, Alexis; Sommade, Christian; Villain, Alain; Ragazzo, Romeo; Rengot, Marielle; Sename, Jean; Thellier, Yvette; Tremelet, David; Olszewski, Richard; Fournier, Nicolas

2009-12-01

During 40 years, France has chosen nuclear energy as main energy source for power generation. Today, nuclear energy covers 80% of the French electricity needs. For this reason, in France, each inhabitant lives at less than 200 km of a nuclear power plant. The September 11, 2001 terror attack has led to reconsider the nuclear risk in terms of security. In 2005, the French nuclear safety authority (ASN) has been entrusted with the preparation of a nuclear post-accident management study. This study has been mainly based on the experience feedback of the Chernobyl accident and on the dialogue with different actors of the French territory: the local authorities, the habitants, the associations and the health, environment and education actors. This colloquium represents the opening act of the joint elaboration of the management of a potential nuclear accident at the region scale. The colloquium was organized around 5 round tables: 1 - Did the nuclear safety transparency law change the situation?; 2 - Examples of pluralistic dialogues: the long-term management of a nuclear accident; 3 - How to encourage the necessary skills development of citizens? 4 - Regional development strategies in terms of nuclear risks management (incidents, effluents, wastes, transports..); 5 - New territory liabilities and citizens' legitimate aspiration in terms of health/environment: building something together. This document is the proceedings of this colloquium. It reports the exchanges between the participants

Decree no. 2005-79 from January 26, 2005, authorizing the Atomic Energy Commission to proceed to the definitive shutdown and dismantling operations of the nuclear facility no.21, named Siloette research reactor, in the Grenoble city territory (Isere); Decret no. 2005-79 du 26 janvier 2005, autorisant le Commissariat a l'Energie Atomique a proceder aux operations de mise a l'arret definitif et de demantelement de l'installation nucleaire de base no.21 denommee reacteur de recherche Siloette sur le territoire de la commune de Grenoble (Isere)

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-02-15

On May 26, 2003, the French atomic energy commission (CEA) addressed an authorization demand for the definitive shutdown and dismantling of the Siloette research reactor. After a technical and administrative instruction of this demand by the French nuclear safety authority (ASN), a project of decree has been presented on July 6, 2004 at the permanent section of the inter-ministry commission of basic nuclear facilities. The commission gave its favourable judgment which is the object of this decree. (J.S.)

The quality and safety of nuclear plants: the part played by the administrative authorities

International Nuclear Information System (INIS)

Queniart, Daniel

1976-01-01

After specifying the notions of 'safety' and 'quality', the terms and conditions governing the intervention of the public authorities in the matter of safety of nuclear plants are described: individual permits, the establishing and application of technical rules of a general character, surveillance of the plants. The criteria and regulations guiding the evaluation of safety and quality and, in conclusion, insisting on the necessity for permanent discussions among the various organizations concerned are presented [fr

ASN: regional day of information and exchange on transport of radioactive materials - 4 February 2010

International Nuclear Information System (INIS)

2010-01-01

This document gathers Power Point presentations made during a meeting on the transport of radioactive materials. The contributions addressed the following topics: results of a survey based on questionnaires sent to actors of this sector, regulatory framework and radioprotection plan, case of parcels not submitted to the authority concerned, declaration of transport interesting or significant events, ASN inspections, the transport of radioactive products by the IBt Bebig company in France, the activities of the Institut de Soudure Industrie (industry welding institute), the activities of the ISO Life company specialized in health product transportation, the activities of the Securidis company (a consulting company for activities related to hazardous materials transportation, and notably radioactive materials), the activities a the ACE Environnement company (specialized in building diagnosis), the point of view of an academic research unit on radioactive material transportation, the experience of the hospital sector in radioactive source transportation, the experience of the Advanced Accelerator Applications company in radioactive material transportation, and a discussion on regulation application

Safety and environmental protection - realization efforts regarding the authorization of power engineering plants

International Nuclear Information System (INIS)

Dreyhaupt, F.J.

1982-01-01

As to power plants the author calls special attention to three statements concerning questions on safety and environmental protection which play a decisive part in authorizing conventional and nuclear facilities. After investigating the most important legal fundamental principles for the authorization of power engineering plants, the Atomic Act and the Federal Immission Protection Act, the author discusses the problems that arise with the application of the authorization procedures. The reasons which can be made responsible for the long running periods of the authorization procedures and therewith of the realization of the site installation work are given. Finally, the author describes and judges the outlines of regulations for large scale furnaces and for the TA-air supplementary clause. (orig.) [de

Bioremediation of acidic oily sludge-contaminated soil by the novel yeast strain Candida digboiensis TERI ASN6.

Science.gov (United States)

Sood, Nitu; Patle, Sonali; Lal, Banwari

2010-03-01

Primitive wax refining techniques had resulted in almost 50,000 tonnes of acidic oily sludge (pH 1-3) being accumulated inside the Digboi refinery premises in Assam state, northeast India. A novel yeast species Candida digboiensis TERI ASN6 was obtained that could degrade the acidic petroleum hydrocarbons at pH 3 under laboratory conditions. The aim of this study was to evaluate the degradation potential of this strain under laboratory and field conditions. The ability of TERI ASN6 to degrade the hydrocarbons found in the acidic oily sludge was established by gravimetry and gas chromatography-mass spectroscopy. Following this, a feasibility study was done, on site, to study various treatments for the remediation of the acidic sludge. Among the treatments, the application of C. digboiensis TERI ASN6 with nutrients showed the highest degradation of the acidic oily sludge. This treatment was then selected for the full-scale bioremediation study conducted on site, inside the refinery premises. The novel yeast strain TERI ASN6 could degrade 40 mg of eicosane in 50 ml of minimal salts medium in 10 days and 72% of heneicosane in 192 h at pH 3. The degradation of alkanes yielded monocarboxylic acid intermediates while the polycyclic aromatic hydrocarbon pyrene found in the acidic oily sludge yielded the oxygenated intermediate pyrenol. In the feasibility study, the application of TERI ASN6 with nutrients showed a reduction of solvent extractable total petroleum hydrocarbon (TPH) from 160 to 28.81 g kg(-1) soil as compared to a TPH reduction from 183.85 to 151.10 g kg(-1) soil in the untreated control in 135 days. The full-scale bioremediation study in a 3,280-m(2) area in the refinery showed a reduction of TPH from 184.06 to 7.96 g kg(-1) soil in 175 days. Degradation of petroleum hydrocarbons by microbes is a well-known phenomenon, but most microbes are unable to withstand the low pH conditions found in Digboi refinery. The strain C. digboiensis could efficiently degrade

Report from the nuclear safety authority about the preparation of nuclear facilities to the year 2000 transition

International Nuclear Information System (INIS)

Lacoste, A.C.

1999-01-01

The French nuclear safety authority with the technical help of the Institute of Nuclear Protection and Safety (IPSN) started in 1998 an evaluation and control work of the measures taken by the different nuclear facility operators in anticipation of the year 2000 transition. This report makes a status of the state of preparation of nuclear facilities prior to the transition: 1 - The nuclear safety and the year 2000 transition (defense-in-depth approach, preventive actions); 2 - The action of the safety authority (demands addressed to the operators of nuclear facilities, technical evaluation and control of the methodology adopted by each operator, preparation of the safety authority to the transition, follow up of the international actions); 3 - Status of the preparation of the different operators: Electricite de France (EdF) (corrective actions, inventory and investigation of computer systems, results, corrections, preventive actions, defensive actions, synthesis), research centres, storage sites and shutdown reactors, waste storage centres of the ANDRA, CEA facilities, decommissioned or partially dismantled reactors, fuel cycle centres.. (J.S.)

High committee for nuclear safety transparency and information. November 20, 2009 meeting of the High Committee; Haut comite pour la transparence et l'information sur la securite nucleaire. Reunion du Haut comite, 20 novembre 2009

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-11-15

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, and, depending on the events, some extraordinary meetings. This document is the proceedings of an extraordinary meeting about the information and transparency in relation with the management of nuclear materials and wastes at all stages of the fuel cycle. The reason of this meeting is a request from the French Minister of ecology, energy, sustainable development and sea (MEEDDM) after the broadcast of a TV documentary entitled 'wastes: the nuclear industry nightmare' and the publication of a press article affirming that 'our nuclear wastes are hidden in Siberia'. The Minister expressed his wish to have the question of the international trade of nuclear materials examined by the HCTISN. The document is organized as follows: a first part presents the hearings of the general direction of energy and climate (DGEC), of the nuclear safety authority (ASN), of EdF, of Areva, of the CEA, of the senior official for the defense and security of the MEEDDM, of Rosatom company and of Greenpeace organisation. A second part examines the incident which took place in October 2009 at the plutonium technology workshop (ATPu) of Cadarache, where about 22 to 39 kg of plutonium powder were discovered in the gloveboxes of this facility, decommissioned in 2005 and undergoing dismantlement today. This part presents the hearings of the CEA, of AREVA, of the Institute of radiation protection and nuclear safety (IRSN), of the ASN, of the hygiene, safety and labour conditions committee (CHSCT) of Areva and CEA, and of the local information commission (CLI) of Cadarache

Statement of the IRSN on the safety re-examination assessment made by EDF within the frame of the third decennial inspection of the 900 MW reactors

International Nuclear Information System (INIS)

2008-01-01

The IRSN (the French Institute of Radioprotection and Nuclear Safety) here presents an assessment of the studies performed by EDF within the frame of the safety re-examination associated to the third decennial inspections of the 900 MW reactors, and of the modifications resulting from these studies with respect to the originally defined objectives of this re-examination. The aim of this report is to allow the ASN (Autorite de Surete Nucleaire, the Nuclear Safety Authority) stating the 900 MW reactor ability to carry on their operation until the fourth decennial inspections. Different themes and studies are assessed: internal and external aggressions (flooding, explosions, fire, seismic control, and climatic aggressions), accident assessments and their radiological consequences (failure of various components, the performing of probabilistic studies, confining procedures, structures and devices, etc.), operation and design of various systems and of civil engineering works. Several documents or extracts of official reports are given in appendix, expressing notably various recommendations on the here-above topics

Transport of proximity nuclear radioactive materials

International Nuclear Information System (INIS)

2010-01-01

This brief publication gives an overview of the international and national regulatory framework for the transport of radioactive substances, outlines progress orientations identified by the French Nuclear Safety Authority (ASN), indicates the parcel classification and shipment radiological criteria, and how to declare events occurring during the transport of radioactive substances, which number to phone in case of a radiological incident. Finally, the role of the ASN and its field of activity in matters of control are briefly presented with a table of its office addresses in France

Safety and authorizations relating to the use of new fuel in research reactors

International Nuclear Information System (INIS)

Niel, J.-C.; Abou Yehia, H.

1999-01-01

After giving a brief reminder of the procedure applied in France for granting licences to modify research reactors, we outline in this paper the main safety aspects associated with using new fuel in these reactors. Finally, by way of an example, we focus on the procedure followed for converting the cores of the OSIRIS (70 MW) and ISIS (700 kW) reactors to U 3 Si 2 Al fuel and the conclusions of the corresponding safety assessments. (author)

Status of safety in nuclear facilities - 2012. AREVA General Inspectorate Annual report

International Nuclear Information System (INIS)

2013-05-01

After a message from the Areva's Chief Executive Officer and a message from the senior Vice President of safety, health, security, sustainable development, a text by the inspector general comments the key safety results (events, dose levels, radiological impacts), the inspection findings, the areas of vigilance (relationship with the ASN, the management of the criticality risk, and facility compliance), some significant topics after the Fukushima accident. Then this report addresses the status of nuclear safety and radiation protection in the group's facilities and operations. It more specifically addresses the context and findings (lessons learned from the inspections, operating experience from event, employee radiation monitoring, environmental monitoring), crosscutting processes (safety management, controlling facility compliance, subcontractor guidance and management, crisis management), specific risks (criticality risk, fire hazards, transportation safety, radioactive waste management, pollution prevention, liability mitigation and dismantling), and areas for improvement and outlook

NPA applications development in the nuclear safety authority framework

International Nuclear Information System (INIS)

Maselj, A.; Vojnovic, D.; Gregonc, M.

1999-01-01

Due to the present tasks of the SNSA (Slovenian Nuclear Safety Administration) there was a need to gain a tool for analysing the transients of the Krsko Nuclear Power Plant at the SNSA. Combining the RELAP5 code with graphical interface NPA (Nuclear Plant Analyzer), the SNSA management saw an opportunity to have a powerful instrument for analyses and assessments on a user friendly basis and without high costs. The Krsko NPP Analyzer is a joint project of the SNSA and the operator, the Krsko NPP. The RELAP5/Mod2.5 input deck was constructed by the Krsko NPP's experts and their subcontractors. In 1996 the work started with translation of input model from RELAP5/Mod2.5 version to Mod3.2. This was done by Tractebel which combined NPA masks with translated input deck and constructed new dynamic function and interactive commands between graphical MMI (Man Machine Interface) and simulation code. Since Tractebel performed similar activities for the Belgian plants, their experience was used through a transfer of knowledge to the SNSA. After this phase of the project, a user of the NPP Analyzer can run accidents as SBLOCA, Main Steam Line Break, Feed Water Break, SGTR, and many other transients activating and combining interactive commands, starting from a full power operation. This project has not been finished yet. Improvements of the input deck should be done. The Critical Safety Function window will be created. The analyzer will be a helpful tool during the training program for Accident Assessment Group, which will give to the experts basic knowledge of plant operation, its systems, and physical phenomena during a steady state and transients or accidents. Also a new dimension is added to the existing safety evaluations at the SNSA to confirm the requested level of nuclear safety at the Krsko NPP. (author)

International conference on strengthening of nuclear safety in Eastern Europe. Armenian Nuclear Regulatory Authority

International Nuclear Information System (INIS)

Nersesyan, V.

1999-01-01

The status of the Armenian Nuclear Regulatory Authority (ANRA) are described in detail with its main task and responsibilities concerning regulations and surveillance of nuclear and radiation safety. The following issues are presented: nuclear legislation; inspection activities; licensing of significant safety related modifications and modernization of NPPs; incidents at NPPs; personnel training; emergency planning; surveillance of nuclear materials; radioactive waste management; and plan of the ANRA perspective development

Nuclear law. January 2011 - July 2012

International Nuclear Information System (INIS)

Bringuier, Pierre; Di Costanzo, Laura

2012-01-01

This paper gives a synthesis of legal aspects concerning nuclear power in France. The following main points are reviewed: institutional aspects (notably the independence of the Nuclear Safety Authority - ASN); transparency and public information; nuclear safety and radiation protection; nuclear materials, their control and security aspects; transports; trade and non-proliferation agreements; radioactive wastes; radiation accidents; liabilities and insurance; nuclear arms

A lipoprotein lipase mutation (Asn291Ser) is associated with reduced HDL cholesterol levels in premature atherosclerosis

NARCIS (Netherlands)

Reymer, P.W.A.; Gagné, S E; Groenemeyer, B E; Zhang, H; Forsyth, I; Jansen, H; Seidell, J C; Kromhout, D.; Lie, K E; Kastelein, J.J.

1995-01-01

A reduction of high density lipoprotein cholesterol (HDC) is recognized as an important risk factor for coronary artery disease (CAD). We now show in approximately 1 in 20 males with proven atherosclerosis that an Asn291Ser mutation in the human lipoprotein lipase (LPL) gene is associated with

Synthesis of the IRSN report related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor. Referral of the Permanent Group of Experts for nuclear reactors (GPR), examination of probabilistic level-2 safety studies (EPS 2) and severe accidents (AG) of the Flamanville reactor nr 3. Opinion related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor (FA3). Electronuclear reactors - EDF - Flamanville 3 EPR reactor. Severe accidents and probabilistic level 2 studies

International Nuclear Information System (INIS)

2015-01-01

This document gathers several documents. The first one recalls the main arrangements implemented on the FA3 EPR reactor regarding accidents with core fusion, reports the analysis made by the IRSN about the sizing of these arrangements to reach a controlled status of the installation after a severe accident, regarding the probabilistic level-2 safety assessment, regarding the radiological impact of a severe accident on the population and on the environment, regarding those aimed at facing a total and long duration loss of electric power sources and cold sources, and about the situation of the reactor with respect to WENRA positions on severe accidents for new reactors. The second document is a letter sent by the ASN to the Permanent Group of Experts for nuclear reactors (GPR) to address probabilistic level-2 safety studies (EPS2) and severe accidents for the Flamanville 3 reactor. The third one reports the opinion of the GPR on these both issues and proposes a set of recommendations. The next document is a letter sent by the ASN to the Flamanville 3 project manager at EDF which recalls the related objectives, the ASN opinion on the implemented arrangements for severe accidents (de-pressurization of the primary circuit, management of hydrogen-related risks, corium recovery and cooling outside the vessel, limitation of vapour explosion risks outside the vessel, heat evacuation system, containment enclosure, management of the risk of a return to criticality), to face a total and long duration loss of electricity sources and cold sources, and other aspects addressed in the IRSN analysis. Requests and remarks formulated by the ASN are provided in an appendix to this last document

Safety assessment of botanicals and botanical preparations used as ingredients in food supplements: testing an European Food Safety Authority-tiered approach.

Science.gov (United States)

Speijers, Gerrit; Bottex, Bernard; Dusemund, Birgit; Lugasi, Andrea; Tóth, Jaroslav; Amberg-Müller, Judith; Galli, Corrado L; Silano, Vittorio; Rietjens, Ivonne M C M

2010-02-01

This article describes results obtained by testing the European Food Safety Authority-tiered guidance approach for safety assessment of botanicals and botanical preparations intended for use in food supplements. Main conclusions emerging are as follows. (i) Botanical ingredients must be identified by their scientific (binomial) name, in most cases down to the subspecies level or lower. (ii) Adequate characterization and description of the botanical parts and preparation methodology used is needed. Safety of a botanical ingredient cannot be assumed only relying on the long-term safe use of other preparations of the same botanical. (iii) Because of possible adulterations, misclassifications, replacements or falsifications, and restorations, establishment of adequate quality control is necessary. (iv) The strength of the evidence underlying concerns over a botanical ingredient should be included in the safety assessment. (v) The matrix effect should be taken into account in the safety assessment on a case-by-case basis. (vi) Adequate data and methods for appropriate exposure assessment are often missing. (vii) Safety regulations concerning toxic contaminants have to be complied with. The application of the guidance approach can result in the conclusion that safety can be presumed, that the botanical ingredient is of safety concern, or that further data are needed to assess safety.

HCTISN, plenary meeting of the 20 of June 2013

International Nuclear Information System (INIS)

2013-01-01

This document gathers Power Point presentations which have been proposed during the meeting of the High committee for transparency and information on nuclear safety (HCTISN). A first PP, proposed by the ASN, presents the ASN's plan to implement the principle of public participation to the elaboration of its regulatory or individual decisions related to the environment. The second one, proposed by the ANDRA, presents the FAVL (low activity long life) waste storage project, notably for wastes containing radium, graphite or bitumen (waste classification, context, waste origin, temporary storage, long term management, project of small depth storage, site search process, project orientations). The third one, made by the ASN, discusses the opinion of the ASN on documents produced by the ANDRA since 2009 about the project of radioactive waste storage in deep geological layers (context, creation authorization procedure, general considerations, waste inventory, seismic data acquisition, direct storage of spent fuels coming from power reactors)

Safety evaluation report on Tennessee Valley Authority: Browns Ferry nuclear performance plan

International Nuclear Information System (INIS)

1989-10-01

This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory commission staff. The Browns Ferry Nuclear Plant consists of three boiling-water reactors at a site in Limestone County, Alabama. The plan addresses the plant-specific concerns requiring resolution before the startup of Unit 2. The staff will inspect implementation of those TVA programs that address these concerns. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 85 refs

Safety evaluation report on Tennessee Valley Authority: Watts Bar Nuclear Performance Plan

International Nuclear Information System (INIS)

1990-01-01

This safety evaluation report on the information submitted by the Tennessee Valley Authority in its Nuclear Performance Plan for the Watts Bar Nuclear Plant and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific corrective actions as part of the recovery program for licensing of Unit 1. The staff will be monitoring and inspecting the implementation of the programs. The plan does not address all licensing matters that will be required for fuel load and operation of Unit 1. Those remaining licensing matters have been addressed in previous safety evaluations or will be addressed in accordance with routing NRC licensing practices. 97 refs

76 FR 63988 - Pilot Project on NAFTA Trucking Provisions; Pre-Authorization Safety Audits

Science.gov (United States)

2011-10-14

...-0097] Pilot Project on NAFTA Trucking Provisions; Pre-Authorization Safety Audits AGENCY: Federal Motor... motor carriers that applied to participate in the Agency's long-haul pilot program to test and... intent to proceed with the initiation of a United States- Mexico cross-border long-haul trucking pilot...

High committee for transparency and information on nuclear safety: meeting of December 16, 2010; Haut Comite pour la Transparence et l'Information sur la Securite Nucleaire. Reunion du 16 decembre 2010

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-07-01

The discussion between members dealt with the following topics: the committee' program and implication with respect to the ACN approach (Aarhus Convention and Nuclear), the main orientations of the Transparency and Secret work group, the hearing of actors involved in a Tritium contamination incident in Valduc. These actors belonged to the CEA, to the 2M Process company, to the Nuclear safety authority or ASN, to the Institute for radiation protection and nuclear safety or IRSN, or to the Delegate to radiation protection and nuclear safety for installations of interest for the defence or DSND. Then the committee addressed the issue of old uranium mines and of places of use of uranium mining tailings. The committee members discuss the results of investigations performed around the Tricastin site (studies on cancers, on the presence of uranium in underground water sheets). Other topics are addressed: waste transportation to Germany, the French-British nuclear cooperation, the creation of a web site

Stěžejní východiska a koncepce současné anglické náboženské pedagogiky

Directory of Open Access Journals (Sweden)

Karim Sidibe

2017-08-01

Full Text Available Tento článek si klade za cíl analyzovat didaktické koncepce výuky náboženství pěti hlavních teoretiků současné anglické náboženské pedagogiky, Harolda Loukese, Niniana Smarta, Davida Haye, Cliva Errickera a Andrewa Wrighta. Loukes a Smart položili základy současné náboženské pedagogiky v Anglii v 60. letech 20. století. Loukes využil poznatky vývojové psychologie a Smart výuku sekularizoval. Hayovo pojetí z 80. let 20. století akcentuje niternou duchovní skutečnost žáků. V současné době Erricker aplikuje postmoderní filosofická východiska na výuku a akcentuje individualitu a nezávislost žáků, zatímco Wright vychází z filosofických východisek kritického realismu a akcentuje nutnost teologické a filosofické diskuze na hodinách náboženství.

Public safety around dams : Grand River Conservation Authority

Energy Technology Data Exchange (ETDEWEB)

Moore, N [Grand River Conservation Authority, Cambridge, ON (Canada)

2009-07-01

Ontario's Grand River Conservation Authority (GRCA) is a corporate body, through which municipalities, landowners and other organizations work cooperatively to manage the watershed and outdoor recreation. This involves reducing flood damage; improving water quality; providing adequate water supply; protecting natural areas; watershed planning; and environmental education. This presentation discussed public safety issues regarding a dam in the GRCA that is 5 minutes to downtown Brantford; 5 minutes to several elementary and secondary schools; and a popular area for anglers. The city of Brantford owns the east embankment and the Brant conservation area is located on the west embankment. The safeguards included measures to involve the municipality and local police; install better signage; install better fencing; and public education. Increasing public awareness of the dangers surrounding dams was an important point of the presentation. Results included reduced trespassing and greater community awareness. figs.

Criteria adopted by the Argentine Nuclear Regulatory Authority for assessing digital systems related to safety

International Nuclear Information System (INIS)

Terrado, Carlos A.; Chiossi, Carlos E.; Felizia, Eduardo R.; Roca, Jose L.; Sajaroff, Pedro M.

2004-01-01

Following the technological evolution in Instrumentation and Control (I and C) design, analog components are replaced by digital in almost every industry. Due to growing challenges of obsolescence and increasing maintenance costs, licensees of nuclear and radioactive installations are increasingly upgrading or replacing their existing I and C analog systems and components. In existing installations, this involves analog to digital replacements. In new installations design, the use of digital I and C systems is being considered from the very beginning, becoming a good alternative, even in safety applications. Up to now, in Argentina, there is no specific rules for safety-related digital systems, every safety system, analog or digital, must comply with the same generic regulations. The Nuclear Regulatory Authority is now developing criteria to assess digital systems related to safety in nuclear and radioactive installations. In this paper some of those criteria, based on local research and the recognized state of the art, are explained. From a regulatory point of view, the use of digital technology often raises new technical and licensing issues, particularly for safety-related applications. Examples include new failure modes, the potential for common-cause failure of redundant components, electromagnetic interference (EMI), software verification and validation, configuration management and a more exhaustive quality assurance system. The mentioned criteria comprehend the design, operation, maintenance and acquisition of digital systems and components important to safety. The main topics covered are: requirements specifications for digital systems, planning and documentation for digital system development, effectiveness of a digital system, commercial off the shelf (COTS) treatment and considerations involving tools for software development. (author)

Notification and authorization for the use of radiation sources (supplement to IAEA Safety Standards Series No. GS-G-1.5)

International Nuclear Information System (INIS)

2007-04-01

The achievement and maintenance of a high level of safety in the use of radiation sources depend on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for notification and authorization for control over radiation sources, including a system for review and assessment of applications for authorization. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the process for dealing with applications for authorization and accepting notifications to regulatory bodies. Examples of guidelines that may be used by persons required to notify or apply for authorization and of the regulatory body's review and assessment procedures are provided in the Appendices. The TECDOC is oriented towards national regulatory infrastructures concerned with protection and safety for radiation sources used in medicine, industry, agriculture, research and education

Notification and authorization for the use of radiation sources (supplement to IAEA Safety Standards Series No. GS-G-1.5)

International Nuclear Information System (INIS)

2010-10-01

The achievement and maintenance of a high level of safety in the use of radiation sources depend on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for notification and authorization for control over radiation sources, including a system for review and assessment of applications for authorization. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the process for dealing with applications for authorization and accepting notifications to regulatory bodies. Examples of guidelines that may be used by persons required to notify or apply for authorization and of the regulatory body's review and assessment procedures are provided in the Appendices. The TECDOC is oriented towards national regulatory infrastructures concerned with protection and safety for radiation sources used in medicine, industry, agriculture, research and education

Notification and authorization for the use of radiation sources (Supplement to IAEA Safety Standards Series No. GS-G-1.5)

International Nuclear Information System (INIS)

2011-10-01

The achievement and maintenance of a high level of safety in the use of radiation sources depend on there being a sound legal and governmental infrastructure, including a national regulatory body with well-defined responsibilities and functions. These responsibilities and functions include establishing and implementing a system for notification and authorization for control over radiation sources, including a system for review and assessment of applications for authorization. The Safety Requirements publication entitled Legal and Governmental Infrastructure for Nuclear, Radiation, Radioactive Waste and Transport Safety establishes the requirements for legal and governmental infrastructure. The term 'infrastructure' refers to the underlying structure of systems and organizations. This includes requirements concerning the establishment of a regulatory body for radiation sources and the responsibilities and functions assigned to it. The International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources (the Basic Safety Standards or the BSS) establish basic requirements for protection against risks associated with exposure to ionizing radiation and for the safety of radiation sources. The application of the BSS is based on the presumption that national infrastructures are in place to enable governments to discharge their responsibilities to for radiation protection and safety. This TECDOC provides practical guidance on the process for dealing with applications for authorization and accepting notifications to regulatory bodies. Examples of guidelines that may be used by persons required to notify or apply for authorization and of the regulatory body's review and assessment procedures are provided in the Appendices. The TECDOC is oriented towards national regulatory infrastructures concerned with protection and safety for radiation sources used in medicine, industry, agriculture, research and education. The IAEA

HOST GALAXY PROPERTIES OF THE SUBLUMINOUS GRB 120422A/SN 2012bz

Energy Technology Data Exchange (ETDEWEB)

Levesque, Emily M. [CASA, Department of Astrophysical and Planetary Sciences, University of Colorado 389-UCB, Boulder, CO 80309 (United States); Chornock, Ryan; Soderberg, Alicia M.; Berger, Edo; Lunnan, Ragnhild, E-mail: Emily.Levesque@colorado.edu [Harvard-Smithsonian Center for Astrophysics, 60 Garden Street, Cambridge, MA 02138 (United States)

2012-10-20

GRB 120422A is a nearby (z = 0.283) long-duration gamma-ray burst (LGRB) detected by Swift with E {sub {gamma},iso} {approx} 4.5 Multiplication-Sign 10{sup 49} erg. It is also associated with the spectroscopically confirmed broad-lined Type Ic SN 2012bz. These properties establish GRB 120422A/SN 2012bz as the sixth and newest member of the class of subluminous GRBs supernovae (SNe). Observations also show that GRB 120422A/SN 2012bz occurred at an unusually large offset ({approx}8 kpc) from the host galaxy nucleus, setting it apart from other nearby LGRBs and leading to speculation that the host environment may have undergone prior interaction activity. Here, we present spectroscopic observations using the 6.5 m Magellan telescope at Las Campanas. We extract spectra at three specific locations within the GRB/SN host galaxy, including the host nucleus, the explosion site, and the 'bridge' of diffuse emission connecting these two regions. We measure a metallicity of log(O/H) + 12 = 8.3 {+-} 0.1 and a star formation rate (SFR) per unit area of 0.08 M {sub Sun} yr{sup -1} kpc{sup -2} at the host nucleus. At the GRB/SN explosion site we measure a comparable metallicity of log(O/H) + 12 = 8.2 {+-} 0.1 but find a much lower SFR per unit area of 0.01 M {sub Sun} yr{sup -1} kpc{sup -2}. We also compare the host galaxy of this event to the hosts of other LGRBs, including samples of subluminous LGRBs and cosmological LGRBs, and find no systematic metallicity difference between the environments of these different subtypes.

Asn563Ser polymorphism of CD31/PECAM-1 is associated with atherosclerotic cerebral infarction in a southern Han population

Directory of Open Access Journals (Sweden)

Song YM

2014-12-01

Full Text Available Yanmin Song, Qunfang Li, Lili Long, Ning Zhang, Yunhai Liu Department of Neurology, Xiangya Hospital, Central South University, Changsha, Hunan Province, People’s Republic of China Background: CD31, also called platelet endothelial cell adhesion molecule-1 (PECAM-1, is thought to play a role in the pathological mechanisms of atherosclerosis. Leu125Val polymorphism and elevated plasma levels of soluble PECAM-1 (sPECAM-1 were found to be associated with cerebral infarction. Our aim was to investigate the association between the Asn563Ser polymorphism of CD31/PECAM-1, plasma level of sPECAM-1, and the risk of atherosclerotic cerebral infarction (ACI in the southern Han population of the People’s Republic of China.Subjects and methods: A total of 147 subjects with ACI and 114 controls were enrolled in the study. The Asn563Ser CD31/PECAM-1 polymorphism was detected using the polymerase chain reaction–restriction fragment length polymorphism method. The plasma spECAM-1 level was measured using the enzyme-linked immunosorbent assay method.Results: In this study, statistically significant differences in Asn563Ser genotype and allele distribution were found between the cases and controls (P<0.05. Furthermore, logistic regression analysis showed that the GG genotype is associated with increase in ACI risk (odds ratio =4.862, P<0.001. The plasma level of sPECAM-1 was associated with ACI (odds ratio =1.431, P=0.038. In both the ACI and the control groups, the plasma sPECAM-1 level in subjects with the GG genotype was higher than that in subjects carrying the AA or GA genotype (P<0.05.Conclusion: Our study showed that the Asn563Ser polymorphism of CD31/PECAM-1 gene and elevated plasma sPECAM-1 level are related to ACI risk in the southern Han population of People’s Republic of China. Keywords: genetic polymorphism, CD31, platelet endothelial cell adhesion molecule-1 (PECAM-1

Transport safety and struggle against malevolent acts: a synergy to be developed - Protecting transports against malevolent acts, Synergies between security and safety: lessons learned from the IAEA international conference, Role of the IRSN transport operational level in the field of safety, Transparency and secret in the field of nuclear material transport

International Nuclear Information System (INIS)

Riac, Christian; Flory, Denis; Loiseau, Olivier; Mermaz, Frederic; Demolins, Laurent

2012-01-01

The first article proposes an interview with the chief of the security department within the French ministry of Ecology, Sustainable Development, Transports and Housing who comments his missions and his relationships with the ASN and the French Home Office for the protection and control of nuclear materials. A second article discusses the lessons learned from an IAEA international conference about the relationship between the approaches to security and to safety. The third article briefly describes the role of the IRSN transport operational level in the field of safety. The last article discusses how opposite notions like transparency and secret are managed in the case of nuclear material transport

NRPA develops regulatory cooperation with Central Asian authorities for nuclear safety and radiation protection

International Nuclear Information System (INIS)

2009-01-01

With the support of the Norwegian Ministry of Foreign Affairs, the NRPA has initiated a regional regulatory cooperation project with Kazakhstan, Kyrgyzstan and Tajikistan to improve regulations on nuclear safety, radiation protection and environmental issues, and assist the countries in re mediating radioactively contaminated sites. There is a critical lack in the regulatory basis for carrying out such remediation work, including a lack of relevant radiation and environmental safety norms and standards, licensing procedures and requirements for monitoring, as well as expertise to transform such a basis into practice. (Author)

Procedure for getting safety classed concrete structures approved by Finnish Radiation and Nuclear Safety Authority

International Nuclear Information System (INIS)

Halme, Ville-Juhani

2015-01-01

Posiva is preparing geological final disposal in the Finnish bedrock in Olkiluoto, Eurajoki. The final disposal facility includes encapsulation plant and underground repository. Most of the main civil structures are concrete structures. STUK is the supervising authority in civil structures. The National Building Code of Finland and STUK's Regulatory Guide on nuclear safety (YVL) are the most important instructions when constructing concrete structures into nuclear installation. Posiva has classified concrete structures in two classes according STUK's YVL-guidance: EYT (non-nuclear) and Safety Class 3 (SC 3, nuclear safety significance). When building SC 3 concrete structures, specific protocol must be followed. Protocol includes planned routines for design, construction, supervision, quality control (QC) and quality assurance (QA) activities. Documents relating concrete structures must be approved by Posiva and STUK before construction work. After structures have been designed and actual building is ongoing, there are two main steps. Before concreting, readiness inspection for concreting must be arranged. Readiness inspection will be arranged according to a specific plan and the date must be informed to STUK. After establishing readiness for concreting, casting work can begin. Once concrete structures are done, inspected and approved, final documentation according to a quality control plan will be reviewed by Posiva. After Posiva's approval, final documentation will be sent for STUK's approval. In the end STUK will give the permission for commissioning of the concrete structures after approved commissioning inspection. The document is made up of an abstract and a poster

Flexible xxx-asp/asn and gly-xxx residues of equine cytochrome C in matrix-assisted laser desorption/ionization in-source decay mass spectrometry.

Science.gov (United States)

Takayama, Mitsuo

2012-01-01

The backbone flexibility of a protein has been studied from the standpoint of the susceptibility of amino acid residues to in-source decay (ISD) in matrix-assisted laser desorption/ionization mass spectrometry (MALDI MS). Residues more susceptible to MALDI-ISD, namely Xxx-Asp/Asn and Gly-Xxx, were identified from the discontinuous intense peak of c'-ions originating from specific cleavage at N-Cα bonds of the backbone of equine cytochrome c. The identity of the residues susceptible to ISD was consistent with the known flexible backbone amides as estimated by hydrogen/deuterium exchange (HDX) experiments. The identity of these flexible amino acid residues (Asp, Asn, and Gly) is consistent with the fact that these residues are preferred in flexible secondary structure free from intramolecular hydrogen-bonded structures such as α-helix and β-sheet. The MALDI-ISD spectrum of equine cytochrome c gave not only intense N-terminal side c'-ions originating from N-Cα bond cleavage at Xxx-Asp/Asn and Gly-Xxx residues, but also C-terminal side complement z'-ions originating from the same cleavage sites. The present study implies that MALDI-ISD can give information about backbone flexibility of proteins, comparable with the protection factors estimated by HDX.

Flexible Xxx–Asp/Asn and Gly–Xxx Residues of Equine Cytochrome c in Matrix-Assisted Laser Desorption/Ionization In-Source Decay Mass Spectrometry

Science.gov (United States)

Takayama, Mitsuo

2012-01-01

The backbone flexibility of a protein has been studied from the standpoint of the susceptibility of amino acid residues to in-source decay (ISD) in matrix-assisted laser desorption/ionization mass spectrometry (MALDI MS). Residues more susceptible to MALDI-ISD, namely Xxx–Asp/Asn and Gly–Xxx, were identified from the discontinuous intense peak of c′-ions originating from specific cleavage at N–Cα bonds of the backbone of equine cytochrome c. The identity of the residues susceptible to ISD was consistent with the known flexible backbone amides as estimated by hydrogen/deuterium exchange (HDX) experiments. The identity of these flexible amino acid residues (Asp, Asn, and Gly) is consistent with the fact that these residues are preferred in flexible secondary structure free from intramolecular hydrogen-bonded structures such as α-helix and β-sheet. The MALDI-ISD spectrum of equine cytochrome c gave not only intense N-terminal side c′-ions originating from N–Cα bond cleavage at Xxx–Asp/Asn and Gly–Xxx residues, but also C-terminal side complement z′-ions originating from the same cleavage sites. The present study implies that MALDI-ISD can give information about backbone flexibility of proteins, comparable with the protection factors estimated by HDX. PMID:24349908

ASN.1 notation for exchange of data in computer-based railway control systems

Directory of Open Access Journals (Sweden)

Zbigniew ŁUKASIK

2009-01-01

Full Text Available Development of railway control systems aims at computerization. In most cases these systems are Distributed Real Time Systems. However, a huge problem in their putting into practice is the lack of interface standardization in the range of data structures and information exchange methods. It results in a variety of solutions, and thus in problems concerning cooperation of systems that come from different software vendors. Specification of protocols for data exchanging applications should therefore be created with the use of generally accepted standards. One of them is ASN.1 (Abstract Syntax Notation One language, which shall be presented in this article.

Leukaemia risks and exposure to ionizing radiations. ASN seminar, Tuesday, June 9, 2015, report

International Nuclear Information System (INIS)

Niel, Jean-Christophe; Samain, Jean-Paul; Colonna, Marc; Maynadie, Marc; Richardson, David; Bey, Pierre; Leuraud, Klervi; Laurier, Dominique; Hemon, Denis; Spycher, Ben; Kosti, Ourania; Bouville, Andre; Grosche, Bernd; Ziegelberger, Gunde; Kesminiene, Ausrele; Clavel, Jacqueline; Smeesters, Patrick; Murith, Christophe

2015-08-01

This seminar aims at proposing a review of present knowledge on leukaemia risks for children and adults associated with ionizing radiations, and at sharing knowledge between experts. After an introduction which outlined the interest of the ASN in research issues, and the importance awarded by the ASN to the variety of points of view, a first session addressed leukaemia and exposures to ionizing radiations. The contributions addressed some general aspects (an overview of leukaemia in France, the different types of adult and child leukaemia), leukaemia and acute exposures to ionizing radiations (ionizing radiation and leukaemia among Japanese bomb survivors, risks of leukaemia after radiotherapy), leukaemia and chronic exposures to ionizing radiations (assessment of epidemiological studies for adult chronic exposures). The second session addressed childhood leukaemia and ionizing radiations. The contributions of this second session more particularly addressed the following topics: childhood leukaemia and natural radioactivity (French studies, synthesis of international studies and a new Swiss study), childhood leukaemia and proximity of nuclear base installations (assessment of national and international studies, analysis of cancer risks in populations near nuclear facilities in the US, calculation of dose at the medulla as example of dosimetry of ionizing radiations and leukaemia, conclusions of the 2012 MELODI workshop), childhood leukaemia and scanner (recent results and perspectives), childhood leukaemia and other risk factors (etiology of childhood leukaemia - presentation of French studies initiated by the INSERM, and presentation of studies initiated by BfS)

Modalities of exploitation of the AP2 fuel fabrication plant at the FBFC facility of Romans-sur-Isere (INB98)

International Nuclear Information System (INIS)

2001-01-01

This decision from the French authority of nuclear safety (ASN) aims at establishing a normal framework to the effluents management and waste storage activities that are carried out inside the 'south storage shed' of the AP2 fuel fabrication plant of the FBFC facility of Romans-sur-Isere (France). (J.S.)

Power learning or path dependency? Investigating the roots of the European Food Safety Authority.

Science.gov (United States)

Roederer-Rynning, Christilla; Daugbjerg, Carsten

2010-01-01

A key motive for establishing the European Food Safety Authority (EFSA) was restoring public confidence in the wake of multiplying food scares and the BSE crisis. Scholars, however, have paid little attention to the actual political and institutional logics that shaped this new organization. This article explores the dynamics underpinning the making of EFSA. We examine the way in which learning and power shaped its organizational architecture. It is demonstrated that the lessons drawn from the past and other models converged on the need to delegate authority to an external agency, but diverged on its mandate, concretely whether or not EFSA should assume risk management responsibilities. In this situation of competitive learning, power and procedural politics conditioned the mandate granted to EFSA. The European Commission, the European Parliament and the European Council shared a common interest in preventing the delegation of regulatory powers to an independent EU agency in food safety policy.

Cigeo storage project - Examination of the Safety options file. Meeting of the Experts Permanent Groups for wastes and for laboratories and plants on the 18-19 May 2017

International Nuclear Information System (INIS)

2017-01-01

This document contains a report in two volumes and several appendices with documents issues by other bodies than the IRSN (notably the ASN). The two volumes report a study made on the request of the ASN regarding safety options for the Cigeo project of deep geological storage of nuclear wastes. The first volume proposes a description of the Cigeo project (site, storage architecture, parcels, Cigeo timescale, storage closure, processes implemented within the installations, Cigeo adaptability to inventory evolution, safety functions), addresses the waste parcel inventory (parcel inventory, reference radiological and chemical inventories, storage planning, reserve wastes, spent fuels), presents elements related to the site itself (geological context, natural resources, geo-dynamic characterisation, host rock, hydro-geology of aquifer layers), discusses the evolution of storage components (parcel behaviour after storage closure, evolution of steels, of concretes and of clayey materials). The second volume proposes a detailed overview of the safety approach for the different phases (exploitation, and after closure), proposes an assessment of safety during the exploitation phase (internal risks from nuclear origin, internal aggressions like fire, flooding or explosion, or related to parcel transport and handling, external aggressions like earthquakes, external flooding, and issues related to exploitation effluents and wastes), and proposes a safety assessment after closure (risk analysis for underground installations, and assessment of the global confinement capacity)

Safety guidebook relative to the disposal of radioactive wastes in deep geologic formation; Guide de surete relatif au stockage definitif des dechets radioactifs en formation geologique profonde

Energy Technology Data Exchange (ETDEWEB)

NONE

2008-07-01

The French nuclear safety authority (ASN) initiated in 2003 a revision process of the objectives to be considered during the research and work steps of the implementation of a radioactive waste storage facility in deep geologic formations. The purpose of this document is to define the safety objectives that have to be retained at each step of this implementation, from the site characterization to the closure of the facility. This update takes into account the works carried out by the ANDRA (French national agency of radioactive wastes) in the framework of the law from December 30, 1991, and the advices of the permanent experts group about these works. It takes also into consideration the international research works in this domain and the choices defined in the program law no 2006-739 from June 28, 2006 relative to the sustainable management of radioactive materials and wastes. The main modifications concern: the notion of reversibility, the definition of the safety functions of disposal components, the safety goals and the design principles assigned to waste packages, the control of nuclear materials and the monitoring objectives of the facility. The documents treats of the following points: 1 - the objectives of public health and environment protection; 2 - the safety principles and the safety-related design bases of the facility; and 3 - the method used for demonstrating the disposal safety. (J.S.)

Order of the 24. of November 2009 approving the decision n. 2009-DC-0147 made on the 16. of July 2009 by the Nuclear Safety Authority (ASN) defining duties practice conditions of a person having abilities in radioprotection and external to the establishment to apply the R. 4456-4 article of the Labour Code

International Nuclear Information System (INIS)

2009-01-01

This legal text approves a decision made by the ASN defining notably the content and formalization of the agreement between the employer and the person having abilities in radioprotection and who is external to the establishment. It also defines their reciprocal obligations. It indicates the groups of electrical equipment generating X rays and the groups of professional activities which are concerned by this order. It finally defines the requirements related the interventions of this person (frequency, mandatory interventions) with respect to the equipment groups

Improving Research Reactor Accident Response Capability at the Hungarian Nuclear Safety Authority

International Nuclear Information System (INIS)

Vegh, J.; Gajdos, F.; Horvath, Cs.; Matisz, A.; Nyisztor, D.

2013-06-01

The paper describes the design and implementation of an on-line operation monitoring and accident response support system to be used at the CERTA emergency response centre of Hungarian Atomic Energy Authority (HAEA). The monitored facility is the Budapest Research Reactor (BRR), which is a tank-type thermal reactor having 10 MW thermal power. The basic reason for the development of the on-line safety information system is to extend the emergency response capability of the CERTA crisis centre to include emergencies related to BRR, as well. CERTA is operated by HAEA at its Budapest headquarters and the centre already has an on-line system for monitoring the state of the four units of Paks NPP, Hungary. The system is called CERTA VITA and it is able to monitor the four VVER-440/V213 units during their normal operation, and during emergencies (including severe accidents). Ensuring appropriate emergency response capabilities, as well as improving the presently available systems and tools was one of the important recommendations resulting from the analyses following the severe accident at Fukushima. This task is valid not only for the operators of the nuclear facilities but also for the nuclear safety authorities, therefore HAEA decided to launch a project - together with the Centre for Energy Research, the operator of BRR - to establish an on-line information system similar to the CERTA VITA used for monitoring the four units of the Paks NPP. It is believed that by the introduction of this new on-line system the accident response capabilities of HAEA will be further enhanced and the BRR emergencies will be handled at the same professional level as potential emergencies at Paks NPP. (authors)

THE ANALYSIS TOWARDS STATE APPARATUS COMMISSION ROLE IN ASN MANAGEMENT SYSTEM IN INDONESIA

Directory of Open Access Journals (Sweden)

Ajib Rakhmawanto

2015-05-01

Full Text Available In administrating bureaurcy business process, professional state apparatus are needed. Law number 5 of 2014 about the state civil apparatus mentions management based on merit that supposed to be supervised by an independen institution: State Apparatuss Commision (KASN. This article aims to analyze the KASN, and identify its task, function, and responsibilities. The analysis showed that KASN was formed to create professional state apparatus and supervise the merit system based management. The function of KASN becomes ineffective considering there is NCSA, an establish body with a role to supervise the ASN management. KASN will cause an overlapping and conflict of interest between the two institutions.

Asn792 participates in the hydrogen bond network around the K+-binding pocket of gastric H,K-ATPase.

NARCIS (Netherlands)

Swarts, H.G.P.; Koenderink, J.B.; Willems, P.H.G.M.; Krieger, E.; Pont, J.J.H.H.M. de

2005-01-01

Asn792 present in M5 of gastric H,K-ATPase is highly conserved within the P-type ATPase family. A direct role in K+ binding was postulated for Na,K-ATPase but was not found in a recent model for gastric H,K-ATPase (Koenderink, J. B., Swarts, H. G. P., Willems, P. H. G. M., Krieger, E., and De Pont,

International cooperation in production inspections

International Nuclear Information System (INIS)

Limousin, S.

2009-01-01

Nuclear pressure equipment, like the reactor pressure vessel or steam generators, are manufactured in many countries all around the world. As only few reactors were built in the 90's, most of the nuclear safety authorities have lost part of their know how in component manufacturing oversight. For these two reasons, vendor inspection is a key area for international cooperation. On the one hand, ASN has bilateral relationships with several countries (USA, Finland, China...) to fulfill specific purposes. On the other hand, ASN participates in international groups like the MDEP ( Multinational Design Evaluation Program). A MDEP working group dedicated to vendor inspection cooperation enables exchanges of informations (inspection program plan, inspection findings...) among the regulators. Join inspections are organized. International cooperation could lead in the long term to an harmonization of regulatory practices. (author)

IRSN-ANCCLI partnership. ANCCLI-IRSN seminar: Safety challenges after the Fukushima accident - September 2011

International Nuclear Information System (INIS)

Compagnat, Gilles; Laurent, Michel; Baumont, David; Rebour, Vincent; Quentin, Pascal

2011-09-01

Presented under the form of Power Point presentations, the contributions of this seminar proposed: a presentation by the ASN of the French context and of what is at stake with the complementary safety assessments of the French nuclear power plants, a report of the activities the three local information commissions of the Manche district within the context created by the Fukushima accident, and discussions by IRSN experts of the main safety challenges related to seismic hazard (discussion of the robustness of nuclear installations in this respect), to flooding (risk assessment), to a loss of cooling systems and loss of electric supplies, and to crisis management. Finally, a synthesis of the seminar is proposed

Nuclear safety culture and nuclear safety supervision

International Nuclear Information System (INIS)

Chai Jianshe

2013-01-01

In this paper, the author reviews systematically and summarizes up the development process and stage characteristics of nuclear safety culture, analysis the connotation and characteristics of nuclear safety culture, sums up the achievements of our country's nuclear safety supervision, dissects the challenges and problems of nuclear safety supervision. This thesis focused on the relationship between nuclear safety culture and nuclear safety supervision, they are essential differences, but there is a close relationship. Nuclear safety supervision needs to introduce some concepts of nuclear safety culture, lays emphasis on humanistic care and improves its level and efficiency. Nuclear safety supervision authorities must strengthen nuclear safety culture training, conduct the development of nuclear safety culture, make sure that nuclear safety culture can play significant roles. (author)

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Klein, A.

1978-04-11

This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index.

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author. Vol. 11(1)--Vol. 18(6)

International Nuclear Information System (INIS)

Cottrell, W.B.; Klein, A.

1978-01-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Vol. 11, No. 1 (January-February 1970), through Vol. 18, No. 6 (November-December 1977). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 450 technical articles published in Nuclear Safety in the last eight years are listed in this index

Safety evaluation report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan

International Nuclear Information System (INIS)

1991-01-01

This safety evaluation report (SER) was prepared by the US Nuclear Regulatory Commission (NRC) staff and represents the second and last supplement (SSER 2) to the staff's original SER published as Volume 3 of NUREG-1232 in April 1989. Supplement 1 of Volume 3 of NUREG-1232 (SSER 1) was published in October 1989. Like its predecessors, SSER 2 is composed of numerous safety evaluations by the staff regarding specific elements contained in the Browns Ferry Nuclear Performance Plan (BFNPP), Volume 3 (up to and including Revision 2), submitted by the Tennessee Valley Authority (TVA) for the Browns Ferry Nuclear Plant (BFN). The Browns Ferry Nuclear Plant consists of three boiling-water reactors (BWRs) at a site in Limestone County, Alabama. The BFNPP describes the corrective action plans and commitments made by TVA to resolve deficiencies with its nuclear programs before the startup of Unit 2. The staff has inspected and will continue to inspect TVA's implementation of these BFNPP corrective action plans that address staff concerns about TVA's nuclear program. SSER 2 documents the NRC staff's safety evaluations and conclusions for those elements of the BFNPP that were not previously addressed by the staff or that remained open as a result of unresolved issues identified by the staff in previous SERs and inspections

Preventing E-cadherin aberrant N-glycosylation at Asn-554 improves its critical function in gastric cancer

Science.gov (United States)

Carvalho, S; Catarino, TA; Dias, AM; Kato, M; Almeida, A; Hessling, B; Figueiredo, J; Gärtner, F; Sanches, JM; Ruppert, T; Miyoshi, E; Pierce, M; Carneiro, F; Kolarich, D; Seruca, R; Yamaguchi, Y; Taniguchi, N; Reis, CA; Pinho, SS

2016-01-01

E-cadherin is a central molecule in the process of gastric carcinogenesis and its posttranslational modifications by N-glycosylation have been described to induce a deleterious effect on cell adhesion associated with tumor cell invasion. However, the role that site-specific glycosylation of E-cadherin has in its defective function in gastric cancer cells needs to be determined. Using transgenic mice models and human clinical samples, we demonstrated that N-acetylglucosaminyltransferase V (GnT-V)-mediated glycosylation causes an abnormal pattern of E-cadherin expression in the gastric mucosa. In vitro models further indicated that, among the four potential N-glycosylation sites of E-cadherin, Asn-554 is the key site that is selectively modified with β1,6 GlcNAc-branched N-glycans catalyzed by GnT-V. This aberrant glycan modification on this specific asparagine site of E-cadherin was demonstrated to affect its critical functions in gastric cancer cells by affecting E-cadherin cellular localization, cis-dimer formation, molecular assembly and stability of the adherens junctions and cell–cell aggregation, which was further observed in human gastric carcinomas. Interestingly, manipulating this site-specific glycosylation, by preventing Asn-554 from receiving the deleterious branched structures, either by a mutation or by silencing GnT-V, resulted in a protective effect on E-cadherin, precluding its functional dysregulation and contributing to tumor suppression. PMID:26189796

Deliberation nr 2011-DL-0018 of the Nuclear Safety Authority on the 14 June 2011 regarding the improvement of radiation protection in interventional radiology

International Nuclear Information System (INIS)

2011-01-01

After having presented and commented the context of interventional radiology (relatively high doses received by patients and workers, development of a return on experience, assessment of the ASN inspection programs), this report proposes actions in the field of radiation protection, and more particularly in the fields of training, of personnel availability, and of hospital management

Aggregate analysis of regulatory authority assessors' comments to improve the quality of periodic safety update reports.

Science.gov (United States)

Jullian, Sandra; Jaskiewicz, Lukasz; Pfannkuche, Hans-Jürgen; Parker, Jeremy; Lalande-Luesink, Isabelle; Lewis, David J; Close, Philippe

2015-09-01

Marketing authorization holders (MAHs) are expected to provide high-quality periodic safety update reports (PSURs) on their pharmaceutical products to health authorities (HAs). We present a novel instrument aiming at improving quality of PSURs based on standardized analysis of PSUR assessment reports (ARs) received from the European Union HAs across products and therapeutic areas. All HA comments were classified into one of three categories: "Request for regulatory actions," "Request for medical and scientific information," or "Data deficiencies." The comments were graded according to their impact on patients' safety, the drug's benefit-risk profile, and the MAH's pharmacovigilance system. A total of 476 comments were identified through the analysis of 63 PSUR HA ARs received in 2013 and 2014; 47 (10%) were classified as "Requests for regulatory actions," 309 (65%) as "Requests for medical and scientific information," and 118 (25%) comments were related to "Data deficiencies." The most frequent comments were requests for labeling changes (35 HA comments in 19 ARs). The aggregate analysis revealed commonly raised issues and prompted changes of the MAH's procedures related to the preparation of PSURs. The authors believe that this novel instrument based on the evaluation of PSUR HA ARs serves as a valuable mechanism to enhance the quality of PSURs and decisions about optimization of the use of the products and, therefore, contributes to improve further the MAH's pharmacovigilance system and patient safety. Copyright © 2015 John Wiley & Sons, Ltd.

Lessons learned form IRSN review of Flamanville 3 Level PSA

International Nuclear Information System (INIS)

Georgescu, G.; Corenwinder, F.

2012-01-01

In the frame of the construction and licensing of Flamanville 3 NPP the PSA (Probabilistic Safety Assessment)plays an important role for the EPR Project assessment. The PSA was used for early design verification of EPR Reactor, several design improvement being defined based on these PSA insights and following the discussions with the French and German safety authorities. IRSN, as the French Safety Authority (ASN) technical support organization, performs the review of the PSA developed by the plant operator (EDF). The paper presents the main issues regarding the using of 'design PSA', identified by IRSN following the review of the internal events Level 1 PSA transmitted by EDF in the frame of the anticipated instruction of the application for operating license of the Flamanville 3 reactor. (authors)

Report on transparency and nuclear safety - Saclay - 2012

International Nuclear Information System (INIS)

2013-01-01

This report presents the different nuclear base installations (INB) of the Saclay CEA centre, gives an overview of measures regarding safety within these installations (organisation, technical general arrangements, technical arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and dosimetry results, internal dosimetry). It reports the significant events related to safety and radiation protection which occurred in 2012 and were declared to the ASN. It reports and comments the results of measurements of gaseous and liquid effluents, of their impact on the environment, and of surveys of the environment. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. Remarks and recommendations of the CHSCT are given

Mutation of Asn28 Disrupts the Dimerization and Enzymatic Activity of SARS 3CL

Energy Technology Data Exchange (ETDEWEB)

Barrila, J.; Gabelli, S; Bacha, U; Amzel, M; Freire, E

2010-01-01

Coronaviruses are responsible for a significant proportion of annual respiratory and enteric infections in humans and other mammals. The most prominent of these viruses is the severe acute respiratory syndrome coronavirus (SARS-CoV) which causes acute respiratory and gastrointestinal infection in humans. The coronavirus main protease, 3CL{sup pro}, is a key target for broad-spectrum antiviral development because of its critical role in viral maturation and high degree of structural conservation among coronaviruses. Dimerization is an indispensable requirement for the function of SARS 3CL{sup pro} and is regulated through mechanisms involving both direct and long-range interactions in the enzyme. While many of the binding interactions at the dimerization interface have been extensively studied, those that are important for long-range control are not well-understood. Characterization of these dimerization mechanisms is important for the structure-based design of new treatments targeting coronavirus-based infections. Here we report that Asn28, a residue 11 {angstrom} from the closest residue in the opposing monomer, is essential for the enzymatic activity and dimerization of SARS 3CLpro. Mutation of this residue to alanine almost completely inactivates the enzyme and results in a 19.2-fold decrease in the dimerization K{sub d}. The crystallographic structure of the N28A mutant determined at 2.35 {angstrom} resolution reveals the critical role of Asn28 in maintaining the structural integrity of the active site and in orienting key residues involved in binding at the dimer interface and substrate catalysis. These findings provide deeper insight into complex mechanisms regulating the activity and dimerization of SARS 3CL{sup pro}.

Safety assessment of Olkiluoto NPP units 1 and 2. Decision of the Radiation and Nuclear Safety Authority regarding the periodic safety review of the Olkiluoto NPP

International Nuclear Information System (INIS)

2010-02-01

In this safety assessment the Radiation and Nuclear Safety Authority (STUK) has evaluated the safety of the Olkiluoto Nuclear Power Plant units 1 and 2 in connection with the periodic safety review. This safety assessment provides a summary of the reviews, inspections and continuous oversight carried out by STUK. The issues addressed in the assessment and the related evaluation criteria are set forth in the nuclear energy and radiation safety legislation and the regulations issued thereunder. The provisions of the Nuclear Energy Act concerning the safe use of nuclear energy, security and emergency preparedness arrangements, and waste management are specified in more detail in the Government Decrees and Regulatory Guides issued by STUK. Based on the assessment, STUK consideres that the Olkiluoto Nuclear Power Plant units 1 and 2 meet the set safety requirements for operational nuclear power plants, the emergency preparedness arrangements are sufficient and the necessary control to prevent the proliferation of nuclear weapons has been appropriately arranged. The physical protection of the Olkiluoto nuclear power plant is not yet completely in compliance with the requirements of Government Decree 734/2008, which came into force in December 2008. Further requirements concerning this issue based also on the principle of continuous improvement were included in the decision relating to the periodic safety review. The safety of the Olkiluoto nuclear power plant was assessed in compliance with the Government Decree on the Safety of Nuclear Power Plants (733/2008), which came into force in 2008. The decree notes that existing nuclear power plants need not meet all the requirements set out for new plants. Most of the design bases pertaining to the Olkiluoto 1 and 2 nuclear power plant units were set in the 1970s. Substantial modernisations have been carried out at the Olkiluoto 1 and 2 nuclear power plant units since their commissioning to improve safety. This is in line with

To make files of projects of some non-noticeable modifications of base nuclear installations (INB) available to the public

International Nuclear Information System (INIS)

Vial, Eugenie

2013-01-01

As the French Nuclear Safety Authority (ASN) published a decision related to the availability to the public of files of projects of modifications as specified in the French Code of the Environment, the author proposes an analysis of this decision. He discusses its scope of application within a legal and regulatory context at the crossroad of nuclear and environmental issues, and indicates the procedures concerned by this decision. He outlines the content of the files which the operator must transmit to the ASN: the modification request file, the public availability file. He indicates the operations which must be performed prior to public availability, the content of the notice of availability, and the conditions of information of the local information commission (CLI) and of the advert of public availability. He presents the various operations to be performed after the public availability

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

International Nuclear Information System (INIS)

Cottrell, W.B.; Passiakos, M.

1982-06-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index

Index to Nuclear Safety: a technical progress review by chronology, permuted title, and author, Volume 18 (1) through Volume 22 (6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Passiakos, M.

1982-06-01

This index to Nuclear Safety covers articles published in Nuclear Safety, Volume 18, Number 1 (January-February 1977) through Volume 22, Number 6 (November-December 1981). The index is divided into three section: a chronological list of articles (including abstracts), a permuted-title (KWIC) index, and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. Over 300 technical articles published in Nuclear Safety in the last 5 years are listed in this index.

Synthesis of the IRSN report on its analysis of the safety guidance package (DOrS) of the ASTRID reactor project. Safety guidance document for the ASTRID prototype: Referral to the GPR. Opinion related to the safety guidance document of the ASTRID reactor project. ASTRID prototype: Safety guidance document for the ASTRID prototype

International Nuclear Information System (INIS)

Lachaume, Jean-Luc; Niel, Jean-Christophe

2013-01-01

A first document indicates the improvement guidelines for the ASTRID project based on the French experience in the field of sodium-cooled fast neutron reactors, addresses the safety objectives as they are presented for the ASTRID project, discusses how the project includes a regulation and design referential, and how it addresses various aspects of the design approach (ranking and analysis of operation situations, defence in depth, use of probabilistic studies, safety classification and qualification to accidental situations, taking internal and external aggressions into account and taking severe accidents into account at the design level). It comments the guidelines related to the first two barriers, to main safety functions (control of reactivity and of reactor cooling, containment of radioactive and toxic materials), to dismantling, to R and D for safety support. A second document is a letter sent by the ASN to the GPR (permanent group of experts in charge of nuclear reactors) about the safety guidance document for the ASTRID prototype. The third document is the answer and contains comments and recommendations by this group about the content of this document, and therefore addresses the same topics as the first document. The last document defines the framework of the approach to this document

International relations

International Nuclear Information System (INIS)

Anon.

2009-01-01

The French nuclear safety authority (A.S.N.) has participated at different meeting in European Union as nuclear decommissioning assistance programme(N.D.A.P.), Regulatory assistance management group (R.A.M.G.) and Instrument for nuclear safety cooperation (I.N.S.C.). The members of Western European nuclear regulator association (W.E.N.R.A.) met and discussed about the future of W.E.N.R.A. and its representativeness and its cooperation with European nuclear safety regulator group (E.N.S.R.E.G.) and head of European radiation control authorities (H.E.R.C.A.). About International relations it is to noticed a meeting at the invitation of IAEA to discuss about the possibility to resort to the Ines scale for medical events. An audit mission under the IAEA aegis stood at Fessenheim, O.S.A.R.T. for operational safety review team. Two years and a half passed by between the audit mission Integrated regulatory review service (I.R.S.S.) welcome by A.S.N. in november 2006 and the audit mission follow up in 2009, 12 experts from 11 different countries and coordinated by three representatives of IAEA worked, the conclusions were that 90% of recommendations made to A.S.N. in 2006 were treated in a satisfying way; the evaluation gives three new recommendations, 7 new suggestions and 11 new correct practices. A meeting of the commission on safety standards (C.S.S.) stood in april 2009. Some others meeting are to be noticed: nuclear safety and security group (N.S.S.G.), expert group on nuclear and radiation safety (E.G.N.R.S.) instituted by the council of the Baltic sea states (C.B.S.S.) treats data exchange on the national networks of dose rates and surveillance of radioactivity in air. International nuclear regulator association (I.N.R.A.) held its first meeting in april 2009 at Seoul (Korea). Bilateral relations with Poland, Italy, Ukraine and Germany planed cooperation or information exchange in the field of nuclear safety. Participation to conference in Usa, meetings with United

Needs, requirements and challenges for technical support to nuclear safety authority

International Nuclear Information System (INIS)

Madonna, A.; Orsini, G.

2010-01-01

To face the very broad range of technical matters on which the regulatory and licensing activity are based, and related research and development activity, the Nuclear Safety Authorities (NSA) may need to rely upon external technical and scientific support. In providing technical support to NSA, the experience shows, from one side, the importance to have technical support organizations (TSO) with recognized competence, independence and appropriate regulatory view, and from the other side, the importance to have within the NSAs well developed management and technical capability to address, coordinate and use the results of the external technical support. Retaining the NSA the full responsibility for the final decision. Under which conditions and modus operandi the external support shall be provided in order to comply with requirements of being independent, competent and timely provided, fulfilling the administrative procedures, is the subject of attention and consideration of TSO function today. The Italian regulatory body is currently going to be institutionally re-established according to new law approved in 2009 /1/ and it needs to be resourced and fully organized with necessary capacities in the nearest future. The perspective of a new nuclear program, recently launched by the government, with significant incoming tasks for regulation and licensing, against the existing limited resources, let foresee a substantial potential need for technical support and advice. ITER-Consult (Ltd), created in 2003 in Italy, has well developed capabilities to provide independent technical evaluation and support to NSAs, to maintain safety culture and updated knowledge, to transfer know how and to establish international cooperation and networking. This mission is guided assuming as values the independence, the professional competence, the transparency, the credibility and the establishment of respectful relationship with the partners. Challenges exist for funding and operational

Characterization of deamidation at Asn138 in L-chain of recombinant humanized Fab expressed from Pichia pastoris.

Science.gov (United States)

Ohkuri, Takatoshi; Murase, Eri; Sun, Shu-Lan; Sugitani, Jun; Ueda, Tadashi

2013-10-01

A method was previously established for evaluating Asn deamidation by matrix-assisted laser desorption/ionization time of flight-mass spectrometry using endoproteinase Asp-N. In this study, we demonstrated that this method could be applied to the identification of the deamidation site of the humanized fragment antigen-binding (Fab). First, a system for expressing humanized Fab from methylotrophic yeast Pichia pastoris was constructed, resulting in the preparation of ∼30 mg of the purified humanized Fab from 1 l culture. Analysis of the L-chain derived from recombinant humanized Fab that was heated at pH 7 and 100°C for 1 h showed the deamidation at Asn138 in the constant region. Then, we prepared L-N138D Fab and L-N138A Fab and examined their properties. The circular dichroism (CD) spectrum of the L-N138D Fab was partially different from that of the wild-type Fab. The measurement of the thermostability showed that L-N138D caused a significant decrease in the thermostability of Fab. On the other hand, the CD spectrum and thermostability of L-N138A Fab showed the same behaviour as the wild-type Fab. Thus, it was suggested that the introduction of a negative charge at position 138 in the L-chain by the deamidation significantly affected the stability of humanized Fab.

Role of supervising authorities in NPP operation safety ensuring

International Nuclear Information System (INIS)

Elagin, Yu.P.

2001-01-01

The main working spheres and results gained during 40 years of activity of the Great Britain Nuclear Installation Inspectorate (NII) are considered. The new approach to safety analysis developed with NII participation is described in details. The important role of the safety analysis realization, utilization of modern methods for risk estimation and safety culture principles introduction at NPPs is shown [ru

Index to Nuclear Safety: a technical progress review by chrology, permuted title, and author, Volume 11(1) through Volume 20(6)

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W B; Passiakos, M

1980-06-01

This index to Nuclear Safety, a bimonthly technical progress review, covers articles published in Nuclear Safety, Volume II, No. 1 (January-February 1970), through Volume 20, No. 6 (November-December 1979). It is divided into three sections: a chronological list of articles (including abstracts) followed by a permuted-title (KWIC) index and an author index. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center (NSIC), covers all safety aspects of nuclear power reactors and associated facilities. Over 600 technical articles published in Nuclear Safety in the last ten years are listed in this index.

Quality systems for radiotherapy: Impact by a central authority for improved accuracy, safety and accident prevention

International Nuclear Information System (INIS)

Jaervinen, H.; Sipilae, P.; Parkkinen, R.; Kosunen, A.; Jokelainen, I.

2001-01-01

High accuracy in radiotherapy is required for the good outcome of the treatments, which in turn implies the need to develop comprehensive Quality Systems for the operation of the clinic. The legal requirements as well as the recommendation by professional societies support this modern approach for improved accuracy, safety and accident prevention. The actions of a national radiation protection authority can play an important role in this development. In this paper, the actions of the authority in Finland (STUK) for the control of the implementation of the new requirements are reviewed. It is concluded that the role of the authorities should not be limited to simple control actions, but comprehensive practical support for the development of the Quality Systems should be provided. (author)

Additional safety assessments. Report by the Nuclear Safety Authority - December 2011

International Nuclear Information System (INIS)

2011-12-01

The first part of this voluminous report proposes an assessment of targeted audits performed in French nuclear installations (water pressurized reactors on the one hand, laboratories, factories and waste and dismantling installations on the other hand) on issues related to the Fukushima accident. The examined issues were the protection against flooding and against earthquake, and the loss of electricity supplies and of cooling sources. The second part addresses the additional safety assessments of the reactors and the European resistance tests: presentation of the French electronuclear stock, earthquake, flooding and natural hazards (installation sizing, safety margin assessment), loss of electricity supplies and cooling systems, management of severe accidents, subcontracting conditions. The third part addresses the same issues for nuclear installations other than nuclear power reactors

Protein changes associated with reprotonation of the Schiff base in the photocycle of Asp96-->Asn bacteriorhodopsin. The MN intermediate with unprotonated Schiff base but N-like protein structure

Science.gov (United States)

Sasaki, J.; Shichida, Y.; Lanyi, J. K.; Maeda, A.

1992-01-01

The difference Fourier transform infrared spectrum for the N intermediate in the photoreaction of the light-adapted form of bacteriorhodopsin can be recorded at pH 10 at 274 K (Pfefferle, J.-M., Maeda, A., Sasaki, J., and Yoshizawa, T. (1991) Biochemistry 30, 6548-6556). Under these conditions, Asp96-->Asn bacteriorhodopsin gives a photoproduct which shows changes in protein structure similar to those observed in N of wild-type bacteriorhodopsin. However, decreased intensity of the chromophore bands and the single absorbance maximum at about 400 nm indicate that the Schiff base is unprotonated, as in the M intermediate. This photoproduct was named MN. At pH 7, where the supply of proton is not as restricted as at pH 10, Asp96-->Asn bacteriorhodopsin yields N with a protonated Schiff base. The Asn96 residue, which cannot deprotonate as Asp96 in wild-type bacteriorhodopsin, is perturbed upon formation of both MN at pH 10 and N at pH 7. We suggest that the reprotonation of the Schiff base is preceded by a large change in the protein structure including perturbation of the residue at position 96.

Purification, crystallization and preliminary X-ray crystallographic analysis of ST1022, a putative member of the Lrp/AsnC family of transcriptional regulators isolated from Sulfolobus tokodaii strain 7

Energy Technology Data Exchange (ETDEWEB)

Nakano, Noboru; Kumarevel, Thirumananseri, E-mail: tskvel@spring8.or.jp; Matsunaga, Emiko; Shinkai, Akeo [RIKEN SPring-8 Center, Harima Institute, 1-1-1 Kouto, Sayo, Hyogo 679-5148 (Japan); Kuramitsu, Seiki [RIKEN SPring-8 Center, Harima Institute, 1-1-1 Kouto, Sayo, Hyogo 679-5148 (Japan); Department of Biological Sciences, Graduate School of Science, Osaka University, Tayonaka, Osaka 560-0043 (Japan); Yokoyama, Shigeyuki, E-mail: tskvel@spring8.or.jp [RIKEN SPring-8 Center, Harima Institute, 1-1-1 Kouto, Sayo, Hyogo 679-5148 (Japan); Genomic Sciences Center, Yokohama Institute, RIKEN, 1-7-22 Suehiro-cho, Tsurumi, Yokohama 230-0045 (Japan); Department of Biophysics and Biochemistry, Graduate School of Science, The University of Tokyo, 7-3-1 Hongo, Bunkyo-ku, Tokyo 113-0033 (Japan)

2007-11-01

A putative member of the Lrp/AsnC family of transcriptional regulators, ST1022 from S. tokodaii strain 7, has been purified and crystallized in the absence and presence of the effector l-glutamine. A molecular-replacement solution was found using the FL11 transcriptional regulator from Pyrococcus sp. OT3 as a model and structural refinement is under way. The Lrp/AsnC family of transcriptional regulators, also known as feast/famine transcriptional regulators, are widely distributed among bacteria and archaea. This family of proteins are likely to be involved in cellular metabolism, with exogenous amino acids functioning as effectors. Here, the crystallization and preliminary X-ray diffraction analysis of ST1022, a member of the Lrp/AsnC family of proteins, is reported with and without exogenous glutamine as the effector molecule. The crystals of native ST1022 and of the putative complex belong to the tetragonal space group I422, with unit-cell parameters a = b = 103.771, c = 73.297 Å and a = b = 103.846, c = 73.992 Å, respectively. Preliminary X-ray diffraction data analysis and molecular-replacement solution revealed the presence of one monomer per asymmetric unit.

Purification, crystallization and preliminary X-ray crystallographic analysis of ST1022, a putative member of the Lrp/AsnC family of transcriptional regulators isolated from Sulfolobus tokodaii strain 7

International Nuclear Information System (INIS)

Nakano, Noboru; Kumarevel, Thirumananseri; Matsunaga, Emiko; Shinkai, Akeo; Kuramitsu, Seiki; Yokoyama, Shigeyuki

2007-01-01

A putative member of the Lrp/AsnC family of transcriptional regulators, ST1022 from S. tokodaii strain 7, has been purified and crystallized in the absence and presence of the effector l-glutamine. A molecular-replacement solution was found using the FL11 transcriptional regulator from Pyrococcus sp. OT3 as a model and structural refinement is under way. The Lrp/AsnC family of transcriptional regulators, also known as feast/famine transcriptional regulators, are widely distributed among bacteria and archaea. This family of proteins are likely to be involved in cellular metabolism, with exogenous amino acids functioning as effectors. Here, the crystallization and preliminary X-ray diffraction analysis of ST1022, a member of the Lrp/AsnC family of proteins, is reported with and without exogenous glutamine as the effector molecule. The crystals of native ST1022 and of the putative complex belong to the tetragonal space group I422, with unit-cell parameters a = b = 103.771, c = 73.297 Å and a = b = 103.846, c = 73.992 Å, respectively. Preliminary X-ray diffraction data analysis and molecular-replacement solution revealed the presence of one monomer per asymmetric unit

Reports by the Parliamentary Office for scientific and technological assessments. Thursday, April 14, 2011. Information on the Fukushima accident by Mr Thomas Houdre, Nuclear plant manager by the Nuclear Safety Authority. Nuclear safety, the role and future of the sector - Presentation of the feasibility study; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 14 avril 2011. Point d'information sur l'accident de Fukushima par M. Thomas Houdre, directeur des centrales nucleaires de l'Autorite de Surete Nucleaire. Securite nucleaire, place de la filiere et son avenir - Presentation de l'etude de faisabilite

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-04-15

In a first part, a representative of the ASN describes the situation of the Fukushima Daiichi nuclear power station about one month after the accident. He reports the phenomena which have occurred, gives some explanations, compares this accident with that of Chernobyl. The second part is a discussion about the content and the organization of a parliamentary mission which aims at investigating nuclear safety, and the role and future of the nuclear sector

Report on nuclear safety and transparency 2011 - Saclay

International Nuclear Information System (INIS)

2012-06-01

After a brief presentation of the Saclay CEA centre, this report indicates the different safety measures related to different risks, to emergency situations, to inspections and audits, and to nuclear base installations (INB). It describes measures related to radiation protection (organisation, personnel dosimetry) and some remarkable facts which occurred in 2011. It presents the different significant events which occurred in 2011 and were declared to the ASN. It discusses the results of measurements of liquid and gaseous releases from the installations and their impact on the environment. It addresses the radioactive wastes which are warehoused on the site (measures to limit their volume and to limit their impact on health and on the environment, notably on water and soils, types and quantities of wastes stored in INBs

Report on nuclear safety and transparency 2011 - Grenoble

International Nuclear Information System (INIS)

2012-06-01

After a brief presentation of the Grenoble CEA centre, this report indicates the different safety measures related to different risks, to emergency situations, to inspections and audits, and to nuclear base installations (INB). It describes measures related to radiation protection organisation and some remarkable facts which occurred in 2011. It presents the different significant events which occurred in 2011 and were declared to the ASN. It discusses the results of measurements of liquid and gaseous releases from the installations and their impact on the environment. It addresses the radioactive wastes which are warehoused on the site (measures to limit their volume and to limit their impact on health and on the environment, notably on water and soils, types and quantities of wastes stored in INBs)

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

International Nuclear Information System (INIS)

Cottrell, W.B.; Klein, A.

1977-01-01

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1--Vol. 17, No. 6

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Klein, A.

1977-02-23

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970), through Vol. 17, No. 6 (Nov.-Dec. 1976). The index includes a chronological list of articles (including abstract) followed by KWIC and Author Indexes. Nuclear Safety, a bimonthly technical progress review prepared by the Nuclear Safety Information Center, covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 350 technical articles in the last six years of publication.

Characterization of an Lrp/AsnC family regulator SCO3361, controlling actinorhodin production and morphological development in Streptomyces coelicolor.

Science.gov (United States)

Liu, Jing; Li, Jie; Dong, Hong; Chen, Yunfu; Wang, Yansheng; Wu, Hang; Li, Changrun; Weaver, David T; Zhang, Lixin; Zhang, Buchang

2017-07-01

Lrp/AsnC family regulators have been found in many bacteria as crucial regulators controlling diverse cellular processes. By genomic alignment, we found that SCO3361, an Lrp/AsnC family protein from Streptomyces coelicolor, shared the highest similarity to the SACE_Lrp from Saccharopolyspora erythraea. Deletion of SCO3361 led to dramatic reduction in actinorhodin (Act) production and delay in aerial mycelium formation and sporulation on solid media. Dissection of the mechanism underlying the function of SCO3361 in Act production revealed that it altered the transcription of the cluster-situated regulator gene actII-ORF4 by directly binding to its promoter. SCO3361 was an auto-regulator and simultaneously activated the transcription of its adjacent divergently transcribed gene SCO3362. SCO3361 affected aerial hyphae formation and sporulation of S. coelicolor by activating the expression of amfC, whiB, and ssgB. Phenylalanine and cysteine were identified as the effector molecules of SCO3361, with phenylalanine reducing the binding affinity, whereas cysteine increasing it. Moreover, interactional regulation between SCO3361 and SACE_Lrp was discovered for binding to each other's target gene promoter in this work. Our findings indicate that SCO3361 functions as a pleiotropic regulator controlling secondary metabolism and morphological development in S. coelicolor.

Radiation Authority and Nuclear Safety in Finland (STUK); La autoridad de Radiacion y Seguridad Nuclear de Finlandia (STUK)

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-07-01

Created in 1958 as an institute in charge of inspecting radioactive equipment used in hospitals, STUK is nowadays a specialised organisation whose functions cover all fields for applying radiation and nuclear safety. (Author)

Action taken by the french safety authorities for fire protection and fire fighting in basic nuclear plants

International Nuclear Information System (INIS)

Savornin, J.; Gibault, M.; Berger, R.; Kaluzny, Y.; Wallard, H.E.; Winter, D.

1989-03-01

The safety goal for nuclear installations is to prevent the dispersal of radioactive substances, both in the work area and outside the buildings into the environment. It is therefore at the design stage, then during construction and subsequent operation that it is necessary to take preventive measures against the outbreak of fire, and to take precautions to ensure that the consequences will always be limited. The paper describes the arrangements made by the French safety authorities to provide protection against fire in both nuclear plants and nuclear fuel cycle installations at all these stages

Safety Evaluation Report on Tennessee Valley Authority: Browns Ferry Nuclear Performance Plan: Browns Ferry Unit 2 restart

International Nuclear Information System (INIS)

1989-04-01

This safety evaluation report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Nuclear Performance Plan, through Revision 2, for the Browns Ferry Nuclear Power Station and in supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific concerns requiring resolution before startup of Unit 2. The staff will inspect implementation of those programs. Where systems are common to Units 1 and 2 or to Units 2 and 3, the staff safety evaluations of those systems are included herein. 3 refs

Report on transparency and nuclear safety 2014 - Cadarache CEA centre

International Nuclear Information System (INIS)

2015-07-01

This document proposes, first, a presentation of the Cadarache CEA centre, of its activities and installations, gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. Then it reports significant events related to safety and to radiation protection which occurred in 2014 and have been declared to the ASN. Next, it discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. Finally, it addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre, indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and on the environment. Nature and quantities of warehoused wastes are specified. Remarks and recommendations of the CHSCT are given

Nuclear safety

International Nuclear Information System (INIS)

Tarride, Bruno

2015-10-01

The author proposes an overview of methods and concepts used in the nuclear industry, at the design level as well as at the exploitation level, to ensure an acceptable safety level, notably in the case of nuclear reactors. He first addresses the general objectives of nuclear safety and the notion of acceptable risk: definition and organisation of nuclear safety (relationships between safety authorities and operators), notion of acceptable risk, deterministic safety approach and main safety principles (safety functions and confinement barriers, concept of defence in depth). Then, the author addresses the safety approach at the design level: studies of operational situations, studies of internal and external aggressions, safety report, design principles for important-for-safety systems (failure criterion, redundancy, failure prevention, safety classification). The next part addresses safety during exploitation and general exploitation rules: definition of the operation domain and of its limits, periodic controls and tests, management in case of incidents, accidents or aggressions

The Flamanville 3 EPR reactor; Le reacteur EPR Flamanville 3

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

On April 10. 2007, the french government authorized EDF to create on the site of Flamanville ( La Manche) a nuclear base installation containing a pressurized water EPR type reactor. This nuclear reactor, conceived by AREVA NP and EDF, is the first copy of a generation susceptible to replace later, at least partly, the French nuclear reactors at present in operation.Within the framework of its mission of technical support of the Authority of Nuclear Safety ( A.S.N.), the I.R.S.N. widely contributed successively: to define the general objectives of safety assigned to this new generation of pressurized water nuclear reactors; to analyze the options of safety proposed by EDF for the EPR project; To deepen, upstream to the authorization of creation, the evaluation of the step of safety and the measures of conception retained by EDF that have to allow to respect the objectives of safety which were notified to it. (N.C.)

Scientific Method and the Regulation of Health and Nutritional Claims by the European Food Safety Authority

Science.gov (United States)

Hoad, Darren

2011-01-01

The protection of European consumers from the false or misleading scientific and nutritional claims of food manufacturers took a step forward with the recent opinions of the European Food Safety Authority (EFSA). As a risk assessment agency, the EFSA recently assessed and rejected a vast number of food claim forcing the withdrawal of many claims…

Regulation imposed to nuclear facility operators for the elaboration of 'waste studies' and 'waste statuses'

International Nuclear Information System (INIS)

2001-01-01

This decision from the French authority of nuclear safety (ASN) aims at validating the new versions of the guidebook for the elaboration of 'waste studies' for nuclear facilities and of the specifications for the elaboration of 'waste statuses' for nuclear facilities. This paper includes two documents. The first one is a guidebook devoted to nuclear facility operators which fixes the rules of production of waste studies according to the articles 20 to 26 of the inter-ministry by-law from December 31, 1999 (waste zoning conditions and ASN's control modalities). The second document concerns the specifications for the establishment of annual waste statuses according to article 27 of the inter-ministry by-law from December 31, 1999 (rational management of nuclear wastes). (J.S.)

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

Application of the INES scale to the transport of radioactive materials

International Nuclear Information System (INIS)

2001-01-01

This decision from the French authority of nuclear safety (ASN) concerns the application of the international nuclear event scale (INES) to the incidents and accidents occurring during the transport of radioactive materials. Only the off-site impacts and defense-in-depth degradation aspects are taken into account in the INES-transportation scale. A proposal of classification grid is given for both aspects. (J.S.)

Organization of public authorities in France for the event of an incident or accident involving nuclear safety: Simulation of a nuclear crisis

International Nuclear Information System (INIS)

Cartigny, J.; Majorel, Y.

1986-01-01

The French nuclear safety regulations lay down the action to be taken in the event of an incident or accident involving the types of radiological hazard that could arise in a nuclear installation or during the transport of radioactive material. The organization established for this purpose is designed to ensure that the technical measures taken by the authorities responsible for nuclear safety, radiation protection, public order and public safety are fully effective. The Interministerial Nuclear Safety Committee (Comite interministeriel de la securite nucleaire), which reports to the Prime Minister, co-ordinates the measures taken by the public authorities. The public authorities and the operators together organize exercises designed to verify the whole complex of measures foreseen in the event of an incident or accident. These exercises, which have been carried out in a systematic manner in France for some years, are based on scenarios which are as realistic as possible and enable the following objectives to be achieved: (1) analysis of the crisis apparatus (ORSECRAD plans, individual intervention plans, information conventions); (2) uncovering gaps or inadequacies; (3) arrangements for interchange of information between the various participants whose responsibilities involve them in the emergency; and (4) allowance for the information requirements of the media and the population. The information drawn from these exercises enables the various procedures to be improved step by step. (author)

Efficacy and safety testing of mycotoxin-detoxifying agents in broilers following the European Food Safety Authority guidelines.

Science.gov (United States)

Osselaere, A; Devreese, M; Watteyn, A; Vandenbroucke, V; Goossens, J; Hautekiet, V; Eeckhout, M; De Saeger, S; De Baere, S; De Backer, P; Croubels, S

2012-08-01

Contamination of feeds with mycotoxins is a worldwide problem and mycotoxin-detoxifying agents are used to decrease their negative effect. The European Food Safety Authority recently stated guidelines and end-points for the efficacy testing of detoxifiers. Our study revealed that plasma concentrations of deoxynivalenol and deepoxy-deoxynivalenol were too low to assess efficacy of 2 commercially available mycotoxin-detoxifying agents against deoxynivalenol after 3 wk of continuous feeding of this mycotoxin at concentrations of 2.44±0.70 mg/kg of feed and 7.54±2.20 mg/kg of feed in broilers. This correlates with the poor absorption of deoxynivalenol in poultry. A safety study with 2 commercially available detoxifying agents and veterinary drugs showed innovative results with regard to the pharmacokinetics of 2 antibiotics after oral dosing in the drinking water. The plasma and kidney tissue concentrations of oxytetracycline were significantly higher in broilers receiving a biotransforming agent in the feed compared with control birds. For amoxicillin, the plasma concentrations were significantly higher for broilers receiving an adsorbing agent in comparison to birds receiving the biotransforming agent, but not to the control group. Mycotoxin-detoxifying agents can thus interact with the oral bioavailability of antibiotics depending on the antibiotic and detoxifying agent, with possible adverse effects on the health of animals and humans.

Report on transparency and nuclear safety - Cadarache CEA centre - 2012

International Nuclear Information System (INIS)

2013-01-01

A first volume proposes a presentation of the Cadarache CEA centre, of its activities and installations, gives a rather detailed overview of measures related to safety and to radiation protection within these activities and installations. It also reports significant events related to safety and to radiation protection which occurred in 2012 and have been declared to the ASN. It discusses the results of release measurements (liquid and gaseous effluents, radiological assessment, and chemical assessment for various installations) and the control of the chemical and radiological impact of these gaseous and liquid effluents on the environment. It addresses the issue of radioactive wastes which are stored in the different nuclear base installations of the Centre, indicates the different measures aimed at limiting the volume of these warehoused wastes and addresses their impact on health and on the environment. Nature and quantities of warehoused wastes are specified. The second volume concerns some specific installations (INB 32 or ATPu, and INB 54 or LPC) which belong to AREVA NC. The same topics are addressed: presentation of the facilities, arrangements regarding safety and radiation protection, significant events related to safety and radiation protection, measurements of effluents and their impact on the environment, warehoused wastes. Remarks and recommendations of the CHSCT are given

Ser95, Asn97, and Thr78 are important for the catalytic function of porcine NADP-dependent isocitrate dehydrogenase

OpenAIRE

Kim, Tae-Kang; Colman, Roberta F.

2005-01-01

The mammalian mitochondrial NADP-dependent isocitrate dehydrogenase is a citric acid cycle enzyme and an important contributor to cellular defense against oxidative stress. The Mn2+-isocitrate complex of the porcine enzyme was recently crystallized; its structure indicates that Ser95, Asn97, and Thr78 are within hydrogen-bonding distance of the γ-carboxylate of enzyme-bound isocitrate. We used site-directed mutagenesis to replace each of these residues by Ala and Asp. The wild-type and mutant...

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2007. Annual report

International Nuclear Information System (INIS)

2007-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2007 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) Abbreviations

Reports by the Parliamentary Office for scientific and technological assessment. Wednesday, March 16, 2011. Nuclear crisis in Japan - Round table; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Mercredi 16 mars 2011. Crise nucleaire au Japon - Table ronde

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-03-15

A round table brought together members of the French national Assembly and Senate, the French ministers of ecology and of industry, the chairmen of the Nuclear Safety Authority (ASN), of the OECD agency for nuclear energy, of AREVA, of EDF and of the High Committee for transparency and information on nuclear safety, and representatives of the IRSN and of the CEA. Three main topics have been addressed: the present technical configuration of the Fukushima site, the situation at the vicinity of the power station and on the whole Japanese territory, and the possible evolution scenarios

Drug packaging in 2014: authorities should direct more efforts towards medication safety.

Science.gov (United States)

2015-05-01

In 2014, Prescrire examined the packaging quality of about 250 drugs. A few advances stand out, mainly involving recent drugs, but on the whole, the situation is worrisome in terms of medication safety. Although pharmaceutical companies and drug regulatory agencies seem to be taking more account of the risk of accidental poisoning in children, the level of protection remains low overall in the absence of stringent measures on the part of the authorities. New drugs too often have poor-quality or even dangerous packaging at the time of their market introduction. And the packaging quality of older drugs is disturbing. Pharmaceutical companies no longer invest in the packaging of these products, and agencies often fail to take advantage of the opportunities provided by their reassessment to improve the situation. The inappropriate labelling of certain injectable drugs remains a source of medication errors, sometimes resulting in very serious consequences. In 2014, signs of progress in the packaging of several drugs show that its role in medication safety is better appreciated. But the persistence of dangers in the pharmaceuticals market, created by "unfinished", overly complex or poor-quality packaging, raises the question of the responsibility of pharmaceutical companies and agencies for past and present accidents.

Safety Evaluation report on Tennessee Valley Authority: Sequoyah nuclear performance plan

International Nuclear Information System (INIS)

1988-05-01

This Safety Evaluation Report (SER) on the information submitted by the Tennessee Valley Authority (TVA) in its Sequoyah Nuclear Performance Plan, through Revision 2, and supporting documents has been prepared by the US Nuclear Regulatory Commission staff. The plan addresses the plant-specific concerns requiring resolution before startup of either of the Sequoyah units. In particular, the SER addresses required actions for Unit 2 restart. In many cases, the programmatic aspects for Unit 1 are identical to those for Unit 2; the staff will conduct inspections of implementation of those programs. Where the Unit 1 program is different, the staff evaluation will be provided in a supplement to this SER. On the basis of its review, the staff concludes that Sequoyah-specific issues have been resolved to the extent that would support restart of Sequoyah Unit 2

State Regulatory Authority (SRA) Coordination of Safety, Security, and Safeguards of Nuclear Facilities: A Framework for Analysis

International Nuclear Information System (INIS)

Mladineo, S.; Frazar, S.; Kurzrok, A.; Martikka, E.; Hack, T.; Wiander, T.

2013-01-01

In November 2012 the International Atomic Energy Agency (IAEA) sponsored a Technical Meeting on the Interfaces and Synergies in Safety, Security, and Safeguards for the Development of a Nuclear Power Program. The goal of the meeting was to explore whether and how safeguards, safety, and security systems could be coordinated or integrated to support more effective and efficient nonproliferation infrastructures. While no clear consensus emerged, participants identified practical challenges to and opportunities for integrating the three disciplines’ regulations and implementation activities. Simultaneously, participants also recognized that independent implementation of safeguards, safety, and security systems may be more effective or efficient at times. This paper will explore the development of a framework for conducting an assessment of safety-security-safeguards integration within a State. The goal is to examine State regulatory structures to identify conflicts and gaps that hinder management of the three disciplines at nuclear facilities. Such an analysis could be performed by a State Regulatory Authority (SRA) to provide a self-assessment or as part of technical cooperation either with a newcomer State, or to a State with a fully developed SRA.

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol 11, No. 1 through Vol. 16, No. 6

International Nuclear Information System (INIS)

Cottrell, W.B.; Klein, A.

1976-04-01

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970) through Vol. 16, No. 6 (Nov.-Dec. 1975). Included in the index is a chronological list of articles (including abstract) followed by both a KWIC index and an Author Index. Nuclear Safety is a bimonthly technical progress review prepared by the Nuclear Safety Information Center and covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 300 technical articles in the last six years of publication

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol 11, No. 1 through Vol. 16, No. 6

Energy Technology Data Exchange (ETDEWEB)

Cottrell, W.B.; Klein, A.

1976-04-01

This index to Nuclear Safety covers articles in Nuclear Safety Vol. 11, No. 1 (Jan.-Feb. 1970) through Vol. 16, No. 6 (Nov.-Dec. 1975). Included in the index is a chronological list of articles (including abstract) followed by both a KWIC index and an Author Index. Nuclear Safety is a bimonthly technical progress review prepared by the Nuclear Safety Information Center and covers all safety aspects of nuclear power reactors and associated facilities. The index lists over 300 technical articles in the last six years of publication.

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

International Nuclear Information System (INIS)

2007-01-01

stipulations of the present Convention. This report was produced by ASN, the French nuclear safety authority, which coordinated the work on it, with contributions from IRSN (Institute for Radiation Protection and Nuclear Safety) and from nuclear reactor licensees, Electricite de France (EDF), the Atomic Energy Commission (CEA) and the Laue-Langevin institute (ILL). The final version was completed in July 2007 after consultation with the French parties concerned. For this report, France has taken account of the experience acquired with the three previous editions: it is a stand-alone report based mainly on existing documents and reflecting the viewpoints of the various stakeholders (regulatory authority and licensees). Thus, for each of the chapters in which the regulatory authority is not the only party to express its point of view, a three-part structure has been adopted: first a description of the regulations by the regulatory authority, followed by a presentation by the licensees of the steps taken to comply with the regulations, and finally an analysis by the regulatory authority of the steps taken by the licensees. The report is structured according to the guidelines for national reports, as modified during the 2002 peer review meeting. The presentation is made 'article by article', each being the subject of a separate chapter, at the beginning of which the corresponding text of the Convention article is reproduced in a shadow box. This introduction presents the main changes since the third national report and France's nuclear power policy. Part A deals with the general provisions (articles 4 to 6). Part B summarises the legislation and regulations (articles 7 to 9). Part C is devoted to general safety considerations (articles 10 to 16). Part D discusses the safety of the installations (articles 17 to 19). The conclusion outlines future trends in the field of nuclear safety in France, including measures for international cooperation. The report is supplemented by a number

Civilian use transport of radioactive substances on public road. Volume 1: Shipment accreditation and approval requests. Guide Nr 7, Revision 2 of 15 February 2016. Volume 2: safety file of package models, European guide 'Package Design Safety Report'. Civilian use transport of radioactive packages or substances on public road. Volume 3: Compliance of package models not subject to accreditation. Guide Nr 7, Revision 7 of the 2015/11/13

International Nuclear Information System (INIS)

2016-01-01

After having recalled the regulatory context and sanctions susceptible to be applied, the first volume presents the accreditation process for a package model: file content, tests programme, safety file, certification studies, documents to be produced, accreditation prorogation request, accreditation extension or package model modifications, instruction delays. Some peculiar cases are described. Models of accreditation certificate are provided, and obligations concerning packaging design, fabrication, use and maintenance are briefly discussed. The second volume is a European technical guide which is intended to assist in the preparation of the Package Design Safety Report (PDSR) to demonstrate compliance of a package design for the transport of radioactive material with the regulatory requirements. It covers package designs requiring competent authority approval, and also covers package designs not requiring competent authority approval. In its first two chapters, this document provides a generic structure and contents of a PDSR which applies to all package types. The contents are described in a comprehensive way to cover all important aspects. Some of these aspects may not be applicable to specific package type and details can be found in the annexes which provide further guidance for the scope of the contents of a PDSR, specifically for each package type. The third volume presents recommendations made by the ASN for all stakeholders to guarantee the compliance to regulation of package models which are 'not submitted to competent authority approval'. After an indication and a comment of the regulatory context, it presents requirements to be applied for the design of those package models, and then describes and comments the structure and content of a safety file for such package models (generalities, authorised contents, packaging description, safety demonstration, receipt, use and maintenance instruction, management system). The last part presents the

Safety challenges after the Fukushima accident for operated installations others than EDF reactors

International Nuclear Information System (INIS)

Sene, Monique; Rollinger, Francois; Lheureux, Yves; Lizot, Marie-Therese; Kerdelhue, M.; Py, M.E.; Leroyer, Veronique; Pultier, Marc; Kassiotis, Christophe; Chambrette, Pierre; Devaux, Pascal; Baron, Yves; Collinet, Jacques

2013-12-01

This document contains Power Point presentations which, within the perspective created by the Fukushima accident, address various aspects of safety issues for installations other than currently operated EDF reactors. These contributions propose: an agenda of additional safety assessments (ECS) performed on these installations and an examination of responses made to prescriptions made on the 16 June 2012; a presentation by the IRSN of ECS performed in Areva plants; a presentation by Areva of arrangements related to these ECS; a presentation of the Manche local information commissions (CLI) and a presentation of their approach according to a white paper for the safety of civil nuclear installations located in the Manche department; a presentation by the IRSN on ECS concerning various basic nuclear installations such as laboratories, experimental reactors and stopped reactors; a presentation by the CEA of ECS of its installations (context, approach, execution and conclusions); a presentation by the ANCCLI about ASN decision and decision projects about the hard core according to ECS (example of the High flux reactor in the ILL in Grenoble)

Building competence in radiation and nuclear safety through education and training - the approach of a national regulatory authority

International Nuclear Information System (INIS)

Karfopoulos, K.L.; Carinou, E.; Kamenopoulou, V.; Dimitriou, P.; Housiadas, Ch.

2015-01-01

The Greek Atomic Energy Commission (EEAE) is the national competent authority for radiation and nuclear safety and security as well as for the radiation protection of ionizing and artificially produced non-ionizing radiation. The legal framework determines, inter alia, the responsibilities in education and training issues. The EEAE has a range of activities, in providing postgraduate and continuous education and training on radiation protection, and nuclear safety and security, at the national and international levels. At the national level, and particularly in the medical field, the EEAE is a participant in and a major contributor to the Inter-University Postgraduate Program on Medical Radiation Physics. Since 2003, the EEAE has been the Regional Training Center (RTC) for radiation, transport and waste safety of the International Atomic Energy Agency (IAEA) for the European Region in the English language. Moreover, the EEAE has also been recognized as the IAEA's Regional Training Center (RTC) in nuclear security in the English language since 2013. The EEAE recently proceeded to two significant initiatives: the design of a national program for education and training, and the certification of the Department of Education according to ISO 29990:2010. In this paper, the initiatives taken to enhance the radiation protection system in the country through education and training are presented. (authors)

Structure-activity relationships of the unique and potent agouti-related protein (AGRP)-melanocortin chimeric Tyr-c[beta-Asp-His-DPhe-Arg-Trp-Asn-Ala-Phe-Dpr]-Tyr-NH2 peptide template.

Science.gov (United States)

Wilczynski, Andrzej; Wilson, Krista R; Scott, Joseph W; Edison, Arthur S; Haskell-Luevano, Carrie

2005-04-21

The melanocortin receptor system consists of endogenous agonists, antagonists, G-protein coupled receptors, and auxiliary proteins that are involved in the regulation of complex physiological functions such as energy and weight homeostasis, feeding behavior, inflammation, sexual function, pigmentation, and exocrine gland function. Herein, we report the structure-activity relationship (SAR) of a new chimeric hAGRP-melanocortin agonist peptide template Tyr-c[beta-Asp-His-DPhe-Arg-Trp-Asn-Ala-Phe-Dpr]-Tyr-NH(2) that was characterized using amino acids previously reported in other melanocortin agonist templates. Twenty peptides were examined in this study, and six peptides were selected for (1)H NMR and computer-assisted molecular modeling structural analysis. The most notable results include the identification that modification of the chimeric template at the His position with Pro and Phe resulted in ligands that were nM mouse melanocortin-3 receptor (mMC3R) antagonists and nM mouse melanocortin-4 receptor (mMC4R) agonists. The peptides Tyr-c[beta-Asp-His-DPhe-Ala-Trp-Asn-Ala-Phe-Dpr]-Tyr-NH(2) and Tyr-c[beta-Asp-His-DNal(1')-Arg-Trp-Asn-Ala-Phe-Dpr]-Tyr-NH(2) resulted in 730- and 560-fold, respectively, mMC4R versus mMC3R selective agonists that also possessed nM agonist potency at the mMC1R and mMC5R. Structural studies identified a reverse turn occurring in the His-DPhe-Arg-Trp domain, with subtle differences observed that may account for the differences in melanocortin receptor pharmacology. Specifically, a gamma-turn secondary structure involving the DPhe(4) in the central position of the Tyr-c[beta-Asp-Phe-DPhe-Arg-Trp-Asn-Ala-Phe-Dpr]-Tyr-NH(2) peptide may differentiate the mixed mMC3R antagonist and mMC4R agonist pharmacology.

Policy elements for post-accident management in the event of nuclear accident. Document drawn up by the Steering Committee for the Management of the Post-Accident Phase of a Nuclear Accident (CODIRPA). Final version - 5 October 2012

International Nuclear Information System (INIS)

2012-01-01

Pursuant to the Inter-ministerial Directive on the Action of the Public Authorities, dated 7 April 2005, in the face of an event triggering a radiological emergency, the National directorate on nuclear safety and radiation protection (DGSNR), which became the Nuclear safety authority (ASN) in 2006, was tasked with working the relevant Ministerial offices in order to set out the framework and outline, prepare and implement the provisions needed to address post-accident situations arising from a nuclear accident. In June 2005, the ASN set up a Steering committee for the management of the post-accident phase in the event of nuclear accident or a radiological emergency situation (CODIRPA), put in charge of drafting the related policy elements. To carry out its work, CODIRPA set up a number of thematic working groups from 2005 on, involving in total several hundred experts from different backgrounds (local information commissions, associations, elected officials, health agencies, expertise agencies, authorities, etc.). The working groups reports have been published by the ASN. Experiments on the policy elements under construction were carried out at the local level in 2010 across three nuclear sites and several of the neighbouring municipalities, as well as during national crisis drills conducted since 2008. These works gave rise to two international conferences organised by ASN in 2007 and 2011. The policy elements prepared by CODIRPA were drafted in regard to nuclear accidents of medium scale causing short-term radioactive release (less than 24 hours) that might occur at French nuclear facilities equipped with a special intervention plan (PPI). They also apply to actions to be carried out in the event of accidents during the transport of radioactive materials. Following definitions of each stage of a nuclear accident, this document lists the principles selected by CODIRPA to support management efforts subsequent to a nuclear accident. Then, it presents the main

Regulation imposed to nuclear facility operators for the elaboration of 'waste studies' and 'waste statuses'; Reglementation imposee aux exploitants d'installations nucleaires pour l'elaboration ''des etudes dechets'' et ''des bilans dechets''

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-09-04

This decision from the French authority of nuclear safety (ASN) aims at validating the new versions of the guidebook for the elaboration of 'waste studies' for nuclear facilities and of the specifications for the elaboration of 'waste statuses' for nuclear facilities. This paper includes two documents. The first one is a guidebook devoted to nuclear facility operators which fixes the rules of production of waste studies according to the articles 20 to 26 of the inter-ministry by-law from December 31, 1999 (waste zoning conditions and ASN's control modalities). The second document concerns the specifications for the establishment of annual waste statuses according to article 27 of the inter-ministry by-law from December 31, 1999 (rational management of nuclear wastes). (J.S.)

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2009. Annual report

International Nuclear Information System (INIS)

2010-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2009 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials and physical protection of nuclear materials; (8) Emergency planning and preparedness; (9) International activities; (10) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations.

Report on activities of Nuclear Regulatory Authority of the Slovak Republic and safety of nuclear installations in the Slovak Republic in 2008. Annual report

International Nuclear Information System (INIS)

Zemanova, D.; Pirozekova, M.

2009-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD SR) in 2008 is presented. These activities are reported under the headings: (1) Foreword; (2) Legislation; (3) Issuance of authorizations, assessment, supervisory activities and enforcement; (4) Nuclear safety of nuclear installations in the Slovak Republic; (5) Safety of other nuclear installations; (6) Management of radioactive waste; (7) Nuclear materials and physical protection of nuclear materials; (8) Activity of Building Office; (9) Emergency planning and preparedness; (10) International activities; (11) Public communication; (11) Nuclear Regulatory Authority of the Slovak Republic; (12) UJD SR organization chart; (13) Abbreviations

The control of nuclear sector; Le controle du nucleaire

Energy Technology Data Exchange (ETDEWEB)

NONE

2007-07-01

The Asn is loaded with the control of the nuclear safety and the radiation protection in France: it provides this control, in the name of the state, to protect the workers, the patients, the public and the environment of the risks in relation with nuclear activities. The control is the core business of Asn. Asn so checks the nuclear basic installations (I.N.B.), since their conception until their dismantling, the pressure equipment specially conceived for these installations, the management of the radioactive waste as well as the transport of radioactive substances. Asn also checks all the industrial and research installations as well as the hospitals where are used ionizing radiations. It is a more recent profession there, because dating the reform of the control of the nuclear power of 2002, which constitutes that of the radiation protection. The first responsibility of the activities at risks falls to the one who begins them. This principle applies to all the sectors checked by Asn: an industrialist is responsible for the safety of the nuclear installations which he exploits, a doctor is responsible for the use of the ionizing radiations which he uses. (N.C.)

The control of nuclear sector

International Nuclear Information System (INIS)

2007-01-01

The Asn is loaded with the control of the nuclear safety and the radiation protection in France: it provides this control, in the name of the state, to protect the workers, the patients, the public and the environment of the risks in relation with nuclear activities. The control is the core business of Asn. Asn so checks the nuclear basic installations (I.N.B.), since their conception until their dismantling, the pressure equipment specially conceived for these installations, the management of the radioactive waste as well as the transport of radioactive substances. Asn also checks all the industrial and research installations as well as the hospitals where are used ionizing radiations. It is a more recent profession there, because dating the reform of the control of the nuclear power of 2002, which constitutes that of the radiation protection. The first responsibility of the activities at risks falls to the one who begins them. This principle applies to all the sectors checked by Asn: an industrialist is responsible for the safety of the nuclear installations which he exploits, a doctor is responsible for the use of the ionizing radiations which he uses. (N.C.)

Safety of nuclear installations in the Slovak Republic and activities of the Nuclear Regulatory Authority of the Slovak Republic in 2007

International Nuclear Information System (INIS)

Zemanova, D.

2008-01-01

Prepared pursuant to the provisions of the Atomic Act, the report provides information on the safety of nuclear installation in the Slovak Republic and activities of the Nuclear Regulatory Authority of the Slovak Republic ( UJD SR). UJD SR executes its activities in the area of legislation, issuance of authorizations and permissions for the siting, construction, operation and decommissioning of nuclear installations, in the area of reviews, assessments and control of nuclear safety of nuclear installations and emergency planning, in the area of records and accountability of nuclear materials, independent public information and in the area of international co-operation focused on peaceful uses of nuclear power. Based on the results of inspection activities and evaluation of safety indicators, UJD SR assessed the operation of nuclear installations in the Slovak Republic as safe and reliable. No significant event that could have a negative impact on the personnel, population or environment occurred in 2007. (orig.)

Guatemala: Ozbrojený konflikt 1960-1996 a současná situace: se zvláštním zaměřením na Máje

OpenAIRE

Vilímková, Olga

2009-01-01

Tématem disertační práce je Guatemala: ozbrojený konflikt v letech 1960 - 1996 a současná situace se zvláštním zaměřením na Máje. Příčiny ozbrojeného konfliktu druhé ploviny XX. století (a mnoha současných problémů) v Guatemale se nacházejí v hluboké minulosti země. Už v době koloniální se začaly formovat ekonomicko - sociální vztahy mezi dvěma antagonistickými vrstvami společnosti: kolonizátory a původním obyvatelstvem, které bylo porobeno, vytlačeno na okraj společnosti a využíváno jako pra...

Report on transparency and nuclear safety - Grenoble CEA centre - 2012

International Nuclear Information System (INIS)

2013-01-01

This report presents the different nuclear base installations (INB) of the Grenoble CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, human and organizational factors, arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and results, main events). It reports the significant events related to safety and radiation protection which occurred in 2012 and were declared to the ASN, and discusses how the return-on-experience has been used. It reports and comments the results of measurements of radiological and chemical gaseous and liquid effluents, of surveys of the environment. It also presents the environmental management approach. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, waste production and removal, nature and quantities of warehoused wastes. Remarks and recommendations of the CHSCT are given

Technical organization of safety authorities for the event of an accident at a nuclear installation

International Nuclear Information System (INIS)

Scherrer, J.; Evrard, J.M.; Ney, J.

1986-01-01

Within the general context of nuclear safety, the Central Nuclear Installation Safety Service of the French Ministry for Industry and its technical backup, the Institute for Radiation Protection and Nuclear Safety of the CEA (Atomic Energy Commission), have established a special organization designed to provide real-time forecasts of the evolution of a nuclear accident situation with sufficient forewarning for the local representative of the Government (the Commissaire de la Republique in the Departement affected) to implement, as required, effective countermeasures to protect the population - for example, confinement indoors or evacuation. Descriptions are given of the principles of this organization and the particular precautions taken to confront the problems of mobilizing experts and of dealing with the saturation of normal telecommunications channels to be expected in the event of a nuclear accident. The organization set up for the installations belonging to Electricite de France is given as a detailed example. Particular stress is placed on the organizational arrangements of the Institute for Radiation Protection and Nuclear Safety designed to provide the emergency teams with the evaluation and forecasting tools they require to carry out their tasks. The procedures are on the whole well developed for atmospheric radioactivity transport, for which operational models already exist. Computer-backed methods with improved performance are at present being developed. A method of forecasting the behaviour of the releases resulting from nuclear accidents is set out for pressurized water reactors, based on evaluating the physical state of the installation, confinement integrity, availability of safety and backup systems, support systems and feed sources and on forecasting how this state will develop on the basis of measured and inferred physical values transmitted from the affected power station through a national network. The experience acquired during accident

Index to Nuclear Safety. A technical progress review by chronology, permuted title, and author. Vol. 11, No. 1 through Vol. 15, No. 6

International Nuclear Information System (INIS)

Cottrell, W.B.; Klein, A.

1975-04-01

This issue of the Index to Nuclear Safety covers only articles included in Nuclear Safety, Vol. 11, No. 1, through Vol. 15, No. 6. This index is presented in three sections as follows: Chronological List of Articles by Volume; Permuted Title (KWIC) Index; and Author Index. (U.S.)

Especificação e Implementação de Templates GDMO e Tipos ASN 1 para Linguagem C++

OpenAIRE

Junior, Rivalino Matias; Specialski, Elizabeth Sueli; May, Karina; Ropelato, Patricia

1996-01-01

Este artigo descreve a especificação e implementação de regras para o mapeamento de templates GDMO (GuideUnes lor the Definition 01 Managed Objects) [1 l, além da implementação dos tipos ASN.1, em linguagem de programação C++[2l. Estas regras serao utilizadas no mapeamentotemplate - GDMO para classes (dass) em C++, linguagem utilizada em todo o projeto da Plataforma de Gerencia da Rede Local UFSC, a qual segue o modelo de gerenciamento de redes OSI.

Mining and mining authorities in Saarland 2016. Mining economy, mining technology, occupational safety, environmental protection, statistics, mining authority activities. Annual report; Bergbau und Bergbehoerden im Saarland 2016. Bergwirtschaft, Bergtechnik, Arbeitsschutz, Umweltschutz, Statistiken, Taetigkeiten der Bergbehoerden. Jahresbericht

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-07-01

The annual report of the Saarland Upper Mining Authority provides an insight into the activities of mining authorities. Especially, the development of the black coal mining, safety and technology of mining as well as the correlation between mining and environment are stressed.

Challenges in developing TSO to provide technical support in nuclear safety and security to Pakistan Nuclear Regulatory Authority

International Nuclear Information System (INIS)

Mallick, Shahid A.; Sherwani, Uzman Habib; Mehdi, M. Ammar

2010-01-01

This paper highlights the needs for the establishment of a technical support organization (TSO) in Pakistan Nuclear Regulatory Authority (PNRA), challenges faced during its development, application of training need assessment required for the competency development of its technical manpower and difficulties encountered after its evolution. Key issues addressed include recruitment of technical manpower and enhancing their competencies, acquisition of proper tools required for safety review and assessment, development of a sustainable education and training program consistent with the best international practices and taking the measures to get confidence of the regulatory body. (author)

Safety evaluation report related to operation of Sequoyah Nuclear Plant, Units 1 and 2, Docket nos. 50-327 and 50-328, Tennessee Valley Authority

Energy Technology Data Exchange (ETDEWEB)

NONE

1979-03-01

A safety evaluation of the Tennessee Valley Authority's application for a license to operate its Sequoyah Nuclear Plant, Units 1 and 2, located in Hamilton County, Tennessee, has been prepared by the Office of Nuclear Reactor Regulation of the Nuclear Regulatory Commission. It consists of a technical review and staff evaluation of applicant information on: (1) population density, land use, and physical characteristics of the site area; (2) design, fabrication, construction, testing criteria, and performance characteristics of plant structures, systems, and components important to safety; (3) expected response of the facility to anticipated operating transients, and to postulated design basis accidents; (4) applicant engineering and construction organization, and plans for the conduct of plant operations; and (5) design criteria for a system to control the plant's radiological effluents. The staff has concluded that the plant can be operated by the Tennessee Valley Authority without endangering the health and safety of the public provided that the outstanding matters discussed in the report are favorably resolved. (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)

For optimum safety technologies: understanding relations between the different national authorities and the technical support organizations

International Nuclear Information System (INIS)

Mahmoud, N.S.; Mostafa Aziz, Mostafa

2010-01-01

TSOs describe expert independent organizations, which provide supports for government, regulatory authorities, utilities and industry. The TSO must dispose different competences and objectives in order to deliver to the four independent authorities the technical and scientific knowledge. This comprehensive knowledge, from TSO, should perform through the research and development activities (R and D). Concerning the government, TSOs consider the R and D on the management procedures to characterize the links, to differentiate roles to prevent the overlapping efforts, and finally to build a central data bank in nuclear technologies for the other three authorities. For regulatory organizations, R and D are involved in the regulatory requirements and surveillance processes. On the other side R and D, in case of utilities, activities should focus on the improvement of safety operations for nuclear power and its new generations, and for other nuclear/radiological facilities. Finally, the forth TSOs has R and D targets that should concentrate mainly on material, efficiency, and durability of different equipment and parts involved in the nuclear activities during manufacturing. (author)

Nuclear safety: a large scale quality audit of pressurized equipment

International Nuclear Information System (INIS)

Faudon, Valerie

2016-01-01

This article notably refers to, quotes and comments a hearing organised by the French Public Office for the Assessment Scientific and Technological Choices (OPECST) on the issue of safety of pressurized equipment in nuclear reactors, and which gathered the main concerned actors (Areva, EDF, IRSN, ASN) to have an overview of quality controls in AREVA NP fabrication plants. Two different issues have been addressed: a technical metallurgical issue related to some boiler-making parts, and an issue related to quality assurance. These issues concern different older reactors (Fessenheim for example) as well as new ones (EPR Flamanville). The article indicates the different measures planned, envisaged or already implemented by the concerned actors in order to improve knowledge in the boiler-making industry, and to ensure a better quality

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

"Minulost je bitevním polem současníků". Konference k osmdesátinám Viléma Prečana

Czech Academy of Sciences Publication Activity Database

Hoppe, Jiří

2013-01-01

Roč. 20, 1/2 (2013), s. 236-241 ISSN 1210-7050. ["Minulost je bitevním polem současníků". Konference k osmdesátinám Viléma Prečana. Praha, 24.01.2013-25.01.2013] Institutional support: RVO:68378114 Keywords : Vilém Prečan Subject RIV: AB - History

Highway Safety Program Manual: Volume 3: Motorcycle Safety.

Science.gov (United States)

National Highway Traffic Safety Administration (DOT), Washington, DC.

Volume 3 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on aspects of motorcycle safety. The purpose and specific objectives of a State motorcycle safety program are outlined. Federal authority in the highway safety area and general policies…

Development of French technical safety regulations: safety fundamental rules

International Nuclear Information System (INIS)

Lebouleux, P.

1982-09-01

The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operations of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridical sense; they are called ''Regles Fondamentales de Surete'' (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation pratice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS -or a letter- can also give the result of the examination of the constructor and operator code (RCC) by safety authorities

Development of French technical safety regulations: safety fundamental rules

International Nuclear Information System (INIS)

Lebouleux, P.

1983-01-01

The technical regulation related to nuclear safety in France is made of a set of regulation texts, of a different nature, that define the requirements for the construction, commissioning and operating of nuclear facilities. Simultaneously, the safety authorities (Service Central de Surete des Installations Nucleaires: SCSIN) issue recommendations or guides which are not strictly speaking regulations in the juridicial sense; they are called Regles Fondamentales de Surete (RFS). The RFS set up and detail the conditions, the respect of which is deemed to be complying with the French regulation practice, for the subject to which they relate. Their purpose is to make known rules judged acceptable by safety authorities, thus making the safety review easier. The RFS program is described. A RFS - or a letter - can also give the result of the examination of the constructor and operator codes (RCC) by safety authorities

Study of the cost-benefit analysis method for safety. Meeting of the Permanent Group in charge of nuclear reactors on the 5 July 2007

International Nuclear Information System (INIS)

2007-07-01

After a recall of the history of the issue of third decennial visit of the 900 MW reactors, of the IRSN preliminary analysis, of elements given to the Permanent Group, of requests made by the ASN, and a presentation of the analysis performed by the IRSN, this large report presents the cost-benefit analysis method and its potential applications (principle, cost assessment, safety assessment, examples) and reports international experience gained in this area: the risk-informed approach (within the IAEA, in the USA, France and other European countries, the specific cost-benefit approach), existing cost-benefit type methods (comparison between methods used in the USA, in France and in Canada), and monetary assessment of accidents. It reports the application of the cost-benefit method for safety and its limitations, and then its application to modifications which have been implemented after safety re-examinations. It discusses the use of level 1 and 2 safety probabilistic studies, and reports the use of a cost-benefit method for safety within the frame of safety re-examinations

Report on nuclear safety and transparency 2011 - NBI operated by the CEA in Marcoule

International Nuclear Information System (INIS)

2012-06-01

After a brief presentation of the Marcoule CEA centre, this report indicates the different safety measures related to different risks, to emergency situations, to inspections and audits, and to nuclear base installations (INB). It describes measures related to radiation protection and some remarkable facts which occurred in 2010. It presents the different significant events which occurred in 2011 and were declared to the ASN. It discusses the results of measurements of releases from the installations and their impact on the environment. It addresses the radioactive wastes which are warehoused on the site (measures to limit their volume and to limit their impact on health and on the environment, notably on water and soils)

Use of probabilistic safety assessment in supporting regulatory authority`s work; Todennaekoeisyyspohjaisen turvallisuusanalyysin kaeyttoe viranomaistyoen tukena

Energy Technology Data Exchange (ETDEWEB)

Julin, A

1995-11-01

The aim of the study was to examine possibilities to use probabilistic safety assessment (PSA) more effectively in regulatory control of nuclear power plants. The structure, results and evaluation methods of PSA along with the necessary equations and principles, which could be used in utilising level 1 PSA results in decision making, have been introduced. The presented examples describe the ways PSA has been utilised abroad and particularly in Finnish Centre for Radiation and Nuclear Safety (STUK). The examples calculated in the study are based on the SPSA code and the PSA model of Olkiluoto nuclear power plant (TVO). The examples compare component safety classes versus safety importance and the risk of continued operation versus shutdown alternative in residual heat removal system failures. In addition to this allowed outage times, as calculated by PSA, were compared to allowed outage times according to technical specifications. The last 9 years operating experiences of TVO II was also examined by analysing the risk importance of significant component failures and operational disturbances. The analysis showed that the contribution of component failures and operational disturbances to the overall core damage risk during the studied time period was only 5 per cent. It appeared that the rare, significant initiating events provide the main contribution to the total cumulative risk. (57 refs., 22 figs., 17 tabs.).

Human factors in safety assessment. Safety culture assessment

International Nuclear Information System (INIS)

Zhang Li; Deng Zhiliang; Wang Yiqun; Huang Weigang

1996-01-01

This paper analyses the present conditions and problems in enterprises safety assessment, and introduces the characteristics and effects of safety culture. The authors think that safety culture must be used as a 'soul' to form the pattern of modern safety management. Furthermore, they propose that the human safety and synthetic safety management assessment in a system should be changed into safety culture assessment. Finally, the assessment indicators are discussed

Information note about the protection of nuclear facilities against aircraft crashes

International Nuclear Information System (INIS)

2001-01-01

The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

Glycosylation at Asn91 of H1N1 haemagglutinin affects binding to glycan receptors.

Science.gov (United States)

Jayaraman, Akila; Koh, Xiaoying; Li, Jing; Raman, Rahul; Viswanathan, Karthik; Shriver, Zachary; Sasisekharan, Ram

2012-06-15

The glycoprotein HA (haemagglutinin) on the surface of influenza A virus plays a central role in recognition and binding to specific host cell-surface glycan receptors and in fusion of viral membrane to the host nuclear membrane during viral replication. Given the abundance of HA on the viral surface, this protein is also the primary target for host innate and adaptive immune responses. Although addition of glycosylation sites on HA are a part of viral evolution to evade the host immune responses, there are specific glycosylation sites that are conserved during most of the evolution of the virus. In the present study, it was demonstrated that one such conserved glycosylation site at Asn(91) in H1N1 HA critically governs the glycan receptor-binding specificity and hence would potentially impinge on the host adaptation of the virus.

Organisational culture at the Radiation and Nuclear Safety Authority of Finland's department of Nuclear Reactor Regulation

International Nuclear Information System (INIS)

Reiman, T.; Norros, L.

2001-03-01

A case study to investigate the organisational culture of the regulatory authority was conducted at the Radiation and Nuclear Safety Authority of Finland's (STUK) Nuclear Reactor Regulation (YTO) - department. Organisational culture is defined as a pattern of shared basic assumptions, which are basically unconscious. Objectives of the study were to conceptualise and describe the main characteristics of YTO's organisational culture and to carry out a tentative core task analysis of the inspectors' work. A combination of quantitative and qualitative methods was used in the research. YTO's culture was identified as a hierarchy-focused culture with less emphasis on innovation or social support. However, the ideal values of the personnel emphasised also social support and goal setting. Ambiguous goals were felt by some personnel as increased uncertainty about the meaningfulness of one's job. Also a lack of feedback was mentioned. The core task analysis identified the critical functions of the regulatory practice. These functions specify the three roles of the regulatory authority, the expert role, the public role and the authority role. The culture must support the fulfilment of the requirements of all the three roles. Development needs in YTO's culture were identified and recommendations were made. (au)

SFEN Annual Convention 2012 - The nuclear energy one year after Fukushima. Proceedings; Convention SFEN 2012 - Le nucleaire un an apres Fukushima. Recueil des presentations

Energy Technology Data Exchange (ETDEWEB)

NONE

2012-03-15

This document brings together the available presentations given at the 2012 edition of the Annual Convention of the French society of nuclear energy (SFEN) on the topic of nuclear energy one year after Fukushima. Twenty four presentations (slides) are compiled in this document: 1 - Presentation and introduction of the Annual Convention (Luc Oursel - SFEN President); 2 - Status of onsite/offsite remedial actions, key lessons learned (Akira Omoto, Tokyo univ., Japan Atomic Energy Commission); 3 - Complementary Safety Assessments (CSA) of the French NPP fleet (Dominique Miniere, EDF); 4 - Speech of M. Francois Fillon - Prime Minister; 5 - CSA of the fuel cycle facilities (Philippe Knoche, Areva); 6 - CSA of the EPR (Bertrand de l'Epinois, Areva; Jean-Luc Foret, EDF CNEN); 7 - The collective responsibility of the operators: the action of WANO (Laurent Stricker, WANO); 8 - Conclusions of French Nuclear Safety Authority (ASN) - Safety measures to be strengthened; 9 - Opinion no. 2012-AV-013 from January 3, 2012 of the French Nuclear Safety Authority - ASN (Sophie Mourlon, ASN; Caroline Lavarenne, IRSN); 10 - Nuclear energy: an energy for the future (Bernard Bigot, CEA); 11 - The nuclear phaseout in Germany from the view of German industry (Eberhard von Rottenburg, BDI); 12 - Prospects in China (Wei Lu, CGNP Europe); 13 - Industry Current Status and its Prospects in the United States (J. Spina, CENG); 14 - Nuclear energy prospects in France: recommendations of the Commission 'Energy 2050' (Jacques Percebois, Creden); 15 - Electrical generation system efficiency and economy (Yves Giraud, EDF); 16 - Electrical generation systems and distribution networks (Herve Mignon, Rte); 17 - Prospects in the UK (Tim Stone, DECC/OND, Senior Adviser to the Secretary of State); 18 - Climatic changes and energy policy (Laura Cozzi, IEA); 19 - The young nuclear professionals network (Boris Supiot, SFEN Young Generation Group); 20 - Socio-economic impacts of the nuclear power

SFEN Annual Convention 2012 - The nuclear energy one year after Fukushima. Proceedings

International Nuclear Information System (INIS)

2012-03-01

This document brings together the available presentations given at the 2012 edition of the Annual Convention of the French society of nuclear energy (SFEN) on the topic of nuclear energy one year after Fukushima. Twenty four presentations (slides) are compiled in this document: 1 - Presentation and introduction of the Annual Convention (Luc Oursel - SFEN President); 2 - Status of onsite/offsite remedial actions, key lessons learned (Akira Omoto, Tokyo univ., Japan Atomic Energy Commission); 3 - Complementary Safety Assessments (CSA) of the French NPP fleet (Dominique Miniere, EDF); 4 - Speech of M. Francois Fillon - Prime Minister; 5 - CSA of the fuel cycle facilities (Philippe Knoche, Areva); 6 - CSA of the EPR (Bertrand de l'Epinois, Areva; Jean-Luc Foret, EDF CNEN); 7 - The collective responsibility of the operators: the action of WANO (Laurent Stricker, WANO); 8 - Conclusions of French Nuclear Safety Authority (ASN) - Safety measures to be strengthened; 9 - Opinion no. 2012-AV-013 from January 3, 2012 of the French Nuclear Safety Authority - ASN (Sophie Mourlon, ASN; Caroline Lavarenne, IRSN); 10 - Nuclear energy: an energy for the future (Bernard Bigot, CEA); 11 - The nuclear phaseout in Germany from the view of German industry (Eberhard von Rottenburg, BDI); 12 - Prospects in China (Wei Lu, CGNP Europe); 13 - Industry Current Status and its Prospects in the United States (J. Spina, CENG); 14 - Nuclear energy prospects in France: recommendations of the Commission 'Energy 2050' (Jacques Percebois, Creden); 15 - Electrical generation system efficiency and economy (Yves Giraud, EDF); 16 - Electrical generation systems and distribution networks (Herve Mignon, Rte); 17 - Prospects in the UK (Tim Stone, DECC/OND, Senior Adviser to the Secretary of State); 18 - Climatic changes and energy policy (Laura Cozzi, IEA); 19 - The young nuclear professionals network (Boris Supiot, SFEN Young Generation Group); 20 - Socio-economic impacts of the nuclear power industry in

Towards the licensing of the Geological Disposal: Illustration of the 2009-2010 intermediate milestone

International Nuclear Information System (INIS)

Boissier, Fabrice; Leverd, Pascal C.; Voinis, Sylvie; Tichauer, Michael

2014-01-01

France has a legal and institutional framework for the management of radioactive materials and waste. On June 28, 2006, the Planning Act No. 2006-739 of materials and radioactive waste management was enacted. This French Act mandates Andra (the National Radioactive Waste Management Agency) to conduct studies and research required for the siting and design of a deep disposal facility for high or medium-and long-lived (ILW-LL-HA) radioactive waste in a geological formation, in view of submitting a request for authorization to create such a repository to be examined in 2015. According to French regulations, a creation decree will authorize both the construction of the facility and the nuclear operations to be performed. The commissioning of the repository needs then to be authorized by the Nuclear Safety Authority (ASN) and at the due date of 2025, construction and equipment work shall be carried out concurrently with nuclear operations in the previously commissioned portions. In order to get all the authorizations, Andra will face a number of other external steps including the process of reviewing and evaluating the safety case by the regulatory authority and his technical safety organization (TSO), the Institute of Radioprotection and Nuclear Safety (IRSN). This step by step decision process involves the regulatory authority ASN, IRSN, at some stage the French standing committee in charge of facilities related to nuclear waste management 'GPD', and Andra. The Decree No. 2008-357 of 16 April 2008 made under that Act, sets out interim milestones before 2015, among which the delivery by Andra to the Ministers for Energy, Research and Environment by the end of 2009 of a record to take stock. That record included a share of studies on the design, the safety and the reversibility options, as well as the waste inventory to be disposed. In that frame, Andra sent to the ASN the so-called 'Dossier 2009'. That intermediate stage aimed at helping in building

Lessons learned on the design and the conduct of Post-Authorization Safety Studies

DEFF Research Database (Denmark)

Engel, Pierre; Almas, Mariana Ferreira; De Bruin, Marieke Louise

2017-01-01

Aims: To describe and characterize the first cohort of Post-Authorization Safety Study (PASS) protocols reviewed under the recent European pharmacovigilance legislation. Methods: A systematic approach was used to compile all publicly available information on PASS protocols and assessments submitted...... the 189 PASS, slightly more involved primary data capture (58%). PASS assessing drug utilization mainly leveraged secondary data sources (58%). The majority of the PASS did not include a comparator (65%) and 35% of PASS also evaluated clinical effectiveness endpoints. Conclusions: To the best of our...... knowledge this is the first comprehensive review of three years of PASS protocols submitted under the new pharmacovigilance legislation. Our results show that both EMA and PASS sponsors could respectively increase the availability of protocol assessments and documents in the EU-PAS. Protocol content review...

Nuclear safety in Slovak Republic. Regulatory aspects of NPP nuclear safety

International Nuclear Information System (INIS)

Lipar, M.

1999-01-01

Regulatory Authority (UJD) is appointed by the Slovak Republic National Council as an Executive Authority for nuclear safety supervision. Nuclear safety legislation, organisation and resources of UJD, its role and responsibilities are described together with its inspection and licensing functions and International cooperation concerning improvements of safety effectiveness. Achievements of UJD are listed in detail

Monitoring radioactivity in the environment: context, objectives, challenges and prospects

International Nuclear Information System (INIS)

Collet, J.; Jaunet, P.

2010-01-01

The aims of environmental radioactivity monitoring are multiples: protection of human health and environment, knowledge of the radiological status of the environment, early detection of radiological events, public information. This monitoring is ensured by several stakeholders (licensees, IRSN, ASN, state and local authorities, associations...) and in all environment compartments (air, water, soil, fauna and flora...). Within a European regulatory context, the Nuclear Transparency and Security Act 2006-686 of 13 June 2006 (TSN Act) reinforces the importance attached to consideration of safety, radiation protection and the environment. Other developments in the scope of environmental radioactivity must be noted: new stakeholders, lower background radiation, deployment of the French National Network of Environmental Radioactivity Monitoring (RNM), evolution of the ICPR thoughts to take better account of environmental protection, post-accident management doctrine, new concerns about environmental behaviour of some radionuclides. In order to maintain a quality policy in the field of environmental radioactivity measurements and to ensure the transparency of information, ASN will make sure that the strategy of environmental radioactivity monitoring will take into account these concerns. (author)

Activities of Nuclear Regulatory Authority and safety of nuclear facilities in the Slovak Republic in 1993

International Nuclear Information System (INIS)

1994-04-01

A brief account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (NRA SR) in 1993 is presented. These activities are reported under the headings: (1) Introduction; (2) Regulatory activities at nuclear power plants units in operation; (2.1) Nuclear power plant SEP-EBO V-1; (4) Selected operation events and safety assessment in NPP SEP-EBO V-1; (2.2) Safety assessment of NPP SEP-EBO V-2; (3) Results of regulatory activities at the decommissioning of NPP A-1; (4) Regulatory activities at units under construction SEP-EMO - NPP Mochovce; (5) Further regulatory activities. (5.1) Preparation of designated personnel; (5.2) Inspection and accountancy of nuclear material; (5.3) Security provisions; (5.4) Accounted items and double use items; (5.5) Problem of radioactive wastes; (6.1) International co-operation activities of NRA; (6.2) Emergency planning; (6.3) International activities for quality enhancement of national supervision; (7) Conclusion [sk

16 CFR 1500.2 - Authority.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Authority. 1500.2 Section 1500.2 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION FEDERAL HAZARDOUS SUBSTANCES ACT REGULATIONS HAZARDOUS SUBSTANCES AND ARTICLES; ADMINISTRATION AND ENFORCEMENT REGULATIONS § 1500.2 Authority. Authority under the...

HCTISN - High Committee for transparency and information on nuclear safety, Plenary meeting of the 3 October 2013

International Nuclear Information System (INIS)

Buerger, Eric; Schilz, Fabien; Piketty, Laurence; Martelet, Bertrand; Quintin, Christophe; Gauthier, Florence; Charles, T.

2013-01-01

This document gathers a set of Power Point presentations. The first one, proposed by the ANDRA, addresses the challenges related to the long term management of dismantling wastes (quantities, perspectives for planning, optimization and R and D investments, ANDRA's missions, R and D themes, industrial developments, service providing). The second one, proposed by AREVA, addresses the dismantling of Areva's nuclear sites (challenges and peculiarities, organisation, overview of the different current dismantling projects in France). The third one, proposed by the ASN, discusses the current status, perspectives and challenges of dismantling (dismantling definition, objectives and strategies, ASN missions for the regulation, authorization, control, public information, and crisis management regarding dismantling, regulatory context with its procedures and for waste management, and installations being currently dismantled). The fourth one, proposed by the CEA, addresses the dismantling of CEA nuclear installations (presentation, challenges, strategy, organisation and financing of the A and D process (cleaning up and dismantling) within the CEA, a focus on the case of CEA installations in Grenoble, the return on experience within the CEA, R and D for A and D programs). The sixth presentation by EDF addresses the program of deconstruction of EDF generation-1 nuclear power plants (legal and financial framework and governance, dismantling policy and strategy, management of deconstruction waste, dismantling program for first-generation reactors and focus on the Brennilis and Chooz reactors, industrial and social challenges of operational practices). Proposed by the ministry of Ecology, the next presentation addresses the safety of nuclear installations and the return on experience after the intrusion in Tricastin (overview of regulation, progress in the implementation of PCMNIT regulation - protection and control of nuclear materials, of their installations and transport - by

IAEA Team Reviews Safety Progress at French Nuclear Power Plant 19-23 May 2014

International Nuclear Information System (INIS)

2014-01-01

the site at all times with the authority and responsibility to initiate appropriate emergency response measures. The team handed over a draft of its findings to Gravelines NPP management officials in the form of Technical Notes for factual comments. These Technical Notes will be reviewed at IAEA headquarters after receiving comments from Gravelines NPP and the French nuclear regulatory authority, ASN. The final report will be submitted to the Government of France within three months

Report on nuclear safety and transparency 2011 - Fontenay-aux-Roses CEA centre

International Nuclear Information System (INIS)

2012-06-01

After a brief presentation of the Fontenay-aux-Roses CEA centre, this report indicates the different safety measures in the different nuclear base installations (INB) of this site (measures related to different risks, to emergency situations, to inspections and audits). It describes measures related to radiation protection: organisation, dosimetry results. It presents the different significant events which occurred in 2011 and were declared to the ASN. It discusses the results of measurements of liquid, gaseous and chemical releases from the installations and their impact on the environment. It addresses the radioactive waste management (measures to limit their volume and to limit their impact on health and on the environment, notably on water and soils, type and quantities of wastes stored in INBs). It presents the different measures and actions related to information transparency

The national plan of radioactive materials and wastes management. 2010-2012 edition

International Nuclear Information System (INIS)

2010-01-01

This short presentation, given by the nuclear safety authority (ASN) at the meeting of January 26, 2010 of the high committee for the nuclear safety transparency and information (HCTISN), describes the different stages of the elaboration of the new edition of the French national plan of radioactive materials and wastes management (PNGMDR). The plan comprises 3 parts: the principles and objectives of the radioactive materials and wastes management, the status of existing procedures and of procedures still under development by the end of 2009, the improvements made. The topics concern: the interim storage, the long-term management and the global consistency of the plan. (J.S.)

Status of radioactive material transport

International Nuclear Information System (INIS)

Kueny, Laurent

2012-01-01

As about 900.000 parcels containing radioactive materials are transported every year in France, the author recalls the main risks and safety principles associated with such transport. He indicates the different types of parcels defined by the regulation: excepted parcels, industrial non fissile parcels (type A), type B and fissile parcels, and highly radioactive type C parcels. He briefly presents the Q-system which is used to classify the parcels. He describes the role of the ASN in the control of transport safety, and indicates the different contracts existing between France or Areva and different countries (Germany, Japan, Netherlands, etc.) for the processing of used fuels in La Hague

The risk of accident in nuclear power plants - Quotes and questions. National debate on energy transition. Taking the risk of nuclear accident into account. Note to the 'scenarios' subgroup of the group of experts

International Nuclear Information System (INIS)

Laponche, Bernard

2013-01-01

After an overview of the production of electricity from nuclear energy and of its risks, the author discusses the issue of nuclear safety by distinguishing the different points of view, by describing the different levels between a severe and a major accident, and by recalling the statements made by the ASN and the IRSN on this issue. He describes the various reasons and consequences of accidents: types of accidents which could result in a core fusion, the containment failure as the major accident. He discusses the questions and comments about major issues like: strength of reactor vessels, hydrogen explosion, water vapour explosion, corium crossing the concrete sill plate, corium recovery, MOX as an aggravating situation for safety. In the last part, the author discusses the global assessment of a risk of a nuclear accident: probabilities and occurrences, significant accidents on PWRs, premonitory analysis, demonstration of nuclear safety

16 CFR 1700.2 - Authority.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Authority. 1700.2 Section 1700.2 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION POISON PREVENTION PACKAGING ACT OF 1970 REGULATIONS POISON PREVENTION PACKAGING § 1700.2 Authority. Authority under the Poison Prevention Packaging Act of 1970 is...

Report on transparency and nuclear safety - 2013. Nuclear facilities exploited by CEA Marcoule

International Nuclear Information System (INIS)

2014-01-01

This report presents the different basic nuclear installations (INB) of the Marcoule CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, arrangements related to different risks, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings) and of measures related to radiation protection (organisation and results, main events). It reports the significant events related to safety and radiation protection which occurred in 2013 and were declared to the ASN, and discusses how the return-on-experience has been used. It reports and comments the results of measurements of gaseous and liquid effluents, of their impact on the environment, and of surveys of the environment. It also presents the environmental management approach. The next part addresses the management of radioactive wastes which are warehoused on this site: arrangements aimed at limiting their volume, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. Remarks and recommendations of the CHSCT are given

Presentation the national Plan of management of radioactive materials and wastes. Friday, the 4. of June 2010

International Nuclear Information System (INIS)

2010-01-01

After a synthesis of the national plan of management of radioactive materials and wastes (PNGMDR for Plan national de gestion des matieres et des dechets radioactifs), this document contains the main conclusions of this plan for the period 2010-2012, a presentation of its elaboration modalities, a presentation of the basic principles regarding radioactive materials and wastes (definitions, origins, waste types and categories, waste management types), a presentation of the main actors of their management (agencies, ministries, authorities, research organizations, institutional bodies, associations). A glossary and other documents are provided, notably a presentation of the ASN (the French Nuclear Safety Authority), a report by the ANDRA agency giving an inventory of radioactive materials and wastes, and a chapter of a report on nuclear safety and radioprotection status in France in 2009

Safety culture

International Nuclear Information System (INIS)

Keen, L.J.

2003-01-01

Safety culture has become a topic of increasing interest for industry and regulators as issues are raised on safety problems around the world. The keys to safety culture are organizational effectiveness, effective communications, organizational learning, and a culture that encourages the identification and resolution of safety issues. The necessity of a strong safety culture places an onus on all of us to continually question whether the safety measures already in place are sufficient, and are being applied. (author)

Assessment of the effectiveness of the Hungarian nuclear safety regulatory authority by international expert teams

International Nuclear Information System (INIS)

Voeroess, L.; Lorand, F.

2001-01-01

On the basis of the role nuclear regulatory authorities (NRA) have to fulfil and the new challenges affecting them, in the paper an overview is made on how the Hungarian NRA has evaluated and utilised the results of different international efforts in the enhancement of its effectiveness and efficiency. The reviews have been conducted by different groups of experts organised by highly recognised international organisations (e.g. IAEA, EC) and highly competent foreign regulatory bodies. The different reviews of activities and working conditions of the HAEA NSD have resulted in a generally positive picture, however, it also revealed weaknesses as well. They recognised the developments made in recent years and also appreciated the overall favourable level of nuclear safety in Hungary, identified 'good practices' and made recommendations and suggestions for the most important and most efficient ways for future improvements. These are cited or referenced in the paper. At the end, some recommendations have been formed based on the experiences gained from the review missions and from our self-assessment. (author)

The management of post nuclear or radiological emergency situations in France

International Nuclear Information System (INIS)

Godet, Jean-Luc; Mehl-Auget, Isabelle; Johanna Fite

2008-01-01

For several years, public authorities have defined an organisation for the management of emergency situations arising from an accident occurring at a nuclear installation. So far, the management of the risk arising from the post accident step was, in itself, not explored with the same care. Whatsoever, no formal policy on which the action of public authority could be based is today available. The French Nuclear Safety Authority (ASN), in relation with the other concerned departments, is now in charge to prepare and implement the necessary provisions to respond to a post accident situation. In June 2005, ASN established the steering committee for the management of post nuclear or radiological emergency situations (CODIRPA). The definition of a national policy related to the management of the radiological risk during a post event situation has to integrate various organisation aspects such as: lifting of protection emergency provisions and rehabilitation of buildings, life in contaminated rural territories, agriculture and water, dose and radiological consequences, sanitary surveillance of victims and populations, indemnification, waste management of contaminated crops and soils, organisation of public Authorities. During the 2nd step of CODIRPA work (2008-2009), the first elements of policy will be consolidated and new scenarios will be studied (one worsened scenario and one scenario with alpha emitting radionuclide). In parallel, a procedure for local actor's consultation has just been launched. (author)

Development of a national doctrine for the management of the post-accident phase of a radiological emergency situation

International Nuclear Information System (INIS)

Niel, J.Ch.; Godet, J.L.

2008-01-01

For several years, public Authorities have defined an organization for the management of emergency situations arising from an accident occurring at a nuclear installation. So far, the management of the risk arising from the post accident phase was, in itself, not explored with the same care. What so ever, no format policy on which the action of public Authority could be based is today available. The nuclear safety Authority (ASN), in relation with the other concerned departments, is now in charge, according to the above mentioned directive, to prepare and implement the necessary provisions to respond to a post accident situation. In dune 2005, ASN established the steering committee for the management of post nuclear or radiological emergency situations (CODIRPA). The definition of a national policy related to the management of the radiological risk during a post event situation having to integrate various organization aspects as: lifting of protection emergency provisions and rehabilitation of buildings, life in contaminated rural territories, agriculture and water, dose and radiological consequences, sanitary surveillance of victims and populations, indemnification, waste management of contaminated crops and soils, organization of public Authorities. During the 2. phase of CODIRPA work (2008-2009), the first elements of policy will be consolidated and new scenarios will be studied (one worsened scenario and one scenario with alpha emitting radionuclide). in parallel, a procedure for local actor's consultation should be elaborated. (authors)

Nuclear law - Nuclear safety

International Nuclear Information System (INIS)

Pontier, Jean-Marie; Roux, Emmanuel; Leger, Marc; Deguergue, Maryse; Vallar, Christian; Pissaloux, Jean-Luc; Bernie-Boissard, Catherine; Thireau, Veronique; Takahashi, Nobuyuki; Spencer, Mary; Zhang, Li; Park, Kyun Sung; Artus, J.C.

2012-01-01

This book contains the contributions presented during a one-day seminar. The authors propose a framework for a legal approach to nuclear safety, a discussion of the 2009/71/EURATOM directive which establishes a European framework for nuclear safety in nuclear installations, a comment on nuclear safety and environmental governance, a discussion of the relationship between citizenship and nuclear, some thoughts about the Nuclear Safety Authority, an overview of the situation regarding the safety in nuclear waste burying, a comment on the Nome law with respect to electricity price and nuclear safety, a comment on the legal consequences of the Fukushima accident on nuclear safety in the Japanese law, a presentation of the USA nuclear regulation, an overview of nuclear safety in China, and a discussion of nuclear safety in the medical sector

77 FR 25179 - Patient Safety Organizations: Voluntary Relinquishment From Surgical Safety Institute

Science.gov (United States)

2012-04-27

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... voluntary relinquishment from the Surgical Safety Institute of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act) authorizes the...

Safety balance: Analysis of safety systems

International Nuclear Information System (INIS)

Delage, M.; Giroux, C.

1990-12-01

Safety analysis, and particularly analysis of exploitation of NPPs is constantly affected by EDF and by the safety authorities and their methodologies. Periodic safety reports ensure that important issues are not missed on daily basis, that incidents are identified and that relevant actions are undertaken. French safety analysis method consists of three principal steps. First type of safety balance is analyzed at the normal start-up phase for each unit including the final safety report. This enables analysis of behaviour of units ten years after their licensing. Second type is periodic operational safety analysis performed during a few years. Finally, the third step consists of safety analysis of the oldest units with the aim to improve the safety standards. The three steps of safety analysis are described in this presentation in detail with the aim to present the objectives and principles. Examples of most recent exercises are included in order to illustrate the importance of such analyses

Author Details

African Journals Online (AJOL)

Ghirxi, KT. Vol 1 (2011) - Articles Human errors and system variability in safety investigations of maritime casualties: an expression of systemic concerns. Abstract. ISSN: 2026-6324. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's Partners ...

Author Details

African Journals Online (AJOL)

Oloyede, AR. Vol 29, No 1 (2011) - Articles Microbiological Safety of Corn-Based Snack Product, Aadun, Sold in Abeokuta, South-Western Nigeria Abstract. ISSN: 0189-7241. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's Partners ...

49 CFR 374.503 - Authority.

Science.gov (United States)

2010-10-01

... 49 Transportation 5 2010-10-01 2010-10-01 false Authority. 374.503 Section 374.503 Transportation Other Regulations Relating to Transportation (Continued) FEDERAL MOTOR CARRIER SAFETY ADMINISTRATION... Incidental Charter Rights § 374.503 Authority. Motor carriers transporting passengers, in interstate or...

Discussion on the safety classification of nuclear safety mechanical equipment

International Nuclear Information System (INIS)

Shen Wei

2010-01-01

The purpose and definition of the equipment safety classification in nuclear plant are introduced. The differences of several safety classification criterions are compared, and the object of safety classification is determined. According to the regulation, the definition and category of the safety functions are represented. The safety classification method, safety classification process, safety class interface, and the requirement for the safety class mechanical equipment are explored. At last, the relation of the safety classification between the mechanical and electrical equipment is presented, and the relation of the safety classification between mechanical equipment and system is also presented. (author)

Author Details

African Journals Online (AJOL)

Oloo, JEO. Vol 10, No 11 (2010) - Articles Food safety and quality management in Kenya: An overview of the roles played by various stakeholders. Abstract PDF. ISSN: 1684-5374. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's Partners ...

Author Details

African Journals Online (AJOL)

Nketsia-Tabiri, J. Vol 39, No 1 (2006) - Articles Irradiation of ready meals for microbiological safety and shelf-life extension. 1. Microbiological quality of waakye and other ready-to-eat meals. Abstract. ISSN: 0855-0042. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's ...

Author Details

African Journals Online (AJOL)

Abey, KA. Vol 17, No 1 (2017) - Articles Knowledge and practices of food hygiene and safety among camel milk handlers in the pastoral camel value chain in Kenya Abstract PDF. ISSN: 1684-5374. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL ...

Author Details

African Journals Online (AJOL)

Perry, EC. Vol 18 (2012): Supplement 1 - Articles Securing South Africa during the 2010 FIFA World Cup: Legacy implications for post-event safety and security. Abstract. ISSN: 1117-4315. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's ...

Author Details

African Journals Online (AJOL)

Ogo, IN. Vol 15, No 1 (2004) - Articles Listeria monocytogenes and other Listeria species in poul try faeces applied as manure on farm lands: Environmental health and food safety. Abstract PDF. ISSN: 01891731. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More ...

Report on transparency and nuclear safety - Fontenay-aux-Roses CEA centre - 2012

International Nuclear Information System (INIS)

2013-01-01

This report presents the different nuclear base installations (INB) of the Fontenay-aux-Roses CEA centre, gives an overview of measures regarding safety within these installations (organisation, general arrangements, arrangements related to different risks, defence in-depth, management of emergency situations, inspections, audits and second-level controls, arrangements and main events specific to the different installations and buildings, issues related to transports, soil radiological assessment) and measures related to radiation protection (organisation and results). It reports the significant events related to safety and radiation protection which occurred in 2012 and were declared to the ASN, and discusses how the return-on-experience has been used. It reports and comments the results of measurements of radiological and chemical gaseous and liquid effluents, of surveys of the environment. It also evokes important events related to these measurement and survey processes, presents the environmental management approach. The next part addresses the management of radioactive wastes: arrangements aimed at limiting the volume of warehoused wastes, and at limiting their impact on health and on the environment, nature and quantities of warehoused wastes. The different arrangements regarding transparency and information are reviewed (TSN report, newsletter, and so on)

Directory of the French nuclear industry

International Nuclear Information System (INIS)

2002-10-01

This directory includes data sheets on the French companies operating in the nuclear industry. It begins with an introduction containing information on the French nuclear industry: 1 - nuclear power development in France (national energy plan, history, organization, economic advantages, reactors); 2 - French operator: Electricite de France (EdF); 3 - the industry (Areva, Cogema, mining activities, uranium chemistry and enrichment, processing, recycling, engineering, services, Framatome ANP); 4 - R and D and knowledge dissemination: French atomic energy commission (CEA); 5 - nuclear safety, security, control and regulation: nuclear safety authority (ASN), general direction of nuclear safety and radioprotection (DGSNR), institute of radioprotection and nuclear safety (IRSN), radioactive wastes, ANDRA's role; 6 - associations: French atomic forum (FAF), French nuclear industry trade association (GIIN), French nuclear energy society (SFEN), French radiation protection society (SFRP). Then, the data sheets of the directory follows. (J.S.)

Employee coaching and counseling program metode alternatif untuk optimalisasi human capital pada pegawai aparatur sipil negara (ASN

Directory of Open Access Journals (Sweden)

Marina Sulastiana

2017-06-01

Full Text Available State Civil Servants Apparatus (ASN have to be more integrity, professional, neutral and capable to carrying out a public service to the community. It was an important one that can be optimized through development of human capital. Based on previous research investigated role of Human Capital towards Services and performance of Public Service, shows that staff and head divison level only has moderate degree of human capital. While, Emotional Capital was a most dominan aspect in Human Capital. Otherwise, Social Capital aspects results in the low level. It comes with consequences to optimized them through psychological intervention with group Employee Coaching and Counseling Program (ECCP. This study was action research, experimental one group preteset and postest design. The result shows that ECCP was contribute effectively to enhance Human Capital, particularly in Emotional Capital optimization.

Information note about the protection of nuclear facilities against aircraft crashes; Note d'information sur la protection des installations nucleaires contre les chutes d'avions

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight < 5.7 t), the military aircraft, and the commercial aircraft (w > 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

Information note about the protection of nuclear facilities against aircraft crashes; Note d'information sur la protection des installations nucleaires contre les chutes d'avions

Energy Technology Data Exchange (ETDEWEB)

NONE

2001-07-01

The protection of nuclear facilities against external risks (earthquakes, floods, fires etc..) is an aspect of safety taken into consideration by the French authority of nuclear safety (ASN). Concerning the aircraft crashes, the fundamental safety rules make three categories of aircraft: the small civil aircraft (weight < 5.7 t), the military aircraft, and the commercial aircraft (w > 5.7 t). Nuclear facilities are designed to resist against crashes of aircraft from the first category only, because the probability of the accidental crash of a big aircraft are extremely low. This document comprises an information note about the protection of nuclear facilities against aircraft crashes, a dossier about the safety of nuclear facilities with respect to external risks in general (natural disasters and aircraft crashes), and an article about the protection of nuclear power plants against aircraft crashes (design, safety measures, regulation, surveillance, experience feedback). (J.S.)

Discussion on building safety culture inside a nuclear safety regulatory body

International Nuclear Information System (INIS)

Fan Yumao

2013-01-01

A strong internal safety culture plays a key role in improving the performance of a nuclear regulatory body. This paper discusses the definition of internal safety culture of nuclear regulatory bodies, and explains the functions that the safety culture to facilitate the nuclear safety regulation and finally puts forward some thoughts about building internal safety culture inside regulatory bodies. (author)

Author Details

African Journals Online (AJOL)

Alfadul, S.M. Vol 10, No 6 (2010) - Articles Use of nanotechnology in food processing, packaging and safety – review. Abstract PDF. ISSN: 1684-5374. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's Partners · Terms and Conditions of Use ...

Author Details

African Journals Online (AJOL)

de Reuck, S. Vol 26, No 1 (2014) - Articles Factors Associated with Safety Events in Air Traffic Control Abstract. ISSN: 1010-2728. AJOL African Journals Online. HOW TO USE AJOL... for Researchers · for Librarians · for Authors · FAQ's · More about AJOL · AJOL's Partners · Terms and Conditions of Use · Contact AJOL ...

Reports by the Parliamentary Office for scientific and technological assessments. Thursday, May 19, 2011. The French nuclear installations in front of natural risks; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Jeudi 19 mai 2011. Les installations nucleaires francaises face aux risques naturels

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-05-15

Members of the French Parliament, representatives of the French nuclear safety authority (ASN), of the Academy of Sciences, researchers, and associations argue on major natural risks and their evaluation, notably by referring to the earthquake and tsunami which caused the Fukushima accident. They discuss the predictability of these phenomena, and evoke the context and consequences of climate change. A representative of the Academy of Technologies discusses the risks of land-slips and dam failure, outlines that earthquakes only caused some cracks in dams, and evokes the legal context and organisation regarding dam safety. Possible effects of earthquakes in France are discussed. A second part addresses the way natural risks are taken into account in the protection of nuclear installations

Reports by the Parliamentary Office for scientific and technological assessments. Thursday, May 19, 2011. The French nuclear installations in front of natural risks

International Nuclear Information System (INIS)

2011-05-01

Members of the French Parliament, representatives of the French nuclear safety authority (ASN), of the Academy of Sciences, researchers, and associations argue on major natural risks and their evaluation, notably by referring to the earthquake and tsunami which caused the Fukushima accident. They discuss the predictability of these phenomena, and evoke the context and consequences of climate change. A representative of the Academy of Technologies discusses the risks of land-slips and dam failure, outlines that earthquakes only caused some cracks in dams, and evokes the legal context and organisation regarding dam safety. Possible effects of earthquakes in France are discussed. A second part addresses the way natural risks are taken into account in the protection of nuclear installations

9 CFR 592.10 - Authority.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Authority. 592.10 Section 592.10 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG PRODUCTS INSPECTION VOLUNTARY INSPECTION OF EGG PRODUCTS Administration § 592.10 Authority. The Administrator shall...

Regulatory review of safety cases and safety assessments - associated challenges

International Nuclear Information System (INIS)

Bennett, D.G.; Ben Belfadhel, M.; Metcalf, P.E.

2006-01-01

Regulatory reviews of safety cases and safety assessments are essential for credible decision making on the licensing or authorization of radioactive waste disposal facilities. Regulatory review also plays an important role in developing the safety case and in establishing stakeholders' confidence in the safety of the facility. Reviews of safety cases for radioactive waste disposal facilities need to be conducted by suitably qualified and experienced staff, following systematic and well planned review processes. Regulatory reviews should be sufficiently comprehensive in their coverage of issues potentially affecting the safety of the disposal system, and should assess the safety case against clearly established criteria. The conclusions drawn from a regulatory review, and the rationale for them should be reproducible and documented in a transparent and traceable way. Many challenges are faced when conducting regulatory reviews of safety cases. Some of these relate to issues of project and programme management, and resources, while others derive from the inherent difficulties of assessing the potential long term future behaviour of engineered and environmental systems. The paper describes approaches to the conduct of regulatory reviews and discusses some of the challenges faced. (author)

9 CFR 590.10 - Authority.

Science.gov (United States)

2010-01-01

... 9 Animals and Animal Products 2 2010-01-01 2010-01-01 false Authority. 590.10 Section 590.10 Animals and Animal Products FOOD SAFETY AND INSPECTION SERVICE, DEPARTMENT OF AGRICULTURE EGG PRODUCTS... Authority. The Administrator shall perform, for and under the supervision of the Secretary, such duties as...

Celostátní seminář Celoživotní učení - Kroměříž 2006 "Současná realita - budoucnost".

Czech Academy of Sciences Publication Activity Database

Basl, Josef

2006-01-01

Roč. 10, č. 6 (2006) ISSN 1212-5075. [Celoživotní učení - Kroměříž 2006 "Současná realita - budoucnost". Kroměříž, 18.05.2006-19.05.2006] R&D Projects: GA ČR GA403/06/1421 Institutional research plan: CEZ:AV0Z70280505 Keywords : Czech Republic * lifelong learning * current issues Subject RIV: AO - Sociology, Demography

48 CFR 50.101-1 - Authority.

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Authority. 50.101-1... EXTRAORDINARY CONTRACTUAL ACTIONS AND THE SAFETY ACT Extraordinary Contractual Actions 50.101-1 Authority. (a... following agencies to exercise the authority conferred by Pub. L. 85-804 and to delegate it to other...

[Do residents and nurses communicate safety relevant concerns? : simulation study on the influence of the authority gradient].

Science.gov (United States)

St Pierre, M; Scholler, A; Strembski, D; Breuer, G

2012-10-01

Due to the negative impact on decision-making too steep authority gradients in teams represent a risk factor for patient safety. As residents and nursing staff may fear sanctions they may be reluctant to forward critical information to or challenge planned actions of attending physicians. In the setting of a simulation course it was investigated whether and to what extent team members would challenge decisions of familiar attending physicians. In each case where participants did not voice an opinion the underlying motives for the behavior were investigated. A total of 59 physicians and 18 nursing staff participated in the scenario. During a rapid sequence induction they were confronted with 7 critical situations created by the attending physician who had been instructed by the simulation team. Recommendations of the German Society of Anaesthesiology were ignored as well as clinical standard operating procedures (SOPs) and two potentially fatal drug administrations were ordered. An attempt was made to determine whether team members were aware of the safety threat at all and if so how they would solve the resulting conflicts. The level of verbal challenge was scored. During debriefing participants were asked to verbalize the motives which they thought might account for their silence or level of challenge. In situations where non-verbal conflict resolution was possible 65% of the participants pursued that strategy whereas 35% voiced an opinion. Situations necessitating verbal intervention were identified in 66% but 72% of the participants chose to remain silent. Team members decided to challenge the attending physician in only 28% of the situations. In 35% their statement was oblique, in 25% the problem was addressed but not further pursued and only in 40% did participants show crisp advocacy and assertiveness and initiated discussion. Asked why they had refrained from challenging the attending physician 37% had no answer, in 35% of situations participants observed a

Selecting of key safety parameters in reactor nuclear safety supervision

International Nuclear Information System (INIS)

He Fan; Yu Hong

2014-01-01

The safety parameters indicate the operational states and safety of research reactor are the basis of nuclear safety supervision institution to carry out effective supervision to nuclear facilities. In this paper, the selecting of key safety parameters presented by the research reactor operating unit to National Nuclear Safety Administration that can express the research reactor operational states and safety when operational occurrence or nuclear accident happens, and the interrelationship between them are discussed. Analysis shows that, the key parameters to nuclear safety supervision of research reactor including design limits, operational limits and conditions, safety system settings, safety limits, acceptable limits and emergency action level etc. (authors)

EDF - The Inspector General's report on Nuclear Safety and Radiation Protection

International Nuclear Information System (INIS)

Tandonnet, Jean

2012-01-01

This report is destined for the President of EDF with the purpose of informing him of the judgement the Inspector General has about the nuclear safety and radiation protection within the EDF Group. It is also intended for all who, in any way, play a role at EDF in improving nuclear safety. It may also prove useful to those outside the company who work in the nuclear field or indeed any branch of industry where there are risks to be managed and who wish to participate in the debate. It also contributes to the pool of information shared with the other nuclear operators under the auspices of WANO. The continuous improvement of nuclear safety results is a fundamental commitment of the EDF Group. This is notably reflected in a policy of transparency, whether in France, Britain, America or China. This document constitutes an example of this, offering an independent view of the operational situation. It is based on facts and findings derived in EDF's contacts with field staff and meetings with the decision makers, managers, medical personnel and players on both sides of this industry as well as outside stakeholders, especially contractor companies. The resulting snapshot of the situation in the field is particularly instructive. This report therefore concentrates more on problems and weaknesses rather than strengths and progress, except as concerns happenings outside France, where the focus is more on good practices than difficulties. Contents: 1 - The view from the Inspector General of EDF about the nuclear safety in the EDF group; 2 - A panorama of 2011: The management, The state of the installations, Maintenance of the French nuclear power plants, Relations with the French nuclear safety authority (ASN), The EPR projects, The players in the fields of health and safety, Radiation protection, Fire prevention and fire fighting, Increasing nuclear power plant security, Decommissioning; 3 - Nuclear safety management; 4 - The Fukushima Daiichi accident; 5 - Training to

SAFETY

CERN Multimedia

Niels Dupont

2013-01-01

CERN Safety rules and Radiation Protection at CMS The CERN Safety rules are defined by the Occupational Health & Safety and Environmental Protection Unit (HSE Unit), CERN’s institutional authority and central Safety organ attached to the Director General. In particular the Radiation Protection group (DGS-RP1) ensures that personnel on the CERN sites and the public are protected from potentially harmful effects of ionising radiation linked to CERN activities. The RP Group fulfils its mandate in collaboration with the CERN departments owning or operating sources of ionising radiation and having the responsibility for Radiation Safety of these sources. The specific responsibilities concerning "Radiation Safety" and "Radiation Protection" are delegated as follows: Radiation Safety is the responsibility of every CERN Department owning radiation sources or using radiation sources put at its disposition. These Departments are in charge of implementing the requi...

Post-authorization safety surveillance of a liquid pentavalent vaccine in Guatemalan children.

Science.gov (United States)

Asturias, Edwin J; Contreras-Roldan, Ingrid L; Ram, Malathi; Garcia-Melgar, Ana J; Morales-Oquendo, Vilma; Hartman, Katharina; Rauscher, Martina; Moulton, Lawrence H; Halsey, Neal A

2013-12-02

Combination vaccines have improved the efficiency of delivery of new vaccines in low and middle-income countries. Post-authorization monitoring of adverse events (AEs) after vaccination with a liquid pentavalent DTwP-HepB-Hib combination vaccine was conducted in Guatemalan infants. A prospective observational safety study of the incidence of medical attended events (MAEs) and serious adverse events (SAEs) in children who received pentavalent and oral polio vaccines at 2, 4 and 6 months of age was conducted in two clinics at the Institute of Guatemala. Parents were contacted by telephone after each dose. All outpatient, emergency department visits, and hospitalizations were monitored. A self-controlled analysis was conducted to determine if there was evidence of increased risk of MAEs or SAEs following vaccines as compared to control time windows. Of 3000 recruited infants, 2812 (93.7%) completed the third dose and 2805 (93.5%) completed follow-up. Ten AEs in eight infants, of which four SAEs in four infants, were classified as related to the vaccine. Thirteen deaths were reported due to common illnesses of infancy, and none were judged to be related to the vaccine. The mortality rate (4.4 per 1000) was lower than expected for the population. The incidence-rate-ratio for healthcare visits was lower in post-vaccination time windows than for control windows; after the first vaccine dose, the rate ratios for the risk periods of 0-1, 2-6, and 7-30 days post-vaccination were 0.3, 0.5, and 0.7, respectively (all statistically significantly different from the reference value of 1.0 for the 31-60 day control period). The liquid pentavalent vaccine was associated with lower rates of health care visits and not associated with increases in SAEs or hospitalizations. Systems can be set up in low to middle income countries to capture all health care visits to monitor the safety of new vaccines. Copyright © 2013 Elsevier Ltd. All rights reserved.

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

Safety analysis SFR 1. Long-term safety

International Nuclear Information System (INIS)

2008-12-01

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the regulatory

Safety analysis SFR 1. Long-term safety

Energy Technology Data Exchange (ETDEWEB)

2008-12-15

An updated assessment of the long-term safety of SKB's final repository for radioactive operational waste, SFR 1, is presented in this report. The report is included in the safety analysis report for SFR 1. The most recent account of long-term safety was submitted to the regulatory authorities in 2001. The present report has been compiled on SKB's initiative to address the regulatory authorities' viewpoints regarding the preceding account of long-term safety. Besides the new mode of working with safety functions there is another important difference between the 2001 safety assessment and the current assessment: The time horizon in the current assessment has been extended to 100,000 years in order to include the effect of future climate changes. The purpose of this renewed assessment of the long-term safety of SFR 1 is to show with improved data that the repository is capable of protecting human health and the environment against ionizing radiation in a long-term perspective. This is done by showing that calculated risks lie below the risk criteria stipulated by the regulatory authorities. SFR 1 is built to receive, and after closure serve as a passive repository for, low. and intermediate-level radioactive waste. The disposal chambers are situated in rock beneath the sea floor, covered by about 60 metres of rock. The underground part of the facility is reached via two tunnels whose entrances are near the harbour. The repository has been designed so that it can be abandoned after closure without further measures needing to be taken to maintain its function. The waste in SFR 1 is short-lived low- and intermediate-level waste. After 100 years the activity is less than half, and after 1,000 years only about 2% of the original activity remains. The report on long-term safety comprises eleven chapters. Chapter 1 Introduction. The chapter describes the purpose, background, format and contents of SAR-08, applicable regulations and injunctions, and the

Regulation Mechanism of the ald Gene Encoding Alanine Dehydrogenase in Mycobacterium smegmatis and Mycobacterium tuberculosis by the Lrp/AsnC Family Regulator AldR.

Science.gov (United States)

Jeong, Ji-A; Hyun, Jaekyung; Oh, Jeong-Il

2015-10-01

In the presence of alanine, AldR, which belongs to the Lrp/AsnC family of transcriptional regulators and regulates ald encoding alanine dehydrogenase in Mycobacterium smegmatis, changes its quaternary structure from a homodimer to an octamer with an open-ring conformation. Four AldR-binding sites (O2, O1, O4, and O3) with a consensus sequence of GA/T-N2-NWW/WWN-N2-A/TC were identified upstream of the M. smegmatis ald gene by means of DNase I footprinting analysis. O2, O1, and O4 are required for the induction of ald expression by alanine, while O3 is directly involved in the repression of ald expression. In addition to O3, both O1 and O4 are also necessary for full repression of ald expression in the absence of alanine, due to cooperative binding of AldR dimers to O1, O4, and O3. Binding of a molecule of the AldR octamer to the ald control region was demonstrated to require two AldR-binding sites separated by three helical turns between their centers and one additional binding site that is in phase with the two AldR-binding sites. The cooperative binding of AldR dimers to DNA requires three AldR-binding sites that are aligned with a periodicity of three helical turns. The aldR gene is negatively autoregulated independently of alanine. Comparative analysis of ald expression of M. smegmatis and Mycobacterium tuberculosis in conjunction with sequence analysis of both ald control regions led us to suggest that the expression of the ald genes in both mycobacterial species is regulated by the same mechanism. In mycobacteria, alanine dehydrogenase (Ald) is the enzyme required both to utilize alanine as a nitrogen source and to grow under hypoxic conditions by maintaining the redox state of the NADH/NAD(+) pool. Expression of the ald gene was reported to be regulated by the AldR regulator that belongs to the Lrp/AsnC (feast/famine) family, but the underlying mechanism was unknown. This study revealed the regulation mechanism of ald in Mycobacterium smegmatis and

Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

Science.gov (United States)

National Highway Traffic Safety Administration (DOT), Washington, DC.

Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…

75 FR 63774 - Pipeline Safety: Safety of On-Shore Hazardous Liquid Pipelines

Science.gov (United States)

2010-10-18

... DEPARTMENT OF TRANSPORTATION Pipeline and Hazardous Materials Safety Administration 49 CFR Part... Pipelines AGENCY: Pipeline and Hazardous Materials Safety Administration (PHMSA), Department of... Gas Pipeline Safety Act of 1968, Public Law 90-481, delegated to DOT the authority to develop...

State safety oversight program : audit of the tri-state oversight committee and the Washington metropolitan area transit authority, final audit report, March 4, 2010.

Science.gov (United States)

2010-03-04

The Federal Transit Administration (FTA) conducted an on-site audit of the safety program implemented by the Washington Metropolitan Area Transit Authority (WMATA) and overseen by the Tri-State Oversight Committee (TOC) between December 14 and 17, 20...

Safety and quality management for radiotherapy treatments - ASN guide nr 5 - Index 1 - Release of the 10/04/2009

International Nuclear Information System (INIS)

2009-01-01

This guide aims at proposing a framework for the safety and quality management for radiotherapy treatments. It addresses the general requirements for the quality management system (general requirements and requirements related to documentation), the management responsibility, the resource management (human and hardware resources), the preparation and performance of activities allowing the taking into care of a patient from his first consultation to the post-treatment follow-up, the assessment, analysis and improvement of the quality management system

MICROBIOLOGICAL SAFETY BIBLIOGRAPHY

Science.gov (United States)

More than a thousand articles on biological safety in infectious disease laboratories are listed for the use of supervisors responsible for the safety of laboratory personnel. An author index is included.

Beyond safety accountability

CERN Document Server

Geller, E Scott

2001-01-01

Written in an easy-to-read conversational tone, Beyond Safety Accountability explains how to develop an organizational culture that encourages people to be accountable for their work practices and to embrace a higher sense of personal responsibility. The author begins by thoroughly explaining the difference between safety accountability and safety responsibility. He then examines the need of organizations to improve safety performance, discusses why such performance improvement can be achieved through a continuous safety process, as distinguished from a safety program, and provides the practic

The 26. CLI national conference. Conference proceedings

International Nuclear Information System (INIS)

Chevet, Pierre-Franck; Niel, Jean-Christophe; Legrand, Henri; Dumont, Jean-Jacques; Lachaume, Jean-Luc; Delalonde, Jean-Claude; Sene, Monique; Le Deaut, Jean Yves; Charles, Thierry; Sasseigne, Philippe; Fournier, Nicolas; Murith, Christophe; Rivasi, Michele; Perissat, Frederic; KESSLER, Emmanuel

2014-12-01

This document gathers contributions presented during a conference held in December 2014. After introduction speeches and a focus of some updates by ANCCLI and ASN representatives, this conference comprised two round tables. The first one addressed the continuation of nuclear reactor operation after their fourth safety re-examination, with contributions by representatives of the ASN, of the ANCCLI, of the IRSN, and of EDF. The second one addressed the issue of a European harmonisation regarding actions of protection of populations in case of a nuclear accident, with interventions of representatives of a CLI, of the ASN, of the Swiss federal office for public health, of an NGO (Nuclear Transparency Watch), and of a departmental prefect

Industrial safety: its structuring and content

International Nuclear Information System (INIS)

Munoz, A.; Rodriguez, J.; Martinez-Val, J.M.

1999-01-01

Industrial development has led to an on-going increase in productivity, but the concept of safety has also become highly relevant. In this article, the authors address the structuring and content of industrial safety which involves laying down essential safety requirements, both in manufacturing and processes and in products. (Author)

Reactor safety; Description and evaluation of safety activities in Nordic countries

International Nuclear Information System (INIS)

Wahlstroem, B.; Gunsell, L.

1998-03-01

The report gives a description of safety activities in the nuclear power industry. The study has been carried out as a part of the four year programme in Nordic Safety Research (NKS) which was completed in 1997. The objective of the NKS/RAK-1.1 project 'A survey and an evaluation of safety activities in nuclear power' was to make a broad description of various activities important for safety and to make an assessment of their efficiency. A special consideration was placed on a comparison of practices in Finland and Sweden, and between their nuclear utilities. The study has been divided into two parts, one theoretical part in which a model of the relationships between various activities important for safety has been constructed and one practical part where a total of 62 persons have been interviewed at the authorities, the nuclear utilities and one reactor vendor. To restrict the amount of work two activities, safety analysis and experience feedback, were selected. A few cases connected to incidents at nuclear power plants were discussed in more detail. The report has been structured around a simple model of nuclear safety consisting of the concepts of goals, means and outcomes. This model illustrates the importance of goal formulation, systematic planning and feedback of operational experience as major components in nuclear safety. In assessing organisation and management at authorities and the power utilities there is a clear trend of decentralisation and delegation of authority. The general impression from the study is that the safety activities in Finland and Sweden are efficient and well targeted. The experience from the methodology is favourable and the comparison of practices gives a good ground for a discussion of contents and targeting of safety activities. (EG) activities. (EG)

Safety margins in deterministic safety analysis

International Nuclear Information System (INIS)

Viktorov, A.

2011-01-01

The concept of safety margins has acquired certain prominence in the attempts to demonstrate quantitatively the level of the nuclear power plant safety by means of deterministic analysis, especially when considering impacts from plant ageing and discovery issues. A number of international or industry publications exist that discuss various applications and interpretations of safety margins. The objective of this presentation is to bring together and examine in some detail, from the regulatory point of view, the safety margins that relate to deterministic safety analysis. In this paper, definitions of various safety margins are presented and discussed along with the regulatory expectations for them. Interrelationships of analysis input and output parameters with corresponding limits are explored. It is shown that the overall safety margin is composed of several components each having different origins and potential uses; in particular, margins associated with analysis output parameters are contrasted with margins linked to the analysis input. While these are separate, it is possible to influence output margins through the analysis input, and analysis method. Preserving safety margins is tantamount to maintaining safety. At the same time, efficiency of operation requires optimization of safety margins taking into account various technical and regulatory considerations. For this, basic definitions and rules for safety margins must be first established. (author)

Assessment of Safety Culture within the Pakistan Nuclear Regulatory Authority (PNRA)

Energy Technology Data Exchange (ETDEWEB)

Afzal, Muhammad [Pakistan Nuclear Regulatory Authority, Islamabad (Pakistan); Choi, Kwang Sik [Korea Institute of Nuclear Safety, Daejeon (Korea, Republic of)

2015-10-15

The objective of this study is to assess the SC of the Pakistan Nuclear Regulatory Authority (PNRA) by developing a performance indicator-based questionnaire. Aspects that potentially play important roles in developing perceptions of SC, including age, type of job, gender and duty hours of regulatory staff, are given due importance in this study. The study also identifies the strengths and weaknesses in the SC of the PNRA and can be used as a model study to assess the SC of other RBs. The questionnaire, developed to assess the SC of the PNRA, was in line with the PNRA's own defined attributes for SC. In the past, significant efforts have been made to ensure the safe operation of NPPs by improving designs and operating procedures; however, the nuclear accident at the Fukushima NPP in Japan in March 2011 revealed that the currently allotted hardware safety margins are not sufficient, and much work is needed to improve safety management in terms of SC. Initially, the concept of SC was introduced for operating organizations to ensure safe operation of NPPs; nonetheless, more recent investigations of nuclear events and accidents, especially Fukushima, and at Davis-Besse, in the US, have revealed that a strong focus is required to address and improve the SC of Regulatory Bodies (RBs). Strong SC is considered a vital tool for RBs to achieve their objectives and discharge their responsibilities in an effective and efficient manner. Though the relationship between the SC of RBs and that of operating organizations is not straight forward, it is believed that the former has a strong influence over the latter. The questionnaire was consistent in terms of the credible nature of its questions, and the response group covered different levels of PNRA staff, from managers to lower level staff. The results show that the PNRA staff have a very good understanding of the nature and significance of attributes of SC and are doing their best to exercise the same within the

Assessment of Safety Culture within the Pakistan Nuclear Regulatory Authority (PNRA)

International Nuclear Information System (INIS)

Afzal, Muhammad; Choi, Kwang Sik

2015-01-01

The objective of this study is to assess the SC of the Pakistan Nuclear Regulatory Authority (PNRA) by developing a performance indicator-based questionnaire. Aspects that potentially play important roles in developing perceptions of SC, including age, type of job, gender and duty hours of regulatory staff, are given due importance in this study. The study also identifies the strengths and weaknesses in the SC of the PNRA and can be used as a model study to assess the SC of other RBs. The questionnaire, developed to assess the SC of the PNRA, was in line with the PNRA's own defined attributes for SC. In the past, significant efforts have been made to ensure the safe operation of NPPs by improving designs and operating procedures; however, the nuclear accident at the Fukushima NPP in Japan in March 2011 revealed that the currently allotted hardware safety margins are not sufficient, and much work is needed to improve safety management in terms of SC. Initially, the concept of SC was introduced for operating organizations to ensure safe operation of NPPs; nonetheless, more recent investigations of nuclear events and accidents, especially Fukushima, and at Davis-Besse, in the US, have revealed that a strong focus is required to address and improve the SC of Regulatory Bodies (RBs). Strong SC is considered a vital tool for RBs to achieve their objectives and discharge their responsibilities in an effective and efficient manner. Though the relationship between the SC of RBs and that of operating organizations is not straight forward, it is believed that the former has a strong influence over the latter. The questionnaire was consistent in terms of the credible nature of its questions, and the response group covered different levels of PNRA staff, from managers to lower level staff. The results show that the PNRA staff have a very good understanding of the nature and significance of attributes of SC and are doing their best to exercise the same within the

33 CFR 147.5 - Delegation of authority.

Science.gov (United States)

2010-07-01

... 33 Navigation and Navigable Waters 2 2010-07-01 2010-07-01 false Delegation of authority. 147.5 Section 147.5 Navigation and Navigable Waters COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) OUTER CONTINENTAL SHELF ACTIVITIES SAFETY ZONES § 147.5 Delegation of authority. The authority to...

Hematological and Molecular Characterization of Hb J-Buda [α61(E10)Lys → Asn, AAG > AAT].

Science.gov (United States)

Panyasai, Sitthichai; Permsripong, Nopphadol; Jaiping, Kanokwan; Khantarag, Pisuttinee; Pornprasert, Sakorn

2016-06-01

Hemoglobin (Hb) J-Buda [α61(E10)Lys → Asn, AAG > AAT] is a very rare α-chain variant found in South-East Asia. We analyzed hematological parameters and provided a rapid molecular analysis method for detection of this hemoglobinopathy in two Thai women who had severe microcytic anemia with Hb and MCV AAG → AAT mutation at codon 61 for Hb J-Buda on one allele of the α1-globin gene. The developed Allele-specific PCR (ASPCR) showed the 455 bp amplified fragment from Hb J-Buda allele. Thus, understanding of hematological characterizations and the developed ASPCR for diagnosis of Hb J-Buda are essential for genetic counseling of this hemoglobinopathy.

International conference on the strengthening of nuclear safety in Eastern Europe. Keynote papers. Regulatory aspects of NPP safety, status of safety improvements, status of safety analysis report

International Nuclear Information System (INIS)

1999-06-01

The Objective of the Conference was to assess the past decade of nuclear safety efforts in countries operating WWER and RBMK nuclear reactors and to address remaining safety issues which require further work. A particular focus of the Conference was on international co-operation and assistance and where such efforts should be focused in the future. All Eastern European countries that operate RBMK or WWER reactors participated in the Conference, and presented papers on three key areas of nuclear safety: Regulatory Aspects of Nuclear Power Plant Safety; Status of Safety Improvements; and Status of Safety Analysis Reports. In addition, representatives from 18 additional countries that provide financial and/or technical assistance and co-operation in the area of WWER and RBMK safety offered the most extensive commentary. Key international (IAEA, World Association of Nuclear Operators, the Nuclear Energy Agency, the G-24 NUSAC, the European Commission, and the EBRD) organizations that provide nuclear safety assistance for WWER and RBMK reactors also made presentations. There is no question that considerable progress on nuclear safety has been made in Eastern Europe. Special mention should be made of successful efforts to strengthen the independence and technical competence of the nuclear regulatory authorities. Efforts should now concentrate on improving the depth and scope of the technical abilities of the regulatory authorities. More attention by governments is needed to ensure that the regulatory authorities have the financial resources and enforcement authority to fully execute their missions. In respect to the operators of the nuclear power plants, they have demonstrated clear progress in operational safety improvements. Significant additional efforts are required to maintain and enhance an effective safety culture. Design safety improvement programmes are in place in all countries. Implementation of these programmes has varied and is particularly affected by

Independent safety organization

International Nuclear Information System (INIS)

Kato, W.Y.; Weinstock, E.V.; Carew, J.F.; Cerbone, R.J.; Guppy, J.G.; Hall, R.E.; Taylor, J.H.

1985-01-01

Brookhaven National Laboratory has conducted a study on the need and feasibility of an independent organization to investigate significant safety events for the Office for Analysis and Evaluation of Operational Data, USNRC. The study consists of three parts: the need for an independent organization to investigate significant safety events, alternative organizations to conduct investigations, and legislative requirements. The determination of need was investigated by reviewing current NRC investigation practices, comparing aviation and nuclear industry practices, and interviewing a spectrum of representatives from the nuclear industry, the regulatory agency, and the public sector. The advantages and disadvantages of alternative independent organizations were studied, namely, an Office of Nuclear Safety headed by a director reporting to the Executive Director for Operations (EDO) of NRC; an Office of Nuclear Safety headed by a director reporting to the NRC Commissioners; a multi-member NTSB-type Nuclear Safety Board independent of the NRC. The costs associated with operating a Nuclear Safety Board were also included in the study. The legislative requirements, both new authority and changes to the existing NRC legislative authority, were studied. 134 references

Periodic safety review of the HTR-10 safety analysis

International Nuclear Information System (INIS)

Chen Fubing; Zheng Yanhua; Shi Lei; Li Fu

2015-01-01

Designed by the Institute of Nuclear and New Energy Technology (INET) of Tsinghua University, the 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first modular High Temperature Gas-cooled Reactor (HTGR) in China. According to the nuclear safety regulations of China, the periodic safety review (PSR) of the HTR-10 was initiated by INET after approved by the National Nuclear Safety Administration (NNSA) of China. Safety analysis of the HTR-10 is one of the key safety factors of the PSR. In this paper, the main contents in the review of safety analysis are summarized; meanwhile, the internal evaluation on the review results is presented by INET. (authors)

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2013-08-15

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

Reports by the Parliamentary Office for scientific and technological assessments. Tuesday, May 24, 2011. Hearing on the protection of a reactor core and critical circuit; Comptes rendus de l' Office Parlementaire d'Evaluation des Choix Scientifiques et Technologiques. Mardi 24 mai 2011. Audition sur la protection du coeur et des circuits critiques d'un reacteur

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-05-15

In the context created by the Fukushima accident, members of the French Parliament, representatives of the French nuclear safety authority (ASN), of the French Institute for radiation protection and nuclear safety (IRSN), and of the CEA describe and discuss the technical aspects and mechanism of defence-in-depth of nuclear reactors (i.e. the different and successive levels of protection aimed at ensuring the reactor integrity to be maintained, even in case of failure of a critical circuit). Then, they discuss advances and researches in the field of protection of reactors. Several research programs are evoked which concern different elements of a nuclear plants such as the fuel, the reactor, loss of cooling system, and so on; these programs are based either on experiments or on simulations

2011 reporting of the risk handling at CEA

International Nuclear Information System (INIS)

Anon.

2012-01-01

In 2011 CEA reported 100 events to the Authority for Nuclear Safety (ASN). 93 were graded 0 on the INES scale and 7 were graded 1. None of them had a significant impact on the staff health and the environment. 25% of these events concerned delays in the controls of safety equipment. In 2011 CEA had to manage several situations that led to a response of its crisis center: 1) the explosion of an oven belonging to the Socodei-Centraco company situated near the Marcoule Center, 2) the discovery of about 500 grenades from the first world war during digging out works in the Grenoble Center, 3) flooding due to heavy rains in the Cadarache Center, and 4) an intrusion attempt at the Cadarache Center. (A.C.)

INES scale: French application to radioactive material transport

International Nuclear Information System (INIS)

Sowinski, S.; Strawa, S.; Aguilar, J.

2004-01-01

After getting the control of radioactive material transport in June 1997, the French safety Authority (ASN) decided to apply the INES scale to transport events. DGSNR (Directorate General for Nuclear Safety and Radioprotection) requests that radioactive material package consignors declare any event occurring during transportation, and has introduced the use of the INES scale adapted to classify transport events in order to inform the public and to have feedback. This paper deals with DGSNR's feedback during the past seven years concerning the french application of the INES scale. Significant events that occurred during transportation are presented. The French experience was used by IAEA to develop a draft guide in 2002 and IAEA asked countries to use a new draft for a trial period in July 2004

Accelerator production of tritium authorization basis strategy

International Nuclear Information System (INIS)

Miller, L.A.; Edwards, J.; Rose, S.

1996-01-01

The Accelerator Production of Tritium (APT) project has proposed a strategy to develop the APT authorization basis and safety case based on DOE orders and fundamental requirements for safe operation. The strategy is viable regardless of whether the APT is regulated by DOE or by an external regulatory body. Currently the operation of Department of Energy (DOE) facilities is authorized by DOE and regulated by DOE orders and regulations while meeting the environmental protection requirements of the Environmental Protection Agency (EPA) and the states. In the spring of 1994, Congress proposed legislation and held hearings related to requiring all DOE operations to be subject to external regulation. On January 25, 1995, DOE, with the support of the White House Council on Environmental Quality, created the Advisory Committee on External Regulation of Department of Energy Nuclear Safety. This committee divided its recommendations into three areas: (1) facility safety, (2) worker safety, and (3) environmental protection. In the area of facility safety the committee recommended external regulation of DOE nuclear facilities by either the Nuclear Regulatory Commission (NRC) or a restructured Defense Nuclear Facilities Safety Board (DNFSB). In the area of worker safety, the committee recommended that the Occupational Safety and Health Administration (OSHA) regulate DOE nuclear facilities. In the environmental protection area, the committee did not recommend a change in the regulation by the EPA and the states of DOE nuclear facilities. If these recommendations are accepted, all DOE nuclear facilities will be impacted to some extent

Regulatory role and approach of BARC Safety Council in safety and occupational health in BARC facilities

International Nuclear Information System (INIS)

Rajdeep; Jayarajan, K.; Taly, Y.K.

2016-01-01

Bhabha Atomic Research Centre is involved in multidisciplinary research and developmental activities, related to peaceful use of nuclear energy and its societal benefits. In order to achieve high level of performance of these facilities, the best efforts are made to maintain good health of the plant personnel and good working conditions. BARC Safety Council (BSC), which is the regulatory body for BARC facilities, regulates radiation safety, industrial safety and surveillance of occupational health, by implementing various rules and guidelines in BARC facilities. BARC Safety framework consists of various committees in a 3-tier system. The first tier is BSC, which is the apex body authorized for issuing directives, permissions, consents and authorizations. It is having responsibility of ensuring protection and safety of public, environment, personnel and facilities of BARC through enforcement of radiation protection and industrial safety programmes. Besides the 18 committees in 2"n"d tier, there are 6 other expert committees which assist in functioning of BSC. (author)

Safety performance indicators program

International Nuclear Information System (INIS)

Vidal, Patricia G.

2004-01-01

In 1997 the Nuclear Regulatory Authority (ARN) initiated a program to define and implement a Safety Performance Indicators System for the two operating nuclear power plants, Atucha I and Embalse. The objective of the program was to incorporate a set of safety performance indicators to be used as a new regulatory tool providing an additional view of the operational performance of the nuclear power plants, improving the ability to detect degradation on safety related areas. A set of twenty-four safety performance indicators was developed and improved throughout pilot implementation initiated in July 1998. This paper summarises the program development, the main criteria applied in each stage and the results obtained. (author)

EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

Energy Technology Data Exchange (ETDEWEB)

Erven, Ulrich (ed.) [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard (ed.) [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De (ed.) [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

2005-07-01

The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

EUROSAFE Forum for nuclear safety. Towards Convergence of Technical Nuclear Safety Practices in Europe. Safety Improvements - Reasons, Strategies, Implementation

Energy Technology Data Exchange (ETDEWEB)

Erven, Ulrich [Gesellschaft fuer Anlagen- und Reaktorsicherheit, GRS mbH, Schwertnergasse 1, 50667 Koeln (Germany); Cherie, Jean-Bernard [Institut de Radioprotection et de Surete Nucleaire, IRSN, BP 17, 92262 Fontenay-aux-Roses Cedex (France); Boeck, Benoit De [Association Vincotte Nuclear, AVN, Rue Walcourt 148, 1070 Bruxelles (Belgium)

2005-07-01

The EUROSAFE Forum for Nuclear Safety is part of the EUROSAFE approach, which consists of two further elements: the EUROSAFE Tribune and the EUROSAFE Web site. The general aim of EUROSAFE is to contribute to fostering the convergence of technical nuclear safety practices in a broad European context. This is done by providing technical safety and research organisations, safety authorities, power utilities, the rest of the industry and non-governmental organisations mainly from the European Union and East-European countries, and international organisations with a platform for the presentation of recent analyses and R and D in the field of nuclear safety. The goal is to share experiences, to exchange technical and scientific opinions, and to conduct debates on key issues in the fields of nuclear safety and radiation protection. The EUROSAFE Forum on 2005 focused on Safety Improvements, Reasons - Strategies - Implementation, from the point of view of the authorities, TSOs and industry. Latest work in nuclear installation safety and research, waste management, radiation safety as well as nuclear material and nuclear facilities security carried out by GRS, IRSN, AVN and their partners in the European Union, Switzerland and Eastern Europe are presented. A high level of nuclear safety is a priority for the countries of Europe. The technical safety organisations play an important role in contributing to that objective through appropriate approaches to major safety issues as part of their assessments and research activities. The challenges to nuclear safety are international. Changes in underlying technologies such as instrumentation and control, the impact of electricity market deregulation, demands for improved safety and safety management, the ageing of nuclear facilities, waste management, maintaining and improving scientific and technical knowledge, and the need for greater transparency - these are all issues where the value of an international approach is gaining

Safety design guide for safety related systems for CANDU 9

International Nuclear Information System (INIS)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young; A. C. D. Wright

1996-03-01

In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new

Safety design guide for safety related systems for CANDU 9

Energy Technology Data Exchange (ETDEWEB)

Lee, Duk Su; Chang, Woo Hyun; Lee, Nam Young [Korea Atomic Energy Research Institute, Daeduk (Korea, Republic of); Wright, A.C.D. [Atomic Energy of Canada Ltd., Toronto (Canada)

1996-03-01

In general, two types of safety related systems and structures exist in the nuclear plant; The one is a systems and structures which perform safety functions during the normal operation of the plant, and the other is a systems and structures which perform safety functions to mitigate events caused by failure of the normally operating systems or by naturally occurring phenomena. In this safety design guide, these systems are identified in detail, and the major events for which the safety functions are required and the major safety requirements are identified in the list. As the probabilistic safety assessments are completed during the course of the project, additions or deletions to the list may be justified. 3 tabs. (Author) .new.

New Safety rules

CERN Multimedia

Safety Commission

2008-01-01

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

Improvements related with the safety required by the Argentine Regulatory Authority to the Atucha I Nuclear Central

International Nuclear Information System (INIS)

Calvo, J.; Michelin, C.; Navarro, R.; Waldman, R.

2006-01-01

The Argentinean Nuclear Regulation Authority (ARN) verified the existence of changes in the state of some internal components of the reactor of the Atucha I Nuclear Power station that, of continuing in the time, it could take to an inconvenient degradation for the safety operation of the installation. In consequence, to the effects of preventing that reach this situation, at the end of 1999, the ARN required to the Responsible Entity for the operation of this power station the implementation of an important improvements program in the internal components of the reactor. Additionally, and based on the results of the Probabilistic Safety analysis, it was added the one mentioned improvements program the implementation of an alternative cooling system of the reactor core denominated Second Drain of Heat, due to it was determined that, for some accidental sequences, their performance would reduce considerably the probability of damage to the core. The concretion of the improvements program implied to the Responsible Entity the realization of an important quantity of engineering studies, tests and specific inspections that allowed to carry out changes on the control bars of the reactor and its guide tubes; the coolant channels; the sensors of neutron flow; and diverse components of the primary and moderator systems. On the other hand also it was implemented the system Second Drain of Heat, what represents a considerable effort to make compatible the instrumentation and control of last generation, with the instrumentation and existent control systems in the power station. Also, it was requested to be carried out an integrity of the pressure recipient for to demonstrate the existence of an acceptable margin for the difference among the acceptable limit temperatures and of ductile/fragile transition of the material for all the possible accidental scenarios during the useful life of the reactor. (Author)

IAEA safety standards and approach to safety of advanced reactors

International Nuclear Information System (INIS)

Gasparini, M.

2004-01-01

The paper presents an overview of the IAEA safety standards including their overall structure and purpose. A detailed presentation is devoted to the general approach to safety that is embodied in the current safety requirements for the design of nuclear power plants. A safety approach is proposed for the future. This approach can be used as reference for a safe design, for safety assessment and for the preparation of the safety requirements. The method proposes an integration of deterministic and risk informed concepts in the general frame of a generalized concept of safety goals and defence in depth. This methodology may provide a useful tool for the preparation of safety requirements for the design and operation of any kind of reactor including small and medium sized reactors with innovative safety features.(author)

Leadership and Safety Culture: Leadership for Safety

International Nuclear Information System (INIS)

Fischer, E.

2016-01-01

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