Canadian Nuclear Safety Commission's intern program

International Nuclear Information System (INIS)

Gilmour, P.E.

2002-01-01

The Intern Program was introduced at the Canadian Nuclear Safety Commission, Canada's Nuclear Regulator in response to the current competitive market for engineers and scientists and the CNSC's aging workforce. It is an entry level staff development program designed to recruit and train new engineering and science graduates to eventually regulate Canada's nuclear industry. The program provides meaningful work experience and exposes the interns to the general work activities of the Commission. It also provides them with a broad awareness of the regulatory issues in which the CNSC is involved. The intern program is a two-year program focusing on the operational areas and, more specifically, on the generalist functions of project officers. (author)

The Canadian Nuclear Safety Commission's financial guarantee requirements

International Nuclear Information System (INIS)

Ferch, R.

2006-01-01

The Nuclear Safety and Control Act gives the Canadian Nuclear Safety Commission (CNSC) the legal authority to require licensees to provide financial guarantees in order to meet the purposes of the Act. CNSC policy and guidance with regard to financial guarantees is outlined, and the current status of financial guarantee requirements as applied to various CNSC licensees is described. (author)

Safety improvement and results of commissioning of Mochovce NPP WWER 440/213

International Nuclear Information System (INIS)

Lipar, M.

1998-01-01

Mochovce NPP is the last one of this kind and compared to its predecessors, it is characterized by several modifications which contribute to the improvement of the safety level. In addition based on Nuclear Regulatory Authority requirements and based on documents: - IAEA - Safety Issues and their ranking for NPP WWER 440/213, - IAEA - Safety Improvement of Mochovce NPP Project Review Mission, - Riskaudit - Evaluation of the Mochovce NPP Safety Improvements. Additional safety measures have been implemented before commissioning. The consortium EUCOM (FRAMATOME - SIEMENS), SKODA Praha, ENERGOPROJEKT Praha, Russian organizations and VUJE Trnava Nuclear Power Plants research institute were selected for design and implementation of the safety measures. The papers summarized, safety requirements, safety measures implemented, results of commissioning and results of safety analysis report evaluation. (author)

UPSAT guidelines. 1996 edition. Reference document for IAEA Uranium Productions Safety Assessment Teams (UPSATs)

International Nuclear Information System (INIS)

1996-05-01

The IAEA Uranium Production Safety Assessment Team (UPSAT) programme provides advice and assistance to Member States to enhance the safety and environmental performance of uranium production facilities during construction, commissioning and operation. Sound design and construction are prerequisite for the safe and environmentally responsible operation of uranium mines and mills. However, the safety of the facility depends ultimately on sound policies, procedures and practices; on the capability and reliability of the construction, commissioning and operating personnel; on comprehensive instructions; and on adequate resources. A positive attitude and conscientiousness on the part of the management and staff in discharging their responsibilities is important to safety. The UPSAT guidelines have been developed in the following areas: (1) management, organization and administration; (2) training and qualification; (3) operation (4) maintenance; (5) safety, fire protection, emergency planning, and preparedness; (6) radiation protection; (7) environmental monitoring programme; (8) construction management; (9) commissioning and decommissioning

Outreach at the Canadian Nuclear Safety Commission - An Aboriginal Peoples' Perspective

International Nuclear Information System (INIS)

Lojk, R.; Ben Belfakhel, M.

2006-01-01

Established by the Nuclear Safety and Control Act (NSCA) that came into force in May 2000, the Canadian Nuclear Safety Commission (CNSC) is an independent federal agency that reports to Parliament through the Minister of Natural Resources. The CNSC regulates all uses of nuclear energy and nuclear materials from the production, to use, to the final disposition of any nuclear substances. Under the NSCA, the CNSC has the mandate to: - Regulate the development, production and use of nuclear energy and materials to protect the health, safety, security and environment; - Regulate production, possession and use of nuclear substances, prescribed equipment and prescribed information; - Implement measures respecting international commitments on the peaceful use of nuclear energy and substances; - Disseminate scientific, technical and regulatory information concerning CNSC activities. The main regulatory activities include setting regulatory standards, issuing licenses, verifying compliance and communicating with stakeholders and the public. These activities are accomplished by the work of two independent entities: a commission of up to seven members and a staff of about 500 employees. The Commission is an independent, quasi-judicial tribunal that provides licensing decisions on nuclear-related activities in a public forum. The President of the tribunal is the CEO of the CNSC staff organization. CNSC's regulatory philosophy is based on two principles: - Those persons and organizations subject to the NSCA and its Regulations are directly responsible for ensuring that the regulated activities that they engage in are managed so as to protect health, safety, security and the environment and to respect Canada's international commitments on the peaceful use of nuclear energy. - The CNSC is responsible to the public for regulating persons and organisations subject to the Nuclear Safety and Control Act and regulations to assure that they are properly discharging their obligations

29 CFR 2200.108 - Official Seal of the Occupational Safety and Health Review Commission.

Science.gov (United States)

2010-07-01

... 29 Labor 9 2010-07-01 2010-07-01 false Official Seal of the Occupational Safety and Health Review... Occupational Safety and Health Review Commission. The seal of the Commission shall consist of: A gold eagle... background, encircled by a white band edged in black and inscribed “Occupational Safety and Health Review...

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

International Nuclear Information System (INIS)

2006-01-01

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

77 FR 10358 - Acceptance of ASTM F963-11 as a Mandatory Consumer Product Safety Standard

Science.gov (United States)

2012-02-22

... CONSUMER PRODUCT SAFETY COMMISSION 16 CFR Chapter II Acceptance of ASTM F963-11 as a Mandatory... have accepted the revised ASTM F963-11 standard titled, Standard Consumer Safety Specifications for Toy Safety. Pursuant to section 106 of the Consumer Product Safety Improvement Act of 2008, ASTM F963-11 will...

Playground Safety

Science.gov (United States)

... Prevention Fall Prevention Playground Safety Poisoning Prevention Road Traffic Safety Sports Safety Get Email Updates To receive ... at the Consumer Product Safety Commission’s Playground Safety website . References U.S. Consumer Product Safety Commission. Injuries and ...

[Safety monitoring of cell-based medicinal products (CBMPs)].

Science.gov (United States)

Funk, Markus B; Frech, Marion; Spranger, Robert; Keller-Stanislawski, Brigitte

2015-11-01

Cell-based medicinal products (CBMPs), a category of advanced-therapy medicinal products (ATMPs), are authorised for the European market by the European Commission by means of the centralized marketing authorisation. By conforming to the German Medicinal Products Act (Sec. 4b AMG), national authorisation can be granted by the Paul-Ehrlich-Institut in Germany exclusively for ATMPs not based on a routine manufacturing procedure. In both procedures, quality, efficacy, and safety are evaluated and the risk-benefit balance is assessed. For the centralised procedure, mainly controlled clinical trial data must be submitted, whereas the requirements for national procedures could be modified corresponding to the stage of development of the ATMP. After marketing authorization, the marketing authorization/license holder is obligated to report all serious adverse reactions to the competent authority and to provide periodic safety update reports. If necessary, post-authorization safety studies could be imposed. On the basis of these regulatory measures, the safety of advanced therapies can be monitored and improved.

75 FR 52046 - Development of U.S. Nuclear Regulatory Commission Safety Culture Policy Statement: Public Meeting

Science.gov (United States)

2010-08-24

... is working towards increasing the attention that is given to safety culture as part of its efforts to... NUCLEAR REGULATORY COMMISSION Development of U.S. Nuclear Regulatory Commission Safety Culture..., Nevada hearing facility to solicit comments on the revision of its draft safety culture policy statement...

Findings by the Commission Evaluating Nuclear Safety and Repository Research in Germany

International Nuclear Information System (INIS)

Sandtner, W.; Closs, K.D.

2000-01-01

The Commission Evaluating Nuclear Safety and Repository Research in Germany, which had been appointed by the German Federal Ministry of Economics on September 24, 1999, submitted its report. Here is the gist of the Commission's findings: Irrespective of the criteria established with the political decision to terminate the use of nuclear power in Germany, competence in nuclear safety must be maintained over the next few decades. Only in this way can the government perform its duty and make provisions for the future, and can the safety of nuclear facilities and waste management pathways be ensured in accordance with the international state of the art. In view of the considerable reduction in funding in recent years and also in future, measures must be taken to ensure that further decreases in-roject funding and institutionalized government financing are excluded so as to avoid further declines in terms of manpower and competence in this field. Reactor safety and repository research must be financed at a level allowing the federal government to discharge its legal duties. The full report by the Commission, with its annexes, is available on the GRS web site (http://www.grs.de) as a PDF file. (orig.) [de

76 FR 10556 - Codex Alimentarius Commission: Meeting of the Codex Committee on Fish and Fishery Products

Science.gov (United States)

2011-02-25

... Amendment to the Standard for Quick Frozen Fish Sticks. Proposed Food Additive Provisions in Standards for... DEPARTMENT OF AGRICULTURE Food Safety and Inspection Service [Docket No. FSIS-2010-0036] Codex Alimentarius Commission: Meeting of the Codex Committee on Fish and Fishery Products AGENCY: Office of the...

Management of fire and industrial safety - challenges during commissioning of a NPP

International Nuclear Information System (INIS)

Maiti, Subhaschandra; Mohan, Nalini; Ghadge, S.G.; Bajaj, S.S.

2006-01-01

Construction and commissioning period of NPP are reduced world over drastically by stringent schedule for financial and economic reasons. For meeting the schedule, commissioning of components and systems are started immediate after installation, while construction activities are continued in parallel at the same place. Parallel activities' and 'Time Constraint' have brought new challenges to 'Management of Fire and Industrial Safely' during commissioning. An innovative approach was used during such phase of commissioning of TAPP-3 and 4. This paper outlines challenges encountered during this phase and special approach and measures used to meet those challenges. This paper also outlines problems encountered during implementation of these measures and subsequent change in approach to ensure smooth and safe execution of activities. Primarily, challenges were conflicting requirements by various agencies to carryout commissioning in parallel with construction activities concurrently. Main challenges were related to fall hazard, chemical hazard, fire hazard, electrical safety, work in confined space, housekeeping problem. Moreover it was within exclusion zone of another operating plant, which added one more dimension to those challenges. Conventional Safely management approach was little short to resolve these challenges. Such challenges were envisaged; analyzed and innovative measures were arrived at. Along with conventional safely analysis like Job Safely or Hazard Analysis (JSA or JHA), Accident Analysis, Accident Trend Analysis, Fire Hazard Analysis (FHA), innovative method like 'Area-Job- Hazard Charting' and 'Ratio Analysis' were used to understand activity dependent time varying hazard scenarios. Based on this analysis, decision were taken to change various existing elements of safely management like safety organizations; standard operating procedures (SOP); emergency operating procedures (EOP); resource allocation, planning and scheduling; safely training; safely

SaferProducts API

Data.gov (United States)

US Consumer Product Safety Commission — On March 11, 2011, the U.S. Consumer Product Safety Commission launched SaferProducts.gov. This site hosts the agency's new Publicly Available Consumer Product...

Energy. Health, environment, and safety hazards. Final report from the Energy Commission. Energi. Haelso- miljoe- och saekerhetsrisker. Slutbetaenkande av energikommissionen

Energy Technology Data Exchange (ETDEWEB)

1978-01-01

The Swedish Energy Commission in its main report (''Energy'', SOU 1978:17) presented its considerations and put forward its proposals for a Swedish Energy policy for the next decade. This report contains complementary information on health hazards, risks of major accidents and sabotage, and problems of waste management. The presentation takes the form of a comparison of such risks in relation to different sources of energy. The Commission is not unanimous in its estimates of the relative hazards of different energysystems. The Commission recommends the initiation of a large number of studies concerning the possible ways the increase the safety and reduce the adverse effects of energy production.

Ordinance of 14 March 1983 concerning the Federal Commission for the Safety of Nuclear Installations

International Nuclear Information System (INIS)

1983-01-01

The Frederal Council issued a new Ordinance concerning the Federal Commission for the Safety of Nuclear Installations. This Ordinance replaces an Ordinance of 13 June 1960 and takes into account the distribution of tasks decided several years ago between the Commission, which operates on a part-time basis, and the principal Division for the Safety of Nuclear Installations attached to the Federal Office of Energy. (NEA) [fr

Reactor safety research program. A description of current and planned reactor safety research sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research

International Nuclear Information System (INIS)

1975-06-01

The reactor safety research program, sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, is described in terms of its program objectives, current status, and future plans. Elements of safety research work applicable to water reactors, fast reactors, and gas cooled reactors are presented together with brief descriptions of current and planned test facilities. (U.S.)

16 CFR 1031.6 - Extent and form of Commission involvement in the development of voluntary standards.

Science.gov (United States)

2010-01-01

..., engineering support, and information and education programs) and administrative assistance (e.g., travel costs... SAFETY COMMISSION GENERAL COMMISSION PARTICIPATION AND COMMISSION EMPLOYEE INVOLVEMENT IN VOLUNTARY... goals and objectives with regard to voluntary standards and improved consumer product safety; responding...

16 CFR 1015.10 - Commission report of actions to Congress.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Commission report of actions to Congress. 1015.10 Section 1015.10 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION GENERAL PROCEDURES FOR... U.S.C. 552(a) § 1015.10 Commission report of actions to Congress. On or before February 1 of each...

Reactor safety: a discussion by officials of the Nuclear Regulatory Commission

International Nuclear Information System (INIS)

Anders, W.A.; Rusche, B.C.; Stello, V. Jr.; Minogue, R.B.

1976-01-01

William A. Anders, Chairman of the Nuclear Regulatory Commission (NRC), and several senior officials spoke to the Joint Committee on Atomic Energy on the subject of nuclear safety, improvements in reactor plant safety, and quality assurance. The NRC, during its first year of organization, has developed new initiatives to improve safety and safeguards regulations. Anders stressed that NRC is not stifling internal discussion of opposing views, that it has been honest with the public, and that operating reactors are meeting rigorous safety standards. Other speakers discussed comparative safety of old and new reactors. Backfitting of older plants with new features is done when substantial safety protection can be added, but detuning an integrated system is not done indiscriminately. Officials of NRC do not agree with former General Electric employees, who testified that the regulatory procedure is inadequate. Safety improvements since August 28, 1962 and outlines of the review process are included in the Appendixes

Report by USSR survey mission of Nuclear Safety Commission

International Nuclear Information System (INIS)

1990-01-01

The USSR survey mission of Nuclear Safety Commission drew up and presents the report as follows. In relation to the accident in Chernobyl Nuclear Power Station in USSR, in order to investigate into the present status of the countermeasures for nuclear power safety in USSR and to exchange opinion, the USSR survey mission inspected nuclear power station facilities and visited the government organs, research institutes and others in USSR. The survey mission comprised 13 members, and went to Moscow, Kiev and two nuclear power station sites, from October 22 to November 1, 1989, for 11 days. At present in USSR, 49 nuclear power plants of about 35 GWe are in operation, and by 2000, the operation of more nuclear power plants of about 30 GWe is needed, but due to the change of social situation in USSR, its attainment seems to be difficult. The plan of nuclear power generation in USSR, the ensuring of safety in general, the recent countermeasures for improving safety, the effect of the accident in Chenobyl Nuclear Power Station on health and so on are reported. The detailed record of the visit to Zaporozhe and Chernobyl Nuclear Power Stations and 7 other research institutes and government organs is given. (K.I.)

The European Commission proposes changes to the directive on nuclear safety

International Nuclear Information System (INIS)

Anon.

2013-01-01

The European Commission proposes changes in the ancient European directive on nuclear safety in order to europeanize nuclear safety. The first proposal is to submit all European nuclear facilities to a control every 6 years by a board of foreign experts. Another proposal is to impose that every new power plant should be designed so that the radiological impact of an accident should be limited to the facility itself. The same proposal would impose for every nuclear plant the presence of an emergency center resistant to radiation, earthquakes and floods. The reporting of any incident occurring in a nuclear plant would be made compulsory. The decision to extend the operating life of a nuclear plant would be suspended to the results of a compulsory safety test. (A.C.)

Animal Product Safety Information

Science.gov (United States)

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

Canada's regulatory framework: The Canadian Nuclear Safety Commission's regulatory framework

International Nuclear Information System (INIS)

Howard, D.

2011-01-01

This paper will discuss the Canadian Nuclear Safety Commission and Canada's Regulatory Framework with respect to Low- and Intermediate-Level Radioactive Waste. The management of low and intermediate level radioactive waste must be ensured in a consistent, environmentally responsible and economical manner throughout its lifecycle -- from its production to the final disposal option. Radioactive waste has been produced in Canada since the early 1930s when the first radium/uranium mine began operating at Port Radium in the Northwest Territories. Pitchblende ore was transported from the Port Radium mine to Port Hope, Ontario where it was refined to produce radium for medical purposes. At present, radioactive waste is generated in Canada from the various stages and uses associated with the nuclear fuel cycle from uranium mining/milling to nuclear reactor operations to radioisotope manufacture and use. The Canadian Nuclear Safety Commission (CNSC regulates the use of nuclear energy and materials to protect the health, safety and security of Canadians and the environment; and to implement Canada's international commitments on the peaceful use of nuclear energy. The CNSC was established in 2000 under the Nuclear Safety and Control Act and reports to Parliament through the Minister of Natural Resources. The CNSC was created to replace the former Atomic Energy Control Board (AECB), which was founded in 1946. Under the Nuclear Safety and Control Act, CNSC's mandate involves four major areas: regulation of the development, production and use of nuclear energy in Canada to protect health, safety and the environment; regulation of the production, possession, use and transport of nuclear substances, and the production, possession and use of prescribed equipment and prescribed information; implementation of measures respecting international control of the development, production, transport and use of nuclear energy and substances, including measures respecting the

The preparation and implementation of the commissioning of Qinshan nuclear power plant

International Nuclear Information System (INIS)

Huang Jinyuan

1993-05-01

The commissioning test of Qinshan Nuclear Power Plant is summarized. The preparation stage includes the organizations, commissioning programme, network planning, commissioning items, management procedures, responsibilities and interfaces between divisions, products ordering and supplying, personal training, quality assurance and the review and supervision by National Nuclear Safety Administration etc. The implementation stage includes the commissioning programme planning, intermediate hand-over inspection of the system and equipment, inspecting conditions and setting organizations for commissioning, the transition from commissioning to operating. Finally, some experiences in the commissioning test are presented in the article

Action by the European Commission to promote nuclear safety outside the territory of the Union

International Nuclear Information System (INIS)

Joulia, J.P.

2010-01-01

The TACIS programme to improve nuclear safety in Central and Eastern Europe and the former USSR has now entered its final phase. A new programme 'the Instrument for Nuclear Safety Cooperation (INSC)' has been launched and its aim is to promote nuclear safety in all third-party countries. Support for improvement of the regulatory framework and the effectiveness of the bodies in charge of nuclear safety is a key element. Within the European Commission, the 'Europe, Southern Mediterranean, Middle East and Neighbourhood policy' Directorate, belonging to the AIDCO General Directorate, is tasked with implementation. (author)

Commissioning an Engineering Scale Coal Gasifier

Energy Technology Data Exchange (ETDEWEB)

Reid, Douglas J.; Bearden, Mark D.; Cabe, James E.

2010-07-01

This report explains the development, commissioning, and testing of an engineering scale slagging coal gasifier at PNNL. The initial objective of this project was to commission the gasifier with zero safety incidents. The commissioning work was primarily an empirical study that required an engineering design approach. After bringing the gasifier on-line, tests were conducted to assess the impact of various operating parameters on the synthesis gas (syngas) product composition. The long-term intent of this project is to produce syngas product for use by internal Pacific Northwest National Laboratory (PNNL) researchers in catalyst, materials, and instrumentation development. Future work on the project will focus on improving the reliability and performance of the gasifier, with a goal of continuous operation for greater than 4 hours using coal feedstock. In addition, alternate designs that allow for increased flexibility regarding the fuel sources that can be used for syngas production is desired. Continued modifications to the fuel feed system will be pursued to address these goals. Alternative feed mechanisms such as a coal/methanol slurry are being considered.

The U.S. Nuclear Regulatory Commission seismic safety research program

International Nuclear Information System (INIS)

Kenneally, R.M.; Guzy, D.J.; Murphy, A.J.

1988-01-01

The seismic safety research program sponsored by the U.S. Nuclear Regulatory Commission is directed toward improving the evaluation of potential earthquake effects on nuclear power plant operations. The research has been divided into three major program areas: earth sciences, seismic design margins, and fragilities and response. A major thrust of this research is to assess plant behavior for seismic events more severe and less probable than those considered in design. However, there is also research aimed at improving the evaluation of earthquake input and plant response at plant design levels

Announcement of recommendations by the Reactor Safety Commission (RSK), presented at its 184. meeting on March 23, 1983

International Nuclear Information System (INIS)

1983-01-01

The Reactor Safety Commission concluded that from the safety engineering point of view there are no misgivings about granting a licence under atomic energy law for away-from-reactor storage and operation of the transport container store at Ahaus and Gorleben. (orig.) [de

Recommendations of the Reactor Safety Commission, 1971--1974

International Nuclear Information System (INIS)

The Reactor Safety Commission (RSC) of the German Federal Republic was created in 1958 by the then Federal Minister for Atomic Energy and Hydroeconomy. Its task included the advising of the Federal Minister responsible for protection of the population from possible dangers occurring during peaceful utilization of nuclear energy and in all matters of the safety of nuclear oriented installations. The RSC consists of independent experts from differing specialty areas. The results of their consultations are passed on in recommendations to the appropriate Federal Minister. Since the reappointment and reorganization of the RSC in the year 1971 by the then Federal Minister for Education and Science, the recommendations have been published in the ''Federal Gazette.'' The report presented is divided into two parts with a three part appendix. All recommendations of the RSC made since the reorganization (68th Meeting on 3 November 1971) until expiration of the last appointment, (96th Meeting on 25 July 1974) are compiled in the first section. The second part contains all announcements of the RSC which have appeared in the ''Federal Gazette.'' These concern training, agenda, as well as current members. Appendix A includes the ''Guidelines for Pressurized Water Reactors'' approved in the 93rd Meeting on 24 April 1974. Two key word listings follow in Sections B and C of the Appendix. The report was prepared in behalf of the Federal Minister of the Interior through the Office of the RSC assigned to the Institute for Reactor Safety of the Technical Inspection Association (IRS). The report is continued at regular intervals following each meeting period

The commissioning of nuclear power plants

International Nuclear Information System (INIS)

1989-09-01

The objectives and requirements to be met in commissioning nuclear power plants are presented. The objective of commissioning is to ensure that each component, subsystem, system, or structure in a plant will be capable of fulfilling its design requirements throughout its design life. The requirements for commissioning are: the preparation of a detailed, comprehensive, documented program to demonstrate that all components, systems and structures relevant to safety meet design intent; documented evidence that safety systems are fully operable and can meet design requirements; and, appropriate documentation of the actual state or behaviour of all components, systems and structures relevant to safety. All systems must be included in the commissioning program. Whenever possible, full safety system test should be performed. If a full system in situ test is not possible, alternative means are suggested. (8 refs.)

Role of the team of scientific and technical commissioning support (TSTCS) during Mochovce NPP unit 3 and 4 commissioning

International Nuclear Information System (INIS)

Hermansky, J.; Prachar, M.; Sedlacek, M.; Petenyi, V.

2011-01-01

The Team of Scientific and Technical Commissioning Support (TSTCS) shall provide an independent support for the Mochovce NPP 3 and 4 Commissioning Department during Mochovce Units 3 and 4 commissioning. This independent support will be in line with the Mochovce NPP 3 and 4 Directive 'Non-active tests and commissioning' and it will be carried out in form of professional and expert works focusing on supervision of fulfilment of requirements for nuclear safety observance. The TSTCS duty to provide for such services during NPP commissioning is specified by Slovak Regulatory Body legislation. The independent TSTCS will supervise; - fulfilment of requirements for nuclear safety during preparation and implementation of commissioning tests; -scientific and technical level of commissioning programmes, and reflection on nuclear safety requirements in commissioning programmes,- commissioning process and test results. Main standpoints of the Team activities for individual unit commissioning stages will be; - assesment of the selected programs of functional tests in installations having an impact on nuclear safety and evaluation of the results of these tests; - assesment of the programs of physics and power commissioning, - assesment of the unit preparedness before fuel loading start; - assesment of the unit preparedness for performing initial criticality and low power commissioning and power commissioning stages; - evaluation of the results of physics and power commissioning stages and sub-stages; - final evaluation of the results from implementing the physics and power commissioning stages. The paper also presents a short description of the Team scope activities, the Team organisation, and a procedure for issuing of standpoints to individual unit commissioning stages. (Authors)

77 FR 73345 - Safety Standard for Bedside Sleepers

Science.gov (United States)

2012-12-10

... durable infant or toddler products, in consultation with representatives of consumer groups, juvenile... Commission (Commission or CPSC) to promulgate consumer product safety standards for durable infant or toddler... marking, labeling, and instructional literature of the proposed rule should be directed to the Office of...

78 FR 63243 - Certain Audiovisual Components and Products Containing the Same; Commission Determination To...

Science.gov (United States)

2013-10-23

... INTERNATIONAL TRADE COMMISSION [Investigation No. 337-TA-837] Certain Audiovisual Components and Products Containing the Same; Commission Determination To Review a Final Initial Determination Finding a... section 337 as to certain audiovisual components and products containing the same with respect to claims 1...

Product Safety Culture: A New Variant of Safety Culture?

International Nuclear Information System (INIS)

Suhanyiova, L.; Flin, R.; Irwin, A.

2016-01-01

Product safety culture is a new research area which concerns user safety rather than worker or process safety. The concept appears to have emerged after the investigation into the Nimrod aircraft accident (Haddon-Cave, 2009) which echoed aspects of NASA’s Challenger and Columbia crashes. In these cases, through a blend of human and organizational failures, the culture deteriorated to the extent of damaging product integrity, resulting in user fatalities. Haddon-Cave noted that it was due to a failure in leadership and organizational safety culture that accidents such as the Nimrod happened, where the aircraft exploded due to several serious technical failures, preceded by deficiencies in the safety case. Now some organizations are starting to measure product safety culture. This is important in day-to-day life as well, where a product failure as a result of poor organizational safety culture, can cause user harm or death, as in the case of Takata airbags scandal in 2015. Eight people have lost their lives and many were injured. According to investigation reports this was due to the company’s safety malpractices of fixing faulty airbags and proceeding to install them in vehicles, as well as secretly conducting tests to assess the integrity of their product and then deleting the data and denying safety issues as a result of the company’s cost-cutting policies. As such, organizational culture, specifically the applications of safety culture, can have far-reaching consequences beyond the workplace of an organization.

16 CFR 1207.9 - Product certification.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Product certification. 1207.9 Section 1207.9 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR SWIMMING POOL SLIDES § 1207.9 Product certification. (a) Certification shall be in accordance...

Nuclear Regulatory Commission Issuances

International Nuclear Information System (INIS)

1992-01-01

This is the thirty-sixth volume of issuances (1-396) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Boards, Administrative Law Judges, and Office Directors. It covers the period from July 1, 1992-December 31, 1992. Atomic Safety and Licensing Boards are authorized by Section 191 of the Atomic Energy Act of 1954. These Boards, comprised of three members conduct adjudicatory hearings on applications to construct and operate nuclear power plants and related facilities and issue initial decisions which, subject to internal review and appellate procedures, become the final Commission action with respect to those applications. Boards are drawn from the Atomic Safety and Licensing Board Panel, comprised of lawyers, nuclear physicists and engineers, environmentalists, chemists, and economists. The Atomic Energy Commission first established Licensing Boards in 1962 and the Panel in 1967

Impact Assessment Road Safety Action Programme : assessment for mid term review : final report. Report on behalf of the European Commission, Directorate-General Energy and Transport.

NARCIS (Netherlands)

ECORYS Transport & SWOV Institute for Road Safety Research

2006-01-01

In 2003 the Commission published Saving 20000 lives on our roads, a shared responsibility, also known as the third European Road Safety Action Programme (RSAP). The RSAP describes concrete actions and proposals for actions by the Commission aimed at realising the target for improving road safety as

76 FR 35014 - Certain Ground Fault Circuit Interrupters and Products Containing Same; Notice of Commission...

Science.gov (United States)

2011-06-15

... INTERNATIONAL TRADE COMMISSION [Investigation No. 337-TA-739] Certain Ground Fault Circuit Interrupters and Products Containing Same; Notice of Commission Determination Not To Review an Initial... fault circuit interrupters and products containing the same by reason of infringement of various claims...

Safety in nuclear power plant operation, including commissioning and decommissioning. A code of practice

International Nuclear Information System (INIS)

1978-01-01

Safe operation of a nuclear power plant postulates satisfactory siting, design, construction and commissioning, together with proper management and operation of the plant. This Code of Practice deals with the safety aspects of management, commissioning, operation and decommissioning of the plant. It forms part of the Agency's programme, referred to as the NUSS programme, for establishing Codes of Practice and Safety Guides relating to land-based stationary thermal neutron power plants. It has been prepared for the use of those responsible for the operation of stationary nuclear power plants, the main function of which is the generation of electrical and/or thermal power, and for the use of those responsible for regulating the operation of such plants. It is not intended for application to reactors used solely for experimental or research purposes. The provisions in the Code are designed to provide assurance that operational activities are carried out without undue radiological hazard to the general public and to persons on the site. It should be understood that the provisions in the Code set forth minimum requirements which shall be met in order to achieve safe operation of a nuclear power plant

Patient Drug Safety Reporting: Diabetes Patients' Perceptions of Drug Safety and How to Improve Reporting of Adverse Events and Product Complaints.

Science.gov (United States)

Patel, Puja; Spears, David; Eriksen, Betina Østergaard; Lollike, Karsten; Sacco, Michael

2018-03-01

Global health care manufacturer Novo Nordisk commissioned research regarding awareness of drug safety department activities and potential to increase patient feedback. Objectives were to examine patients' knowledge of pharmaceutical manufacturers' responsibilities and efforts regarding drug safety, their perceptions and experiences related to these efforts, and how these factors influence their thoughts and behaviors. Data were collected before and after respondents read a description of a drug safety department and its practices. We conducted quantitative survey research across 608 health care consumers receiving treatment for diabetes in the United States, Germany, United Kingdom, and Italy. This research validated initial, exploratory qualitative research (across 40 comparable consumers from the same countries) which served to guide design of the larger study. Before reading a drug safety department description, 55% of respondents were unaware these departments collect safety information on products and patients. After reading the description, 34% reported the department does more than they expected to ensure drug safety, and 56% reported "more confidence" in the industry as a whole. Further, 66% reported themselves more likely to report an adverse event or product complaint, and 60% reported that they were more likely to contact a drug safety department with questions. The most preferred communication methods were websites/online forums (39%), email (27%), and telephone (25%). Learning about drug safety departments elevates consumers' confidence in manufacturers' safety efforts and establishes potential for patients to engage in increased self-monitoring and reporting. Study results reveal potentially actionable insights for the industry across patient and physician programs and communications.

78 FR 17140 - Upholstered Furniture Fire Safety Technology; Meeting and Request for Comments

Science.gov (United States)

2013-03-20

... retardant (FR) chemicals, specialty fibers/fabrics without FR chemicals, inherently fire resistant materials... Furniture Fire Safety Technology; Meeting and Request for Comments AGENCY: Consumer Product Safety... Commission (CPSC, Commission, or we) is announcing its intent to hold a meeting on upholstered furniture fire...

The Canadian Nuclear Safety Commission Compliance Program for Uranium Mines and Mills

Energy Technology Data Exchange (ETDEWEB)

Schryer, D., E-mail: denis.schryer@cnsc-ccsn.gc.ca [Canadian Nuclear Safety Commission, Saskatoon, Saskatchewan (Canada)

2014-05-15

The Canadian Nuclear Safety Commission (CNSC) is the principal nuclear regulator in Canada. The CNSC is empowered through the Nuclear Safety and Control Act (NSCA) and its associated regulations, to regulate the entire nuclear cycle which includes: uranium mining and milling, uranium refining and processing, fuel fabrication, power generation and nuclear waste management. A CNSC uranium mine licence is required by a proponent to site, prepare, construct, operate, decommission and abandon this nuclear facility. The CNSC licence is the legal instrument that authorizes the regulated activities and incorporates conditions and regulatory controls. Following a favourable Commission Tribunal decision to issue a licence to authorize the licensed activities, CNSC develops and executes a compliance plan of the licensee’s programs and procedures. The CNSC compliance plan is risk-informed and applies its resources to the identified higher risk areas. The compliance program is designed to encourage compliance by integrating three components: promotion, verification and enforcement and articulates the CNSC expectations to attain and maintain compliance with its regulatory requirements. The licensee performance is assessed through compliance activities and reported to the Commission to inform the licensing process during licence renewal. The application of the ongoing compliance assessment and risk management model ensures that deviations from impact predictions are addressed in a timely manner. The Uranium Mines and Mills Division of the CNSC are preparing to meet the challenges of the planned expansion of their Canadian uranium mining industry. The presentation will discuss these challenges and the measures required to address them. The Uranium Mines and Mills Division (UMMD) have adopted a structured compliance framework which includes formal procedures to conduct site inspections. New UMMD staff are trained to apply the regulations to licensed sites and to manage non

Joint Commission

Science.gov (United States)

... for the latest publication of The Joint Commission Journal on Quality and Patient Safety (JQPS). . How We Work Process improvement program breeds quality culture, empowers staff An article in Quality Progress, June ...

Impact Assessment Road Safety Action Programme : assessment for mid term review : final report. Report on behalf of the European Commission, Directorate-General Energy and Transport.

OpenAIRE

ECORYS Transport & SWOV Institute for Road Safety Research

2006-01-01

In 2003 the Commission published Saving 20000 lives on our roads, a shared responsibility, also known as the third European Road Safety Action Programme (RSAP). The RSAP describes concrete actions and proposals for actions by the Commission aimed at realising the target for improving road safety as set in the White Paper (European Transport Policy for 2010: time to decide, 2001), namely halving the number of road deaths by 2010. Improving road safety in the EU is clearly a joint responsibilit...

Dynamic modeling of the tradeoff between productivity and safety in critical engineering systems

International Nuclear Information System (INIS)

Cowing, Michelle M.; Elisabeth Pate-Cornell, M.; Glynn, Peter W.

2004-01-01

Short-term tradeoffs between productivity and safety often exist in the operation of critical facilities such as nuclear power plants, offshore oil platforms, or simply individual cars. For example, interruption of operations for maintenance on demand can decrease short-term productivity but may be needed to ensure safety. Operations are interrupted for several reasons: scheduled maintenance, maintenance on demand, response to warnings, subsystem failure, or a catastrophic accident. The choice of operational procedures (e.g. timing and extent of scheduled maintenance) generally affects the probabilities of both production interruptions and catastrophic failures. In this paper, we present and illustrate a dynamic probabilistic model designed to describe the long-term evolution of such a system through the different phases of operation, shutdown, and possibly accident. The model's parameters represent explicitly the effects of different components' performance on the system's safety and reliability through an engineering probabilistic risk assessment (PRA). In addition to PRA, a Markov model is used to track the evolution of the system and its components through different performance phases. The model parameters are then linked to different operations strategies, to allow computation of the effects of each management strategy on the system's long-term productivity and safety. Decision analysis is then used to support the management of the short-term trade-offs between productivity and safety in order to maximize long-term performance. The value function is that of plant managers, within the constraints set by local utility commissions and national (e.g. energy) agencies. This model is illustrated by the case of outages (planned and unplanned) in nuclear power plants to show how it can be used to guide policy decisions regarding outage frequency and plant lifetime, and more specifically, the choice of a reactor tripping policy as a function of the state of the

Safety Culture Evaluation at Research Reactors of Pakistan Atomic Energy Commission

International Nuclear Information System (INIS)

Qamar, M.A.; Saeed, A.; Shah, J.H.

2016-01-01

The concept of safety culture was presented by IAEA in document INSAG-4 (1991), delineated as “assembly of characteristics and attitudes in organizations and individuals which establish that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance”. The purpose of this paper is to describe the evaluation of safety culture at research reactors of the Pakistan Atomic Energy Commission (PAEC). Evaluating the safety culture of a particular organization poses some challenges which can be resolved by using safety culture evaluation models like those of Sachein (1992) and Harber-Barrier(1998). In PAEC, safety culture is the integral part of management system which not only promotes safety culture throughout the organization but also enhances its significance. To strengthen the safety culture, PAEC is also participating in a number of international and regional meetings of IAEA regarding safety culture. PAEC and the national regulator Pakistan Nuclear Regulatory Authority (PNRA) are also arranging workshops, peer reviews, sharing operational experiences and interacting with IAEA missions to enhance its capabilities in the field of safety culture. The Directorate General of Safety (DOS) is a corporate office of PAEC for safety and regulatory matters. DOS is in the process of implementing a program to evaluate safety culture at nuclear installations of PAEC to ensure that safety culture is included as a vital segment of the Integral Management System of the establishment. In this regard, training sessions and lectures on safety culture evaluation are normally conducted in PAEC for awareness and enhancement of the safety culture program. Safety culture is also addressed in PNRA Regulations like PAK-909 and PAK-913. In this paper we will focus on the safety culture evaluation in our research reactors, i.e., PARR-1 and PARR-2. The evaluation results will be based on observations, interviews of employees, group discussions

Independent Commission for Radiological Protection and Nuclear Safety CIPRSN: Balance, obligations and future prospects

International Nuclear Information System (INIS)

Gieb, M.; Meruje, M. M; Sena Lino, A.

2010-01-01

This article summarizes the historical context of the regulatory situation in Portugal that led to the creation of the technical team of the Independent Commission for Radiological Protection and Nuclear Safety (CIPRSN), recalls its early works, and highlights the current work of some members of the team on the self-assessment of the national regulatory system of radiological protection and nuclear safety. The result of this self-assessment allows a detailed analysis of current problems and makes it possible to outline the future work plan of the technical team. It is hoped that this work may contribute to an improvement of the system, especially in view of new international and European legal instruments which are currently under implementation. (author)

Royal Order of 15 October 1979 creating and organising an Interministerial Commission for Nuclear Safety and State Security in the Nuclear Field

International Nuclear Information System (INIS)

1979-01-01

This Royal Order setting up an Interministerial Commission for Nuclear Safety and State Security provides for the duties of the Commission. These are, in particular, to seek the means to ensure the protection of workers against the hazards which might arise from nuclear activities by co-ordinating the work of the ministerial departments concerned. The Commission is composed of representatives of ministries and bodies involved in that field. (NEA) [fr

75 FR 22291 - Safety Standard for Toddler Beds

Science.gov (United States)

2010-04-28

... Kiss, Division of Human Factors, Directorate for Engineering Sciences, Consumer Product Safety... testing requirements to address those types of incidents. Accordingly, the Commission proposes a new 16.... With this in mind, the Commission proposes two alternative labels that address the entrapment hazard...

Review and evaluation of the Nuclear Regulatory Commission safety research program for Fiscal Year 1983. Report to the Congress

International Nuclear Information System (INIS)

1982-02-01

Public Law 95-209 includes a requirement that the Advisory Committee on Reactor Safeguards submit an annual report to Congress on the safety research program of the Nuclear Regulatory Commission. This report presents the results of the ACRS review and evaluation of the NRC safety research program for Fiscal Year 1983. The report contains a number of comments and recommendations

Nuclear Regulatory Commission Issuances

International Nuclear Information System (INIS)

1981-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Problems and experience of regulatory review associated with plant construction and commissioning

International Nuclear Information System (INIS)

Commander, W.

1979-01-01

The work of the Assessment Branch of NII covering the regulatory review during design safety assessment, construction, commissioning and operation is described commencing with the nuclear licensing procedure through licence variations and conditions attached to the licence, to the final stages of plant construction up to commercial operation and full power production. The importance of the application of safety assessment principles is outlined, the importance of the Safety Inspectorate Schedule described, and the need to retain organisational and regulatory flexibility emphasised. (author)

Recommendations of the Reactor Safety Commission (RSK) 1981-1983. Vol. 5

International Nuclear Information System (INIS)

1984-02-01

Since the reorganization of the RSK in 1971 the recommendations are published in the ''Bundesanzeiger'' (BAnz). This makes the work of the RSK transparent for the public. After publication of the recommendations in the Bundesanzeiger, the Office of the RSK publishes them once more as a summary report by order of the Federal Minister of Interior. The reports are divided generally into two parts: Part I contains the recommendations which are given by the RSK; part II contains the official notices concerning the RSK. There is also a subject index. In addition volume 5 contains as part III all papers which were held on the occasion of the 25th anniversary of the Reactor Safety Commission. (orig./HP) [de

Yellin's review of the Nuclear Regulatory Commission's Reactor Safety Study: comment

International Nuclear Information System (INIS)

Wilson, R.

1976-01-01

Joel Yellin (Bell J. Economics, Vol. 7, No. 1 (Spr. 1976)) reviewed the Reactor Safety Study (WASH-1400, or Rasmussen Report) published by the Nuclear Regulatory Commission and makes several criticisms. Wilson finds that some of these criticisms are much overstated, while others, although valid, are mainly criticisms of presentation. To be useful for public policy, reactor risks--and indeed all nuclear risks--must be compared with other risks society faces. Wilson feels that the Rasmussen Report is weak in these comparisons, primarily because there exist few estimates of risk in other places, but that the comparisons he does make indeed confirm that the risk is smaller than Yellin suggests. 20 references

Proposal for the award of a contract for the supply, installation, commissioning and maintenance of the LHC access safety system

CERN Document Server

2005-01-01

This document concerns the award of a contract for the supply, installation, commissioning and maintenance of the LHC access safety system. The Finance Committee is invited to agree to the negotiation of a contract with the consortium CEGELEC CENTRE EST (FR) â?" CEGELEC (NL) â?" SEMER (FR), the lowest bidder, for the supply, installation, commissioning and maintenance for five years of the LHC access safety system for a total amount of 891 423 euros (1 367 633 Swiss francs), subject to revision for inflation for the maintenance of the system from 1 January 2007, with an option for the supply of safety PLCs for a total amount of 894 951 euros (1 373 046 Swiss francs), not subject to revision, bringing the total amount to 1 786 374 euros (2 740 679 CHF).The rate of exchange used is that stipulated in the tender.

EFSA NDA Panel (EFSA Panel on Dietetic Products, Nutrition and Allergies), 2015. Scientific Opinion on the safety of caffeine

DEFF Research Database (Denmark)

Tetens, Inge

2015-01-01

Following a request from the European Commission, the EFSA Panel on Dietetic Products, Nutrition and Allergies was asked to deliver a scientific opinion on the safety of caffeine, providing advice on caffeine intakes, from all dietary sources that do not give rise to concerns about adverse health...... not give rise to safety concerns. The same amount does not give rise to safety concerns when consumed .../L of caffeine, taurine and d-glucurono-γ-lactone, respectively), as well as alcohol at doses up to about 0.65 g/kg bw, would not affect the safety of single doses of caffeine up to 200 mg. Habitual caffeine consumption up to 400 mg per day does not give rise to safety concerns for non-pregnant adults. Habitual...

78 FR 63492 - Certain Audiovisual Components and Products Containing the Same; Notice of Commission...

Science.gov (United States)

2013-10-24

... INTERNATIONAL TRADE COMMISSION [Investigation No. 337-TA-837] Certain Audiovisual Components and Products Containing the Same; Notice of Commission Determination To Review a Final Initial Determination Finding a Violation of Section 337 in Its Entirety; Schedule for Filing Written Submissions on Certain...

Consumer Product Safety Commission

Science.gov (United States)

... Certification Import Surveillance International Recall Guidance Civil and Criminal Penalties Federal Court Orders & Decisions Research & Statistics Research & Statistics Technical Reports Injury Statistics NEISS ...

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1981-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1982-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1982-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking

16 CFR 1205.36 - Product certification and labeling by importers.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Product certification and labeling by importers. 1205.36 Section 1205.36 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR WALK-BEHIND POWER LAWN MOWERS Certification § 1205.36 Product...

16 CFR 1205.35 - Product certification and labeling by manufacturers.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Product certification and labeling by manufacturers. 1205.35 Section 1205.35 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR WALK-BEHIND POWER LAWN MOWERS Certification § 1205.35 Product...

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1988-05-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1987-03-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1990-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1991-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1986-07-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1987-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1989-11-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Danials of Petitions for Rulemaking (DPRM)

Nuclear regulatory commission issuances

International Nuclear Information System (INIS)

1989-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1991-05-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1988-01-01

This report includes the issuance received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances

International Nuclear Information System (INIS)

1986-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1991-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1990-04-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances

International Nuclear Information System (INIS)

1988-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1988-04-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1991-03-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1988-06-01

This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1982-04-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1989-09-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1989-06-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear regulatory commission issuances

International Nuclear Information System (INIS)

1990-07-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1987-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1990-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety And Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1985-04-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1990-09-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1982-08-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1988-08-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

16 CFR Appendix to Part 1213 - Findings Under the Consumer Product Safety Act

Science.gov (United States)

2010-01-01

... at the point of purchase and make their purchase decisions with this safety information in mind. This... the Commission's decision focus on the specific facts of this rulemaking and are stated below. iii... inform the Commission's decision regarding whether a certain level of conformance with a voluntary...

Assessment of phthalates/phthalate alternatives in children's toys and childcare articles: Review of the report including conclusions and recommendation of the Chronic Hazard Advisory Panel of the Consumer Product Safety Commission.

Science.gov (United States)

Lioy, Paul J; Hauser, Russ; Gennings, Chris; Koch, Holger M; Mirkes, Philip E; Schwetz, Bernard A; Kortenkamp, Andreas

2015-01-01

The Consumer Product Safety Commission (CPSC) convened a Chronic Hazard Advisory Panel (CHAP) on Phthalates found in children's toys, and childcare products, and in products used by women of childbearing age. The CHAP conducted a risk assessment on phthalates and phthalate substitutes, and made recommendations to either ban, impose an interim ban, or allow the continued use of phthalates and phthalate substitutes in the above products. After a review of the literature, the evaluation included toxic end points of primary concern, biomonitoring results, extant exposure reconstruction, and epidemiological results. The health end points chosen were associated with the rat phthalate syndrome, which is characterized by malformations of the epididymis, vas deferens, seminal vesicles, prostate, external genitalia (hypospadias), and by cryptorchidism (undescended testes), retention of nipples/areolae, and demasculinization (~incomplete masculinization) of the perineum, resulting in reduced anogenital distance. Risk assessment demonstrated that some phthalates should be permanently banned, removed from the banned list, or remain interim banned. Biomonitoring and toxicology data provided the strongest basis for a mixture risk assessment. In contrast, external exposure data were the weakest and need to be upgraded for epidemiological studies and risk assessments. Such studies would focus on routes and sources. The review presents recommendations and uncertainties.

The Commission's research action programme on the development of nuclear fission energy

International Nuclear Information System (INIS)

1984-01-01

For its 'Framework Programme 1984-1987' the Commission has defined the major goals for a European Scientific and Technical Strategy. One of the means to reduce the energy dependence of the Community, which is an important objective, is to favour the development of nuclear fission energy. As electricity production by nuclear reactors has reached industrial maturity, the Community activities are directed mainly to safety aspects, in order to ensure the protection of workers and the general public, against hazards linked to operations in the nuclear fuel cycle. A description of the main features of the five sub-programmes on nuclear fission energy is given below; these programmes are: reactor safety; nuclear fuels and actinides research; management of radioactive waste; safeguarding and management of fissile materials; decommissioning of nuclear installations. The research and development work is carried out either by the Commission's Joint Research Center or by organizations and companies of the Member Countries, with the Commission's financial support. (author)

Nuclear Regulatory Commission Staff practice and procedure digest. Commission, Appeal Board and Licensing Board Decision, July 1972 - June 1995

International Nuclear Information System (INIS)

1996-04-01

This is the seventh edition of the Nuclear Regulatory Commission (NRC) Staff Practice and Procedure Digest. It contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 1995 interpreting the NRC rules of practice in 10 CFR part 2

Safe LHC beam commissioning

International Nuclear Information System (INIS)

Uythoven, J.; Schmidt, R.

2007-01-01

Due to the large amount of energy stored in magnets and beams, safety operation of the LHC is essential. The commissioning of the LHC machine protection system will be an integral part of the general LHC commissioning program. A brief overview of the LHC Machine Protection System will be given, identifying the main components: the Beam Interlock System, the Beam Dumping System, the Collimation System, the Beam Loss Monitoring System and the Quench Protection System. An outline is given of the commissioning strategy of these systems during the different commissioning phases of the LHC: without beam, injection and the different phases with stored beam depending on beam intensity and energy. (author)

76 FR 11275 - In the Matter of Certain Ceramic Capacitors and Products Containing Same; Notice of Commission...

Science.gov (United States)

2011-03-01

... INTERNATIONAL TRADE COMMISSION [Investigation No. 337-TA-692] In the Matter of Certain Ceramic Capacitors and Products Containing Same; Notice of Commission Determination To Review in Part A Final Initial... importation of certain ceramic capacitors and products containing the same by reason of infringement of...

29 CFR 2200.92 - Review by the Commission.

Science.gov (United States)

2010-07-01

... Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH REVIEW COMMISSION RULES OF PROCEDURE Posthearing Procedures § 2200.92 Review by the Commission. (a) Jurisdiction of the Commission; issues on... Commission to review the entire case. The issues to be decided on review are within the discretion of the...

Nuclear Regulatory Commission Issuances, November 1980

International Nuclear Information System (INIS)

1980-11-01

Contents: Issuances of the Nuclear Regulatory Commission; Issuances of the Atomic Safety and Licensing Appeal Boards; Issuances of the Atomic Safety and Licensing Boards; and Issuances of the Directors Denial

Nuclear Regulatory Commission Issuances, December 1980

International Nuclear Information System (INIS)

1980-12-01

Contents: Issuances of the Nuclear Regulatory Commission; Issuances of the Atomic Safety and Licensing Appeal Boards; Issuances of the Atomic Safety and Licensing Boards; and Issuances of the Directors Denial

Neutron production and dose rate in the IFMIF/EVEDA LIPAc injector beam commissioning

Energy Technology Data Exchange (ETDEWEB)

Kondo, Keitaro, E-mail: kondo.keitaro@jaea.go.jp [Rokkasho Fusion Institute, Japan Atomic Energy Agency, Rokkasho-mura, Kamikita-gun, Aomori (Japan); Narita, Takahiro; Usami, Hiroki; Takahashi, Hiroki; Ochiai, Kentaro; Shinto, Katsuhiro; Kasugai, Atsushi [Rokkasho Fusion Institute, Japan Atomic Energy Agency, Rokkasho-mura, Kamikita-gun, Aomori (Japan); Okumura, Yoshikazu [IFMIF/EVEDA Project Team, Rokkasho-mura, Kamikita-gun, Aomori (Japan)

2016-11-01

Highlights: • A dedicated neutron production yield monitoring system for LIPAc has been developed. • The biological dose rate during operation of the LIPAc injector was analyzed. • The neutron streaming effect due to penetrations in the shielding wall was investigated. - Abstract: The construction of the Linear IFMIF Prototype Accelerator (LIPAc) is in progress in Rokkasho, Japan, and the deuteron beam commissioning of the injector began in July 2015. Due to the huge beam current of 125 mA, a large amount of d-D neutrons are produced in the commissioning. The neutron streaming effect through pipe penetrations and underground pits may dominate the radiation dose at the outside of the accelerator vault during the injector operation. In the present study the effective dose rate expected during the injector commissioning was analyzed by a Monte Carlo calculation and compared with the measured value. For the comparison it is necessary to know the total neutron production yield in the accelerator vault, thus a dedicated neutron production yield monitoring system was developed. The yield obtained was smaller than that previously reported in a literature by a factor of a few and seems to depend on some beam conditions. From the comparison it was proved that the calculation always provides a conservative estimate and the dose rates in places where occupational works can always access and the controlled area boundary are expected to be far less than the legal criteria throughout the injector commissioning.

Nuclear Regulatory Commission issuances, October 1993

International Nuclear Information System (INIS)

1993-10-01

This document contains a Commission issuance in which the Commission denies the petitioners' motion to quash or modify a subpoena issued by the NRC staff in the course of an investigation to determine if the petitioners' have violated NRC regulations and to determine if safety-related problems exist at NRC-licensed facilities. The pertinent regulations and the Commission's Memorandum and Order are included

Safety issues at the defense production reactors

International Nuclear Information System (INIS)

1987-01-01

The United States produces plutonium and tritium for use in nuclear weapons at the defense production reactors - the N Reactor in Washington and the Savannah River reactors in South Carolina. This report reaches general conclusions about the management of those reactors and highlights a number of safety and technical issues that should be resolved. The report provides an assessment of the safety management, safety review, and safety methodology employed by the Department of Energy and the private contractors who operate the reactors for the federal government. This report examines the safety objective established by the Department of Energy for the production reactors and the process the Department of its contractors use to implement the objective; focuses on a variety of uncertainties concerning the production reactors, particularly those related to potential vulnerabilities to severe accidents; and identifies ways in which the DOE approach to management of the safety of the production reactors can be improved

Monitoring product safety in the postmarketing environment.

Science.gov (United States)

Sharrar, Robert G; Dieck, Gretchen S

2013-10-01

The safety profile of a medicinal product may change in the postmarketing environment. Safety issues not identified in clinical development may be seen and need to be evaluated. Methods of evaluating spontaneous adverse experience reports and identifying new safety risks include a review of individual reports, a review of a frequency distribution of a list of the adverse experiences, the development and analysis of a case series, and various ways of examining the database for signals of disproportionality, which may suggest a possible association. Regulatory agencies monitor product safety through a variety of mechanisms including signal detection of the adverse experience safety reports in databases and by requiring and monitoring risk management plans, periodic safety update reports and postauthorization safety studies. The United States Food and Drug Administration is working with public, academic and private entities to develop methods for using large electronic databases to actively monitor product safety. Important identified risks will have to be evaluated through observational studies and registries.

Amendment of the atomic energy basic law and other related laws and establishment of the nuclear safety commission

International Nuclear Information System (INIS)

Ochi, Kenji

1978-01-01

The Atomic Energy Basic Law and related several laws were amended in the recent diet session. The amendment of the laws was requested after the radiation leakage from nuclear-powered ship ''Mutsu''. The reform of administrative system of atomic energy development and utilization are consisted of two important points: one is to establish the Nuclear Safety Commission for strengthening nuclear safety administration, and the other is to give an authority to each ministry or agency to regulate nuclear power reactor from the establishment to operation according to its original mission. (author)

Commissioning and Operational Experience in Power Reactor Fuel Reprocessing Plant

Energy Technology Data Exchange (ETDEWEB)

Pradhan, S., E-mail: spradhan@barctara.gov.in [Tarapur Based Reprocessing Plant, Bhabha Atomic Research Centre, Tarapur (India)

2014-10-15

After completing design, construction, commissioning, operation and maintenance experience of the reprocessing plants at Tarapur, Mumbai and Kalpakkam a new reprocessing plant is commissioned and put into operation at BARC, Tarapur since 2011. Subsequent to construction clearance, commissioning of the plant is taken in many steps with simultaneous review by design and safety committees. In spite of vast experience, all the staff was retrained in various aspects of process and utility operations and in operation of innovative changes incorporated in the design. Operating personnel are licensed through an elaborate procedure consisting of various check lists followed by personnel interview. Commissioning systems were divided in sub-systems. Sub-systems were commissioned independently and later integrated testing was carried out. For commissioning, extreme operating conditions were identified in consultation with designers and detailed commissioning procedures were made accordingly. Commissioning was done in different conditions to ensure safety, smooth operation and maintainability. Few modifications were carried out based on commissioning experience. Technical specifications for operation of the plant are made in consultation with designers and reviewed by safety committees. Operation of the plant was carried out after successful commissioning trials with Deep Depleted Uranium (DDU). Emergency operating procedures for each design basis accident were made. Performance of various systems, subsystems are quite satisfactory and the plant has given very good capacity factor. (author)

DIVERSIFICATION OF A SAFETY FOOTWEAR PRODUCT

OpenAIRE

HARNAGEA Marta Cătălina; SECAN Cristina

2017-01-01

Product diversification is a usual strategy of footwear producers. As a requirement related to competitiveness in this domain, diversification can be done by practical application of some criteria. Considering this aspect, the paper proposes a research on the diversification in the case of a safety footwear product by modifying its component patterns, while keeping the initial shape of the product. Thus, starting from a safety shoe model, diversification was performed by changing the configur...

Safety in the design of production lines

DEFF Research Database (Denmark)

Dyhrberg, Mette Bang; Broberg, Ole; Jacobsen, Peter

2006-01-01

This paper is a case study report on how safety considerations were handled in the process of redesigning a production line. The design process was characterized as a specification and negotiation process between engineers from the company and the supplier organization. The new production line...... in the specification material nor in their face-to-face meetings with the supplier. Safety aspects were not part of their work practice. On this basis, it was suggested that formal guidelines or procedures for integrating safety in the design of production lines would have no effect. Instead, the researchers set up...... became safer, but not as a result of any intentional plan to integrate safety aspects into the design process. Instead, the supplier’s design of a new piece of equipment had a higher built-in safety level. The engineering team in the company was aware of the importance of safety aspects neither...

Safety in the redesigning of production lines

DEFF Research Database (Denmark)

Dyhrberg, Mette Bang; Broberg, Ole; Jacobsen, Peter

2006-01-01

This paper is a case study report on how safety considerations were handled in the process of redesigning a production line. The design process was characterized as a specification and negotiation process between engineers from the company and the supplier organization. The new production line...... became safer, but not as a result of any intentional plan to integrate safety aspects into the design process. Instead, the supplier’s design of a new piece of equipment had a higher built-in safety level. The engineering team in the company was aware of the importance of safety aspects neither...... in the specification material nor in their face-to-face meetings with the supplier. Safety aspects were not part of their work practice. On this basis, it was suggested that formal guidelines or procedures for integrating safety in the design of production lines would have no effect. Instead, the researchers set up...

42 CFR 3.212 - Nonidentification of patient safety work product.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Nonidentification of patient safety work product. 3... PROVISIONS PATIENT SAFETY ORGANIZATIONS AND PATIENT SAFETY WORK PRODUCT Confidentiality and Privilege Protections of Patient Safety Work Product § 3.212 Nonidentification of patient safety work product. (a...

Nuclear Regulatory Commission issuances, May 1982

International Nuclear Information System (INIS)

1982-01-01

This report includes the issuances received during the specified period from the Commission, the Atomic Safety and Licensing Appeal Boards, the Atomic Safety and Licensing Boards, the Administrative Law Judge, the Directors' Decision, and the Denials of Petitions for Rulemaking

42 CFR 3.204 - Privilege of patient safety work product.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Privilege of patient safety work product. 3.204... PROVISIONS PATIENT SAFETY ORGANIZATIONS AND PATIENT SAFETY WORK PRODUCT Confidentiality and Privilege Protections of Patient Safety Work Product § 3.204 Privilege of patient safety work product. (a) Privilege...

Sentinel-1A Product Geolocation Accuracy: Commissioning Phase Results

Directory of Open Access Journals (Sweden)

Adrian Schubert

2015-07-01

Full Text Available Sentinel-1A (S1A is an Earth observation satellite carrying a state-of-the-art Synthetic Aperture Radar (SAR imaging instrument. It was launched by the European Space Agency (ESA on 3 April 2014. With the end of the in-orbit commissioning phase having been completed at the end of September 2014, S1A data products are already consistently providing highly accurate geolocation. StripMap (SM mode products were acquired regularly and tested for geolocation accuracy and consistency during dedicated corner reflector (CR campaigns. At the completion of this phase, small geometric inconsistencies had been understood and mitigated, with the high quality of the final product geolocation estimates reflecting the mission’s success thus far. This paper describes the measurement campaign, the methods used during geolocation estimation, and presents best estimates of the product Absolute Location Error (ALE available at the beginning of S1A’s operational phase.

Aim, mode of work and main recommendations of the Commission Energies 2050

International Nuclear Information System (INIS)

Anon.

2012-01-01

The Commission Energies 2050 has led an analysis of various scenarios concerning the energy mix for electricity production in France. The aim was to shed light on the future investment needed. The Commission has released 8 recommendations: 1) to develop a culture of energy saving and energy efficiency; 2) to quantify any decision in energy policy by considering its impacts on cost, on public financing needs, on commercial balance, on jobs and on environment; 3) to consider only safety concerns to close a nuclear plant; 4) to have a policy of truth concerning the real cost of energy; 5) to propose to the European partners new rules for the energy market in order to allow the investment needed and to give consistency to all the players; 6) to propose a worldwide standardization at the highest level of the nuclear safety rules; 7) to develop coordinated research programs concerning all the aspects of energy: sustainable aspect, storage, safety,... and 8) to continue developing a long-term prospect for nuclear power. (A.C.)

CRASH - Community Road Accident System Homepage : feasibility study on a European Road Safety Information System, financially supported by the European Commission.

NARCIS (Netherlands)

Brouwer, M. Poppe, F. Blokpoel, A. & Kars, V.

2000-01-01

This report is the result of a feasibility study, financially supported by the European Commission. The study investigated the possibilities for the development and maintenance of a European Road Safety Information System with relevant and internationally comparable information. Recommendations on

Nuclear Regualtory Commission Issuances, October 1981

International Nuclear Information System (INIS)

1981-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Denial (DD), and the Denial of Petitions for Rulemaking

78 FR 73692 - Revisions to Safety Standards for Infant Bath Seats, Toddler Beds, and Full-Size Baby Cribs

Science.gov (United States)

2013-12-09

... standard issued under the Danny Keysar Child Product Safety Notification Act was based, the revision... standard. Section 26(c) of the CPSA also provides that states or political subdivisions of states may apply... CONSUMER PRODUCT SAFETY COMMISSION 16 CFR Parts 1215, 1217 and 1219 Revisions to Safety Standards...

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1989-08-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety nd Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

Nuclear Regulatory Commission issuances

Energy Technology Data Exchange (ETDEWEB)

1994-03-01

This report includes the issuances received during the specified period from Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1994-03-01

This report includes the issuances received during the specified period from Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

The Traceability and Safety of Fishery Products

Directory of Open Access Journals (Sweden)

Gheorghe Adrian ZUGRAVU

2012-12-01

Full Text Available The paper follows two main objectives: to understand consumers’ perception of safety trasability and quality of fishery products and to identify communication levers in order to improve the perceived image of fishery products. The present research is focused on the fishery products, regardless of their presentation – fresh, frozen or processed. This paper conducted a questionnaire survey of Romanian consumers’ perception toward fishery products. The empirical study with brands indicated that consumers are different awareness to domestic and foreign safety fish products. National fishery products got more attention from the consumers.

[Legislative regulation of production and turnover of products for people with different diseases].

Science.gov (United States)

Pritul'skaia, N V; Motuzka, Iu N; Antiushko, D L

2013-01-01

This article presents results of analysis of existing regulatory documents and approaches to the legislative regulation of production and turnover of special dietary products for people with specific diseases in EU, Ukraine and Russian Federation. According to the EU legislation, production and turnover of food products for nutritional support of people during specific diseases and the rehabilitation period are regulated by the Commission Directive 1999/21/EC, 2009/39/ES, by Regulation Commission (EU) No 953/2009 and documents of Codex Committee. Special food products for people with specific diseases in Ukrainian legislation are classified as nutrition products for special dietary use and are regulated by the following Laws of Ukraine "On the safety and quality of food", "On ensuring of sanitary and epidemiological welfare of the population", "On Consumer Rights Protection", "On advertising" and by other non-legislative acts. According to the current legislation of the Russian Federation, the products for people with specific diseases are classified as healthy dietary food products. The basis of the legal framework are federal laws "On the quality and safety of food", "On the sanitary-epidemiological welfare of the populations", "On technical regulations and technical regulations of the Customs Union "On Food Safety" and "On the safety of certain types of specialized food products, including healthy dietary food products and therapeutic dietary food products". There is no common approach to the legal regulation of production and turnover of products for people with specific diseases in the world. The proposals for further harmonization of regulatory control in this area have been developed.

Nuclear Regulatory Commission issuances, July 1988

International Nuclear Information System (INIS)

1988-08-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances, October 1986

International Nuclear Information System (INIS)

1986-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, May 1987

International Nuclear Information System (INIS)

1987-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, September 1987

International Nuclear Information System (INIS)

1987-09-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, April 1989

International Nuclear Information System (INIS)

1989-04-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, July 1989

International Nuclear Information System (INIS)

1989-07-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, March 1989

International Nuclear Information System (INIS)

1989-03-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, May 1989

International Nuclear Information System (INIS)

1989-05-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, May 1990

International Nuclear Information System (INIS)

1990-05-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, August 1990

International Nuclear Information System (INIS)

1990-08-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, October 1989

International Nuclear Information System (INIS)

1989-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, June 1987

International Nuclear Information System (INIS)

1987-06-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decision (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, April 1987

International Nuclear Information System (INIS)

1987-04-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances, August 1986

International Nuclear Information System (INIS)

1986-08-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, November 1988

International Nuclear Information System (INIS)

1988-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances, March 1990

International Nuclear Information System (INIS)

1990-01-01

The report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, November 1987

International Nuclear Information System (INIS)

1987-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, June 1990

International Nuclear Information System (INIS)

1990-06-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, December 1990

International Nuclear Information System (INIS)

1990-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, December 1989

International Nuclear Information System (INIS)

1989-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, February 1989

International Nuclear Information System (INIS)

1989-02-01

This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, February 1985

International Nuclear Information System (INIS)

1985-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, November 1990

International Nuclear Information System (INIS)

1990-11-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

16 CFR 1203.34 - Product certification and labeling by manufacturers (including importers).

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Product certification and labeling by... COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SAFETY STANDARD FOR BICYCLE HELMETS Certification § 1203.34 Product certification and labeling by manufacturers (including importers). (a) Form of permanent...

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1993-08-01

This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors; Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

Nuclear Regulatory Commission Issuances

International Nuclear Information System (INIS)

1996-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1991-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuance

International Nuclear Information System (INIS)

1994-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1991-11-01

This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances

International Nuclear Information System (INIS)

1994-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1992-03-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1991-09-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances

International Nuclear Information System (INIS)

1994-05-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1991-07-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Canadian Nuclear Safety Commission 2003-2004 estimates. Part III - report on plans and priorities

International Nuclear Information System (INIS)

2003-01-01

The Commission replace the Atomic Energy Control Board in 2000 as Canada's independent agency which regulates the use of nuclear energy and materials to protect health, safety, security, and the environment. This report is an individual expenditure plan that provides details on a business line basis and contains information on objectives, initiatives, and planned results, including links to related resource requirements over a three-year period. It also provides details on human resource requirements, major capital projects, grants and contributions, and net program costs. Introductory sections with a minister's message are followed by sections giving a departmental or organization overview; plans, results, activities, resources, and initiatives, as applicable; and financial information

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements

International Nuclear Information System (INIS)

2016-01-01

This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication

Nuclear Regulatory Commission issuances, April 1991

International Nuclear Information System (INIS)

1991-04-01

This report includes the issuances received during the specified period (April 1991) from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Commissioning of Temelin NPP as seen by scientific supervisory group

International Nuclear Information System (INIS)

Svoboda, C.

2003-01-01

Scientific Supervisory Group worked during the Temelin NPP commissioning process as an independent supervisor. The main tasks and main results of its activity are described in this contribution. The characteristic common features of commissioning process and most important events from the Scientific Supervisory Group point of view are presented. In April 1999 the Czech Power Utility with the objective to achieve maximum level of nuclear safety and quality within the NPP Temelin commissioning procedures has established a special body / Scientific Supervisory Group and requested Nuclear Research Institute Rez plc to perform the required function. The Scientific Supervisory Group proceeds in accordance with its Statute and provides an independent specialised professional and expert work focused on nuclear safety assurance, assesment of the selected documentation related to plant preparedness for the individual commissioning stages, and, of course. on assessment of the commissioning tests results. While performing its function the Scientific Supervisory Group is guided by the Atomic Act and the relevant Directives of State Office for Nuclear Safety; its activities are in compliance with the applicable IAEA recommendations (Authors)

A Virtual Commissioning Learning Platform

DEFF Research Database (Denmark)

Mortensen, Steffen; Madsen, Ole

2018-01-01

The introduction of reconfigurable manufacturing systems (RMS), Industry 4.0 and the associated technologies requires the establishment of new competencies. Towards that goal, Aalborg University (AAU) has developed an Industry 4.0 learning factory, the AAU Smart Production Lab. The AAU Smart...... Production Lab integrates a number of Industry 4.0 technologies for learning and research purposes. One of the many techniques is virtual commissioning. Virtual commissioning uses a virtual plant model and real controllers (PLCs) enabling a full emulation of the manufacturing system for verification. Virtual...... commissioning can lower the commissioning time up to 63%, allowing faster time to market. However, virtual commission is still missing industrial impact one of the reasons being lack of competencies and integration experiences. The paper presents the setup of the virtual commissioning learning platform...

77 FR 43811 - Submission for OMB Review; Comment Request-Safety Standards for Full-Size Baby Cribs and Non-Full...

Science.gov (United States)

2012-07-26

... CONSUMER PRODUCT SAFETY COMMISSION Submission for OMB Review; Comment Request--Safety Standards for Full-Size Baby Cribs and Non-Full-Size Baby Cribs; Compliance Form AGENCY: Consumer Product Safety... standards for full-size and non-full-size baby cribs in response to the direction under section 104(b) of...

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1982-03-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

Review and evaluation of the Nuclear Regulatory Commission Safety Research Program for Fiscal Years 1984 and 1985

International Nuclear Information System (INIS)

1983-02-01

This is the sixth report by the Advisory Committee on Reactor Safeguards (ACRS) that has been prepared in response to the Congressional requirement for an annual report on the Nuclear Regulatory Commission (NRC) Reactor Safety Research Program. Part I is a compilation of our general comments and recommendations regarding the NRC Safety Research Program, and includes budget recommendations and an identification of matters of special importance that deserve increased emphasis. It is intended to serve as an Executive Summary. Part II is divided into ten chapters, each of which represents a Decision Unit of the NRC research program. In each chapter, specific comments are included on the research involved in the Decision Unit, an assessment of priorities, and recommendations regarding new directions and levels of funding

Safety policy in the production of electricity

International Nuclear Information System (INIS)

Siddall, E.

1982-01-01

When safety is properly understood, defined and quantified, it can be seen that the development of our present industrial civilization has resulted in a progressive improvement in human safety. Increased safety has come with increased wealth in such close association that a high degree of cause-and-effect relationship must be considered. The quantitative relationship between wealth production and safety improvement is derived from different sources of evidence. When this is applied to the wealth production from electricity generation in a standard module of population in an advanced society, a safety benefit is indicated which exceeds the assessed direct risk associated with the electricity generation by orders of magnitude. It appears that a goal or policy intended to confer the greatest safety benefit to the population would result in attitudes and actions diametrically opposite to those which are conventional at the moment

Food Safety Practices in the Egg Products Industry.

Science.gov (United States)

Viator, Catherine L; Cates, Sheryl C; Karns, Shawn A; Muth, Mary K; Noyes, Gary

2016-07-01

We conducted a national census survey of egg product plants (n = 57) to obtain information on the technological and food safety practices of the egg products industry and to assess changes in these practices from 2004 to 2014. The questionnaire asked about operational and sanitation practices, microbiological testing practices, food safety training for employees, other food safety issues, and plant characteristics. The findings suggest that improvements were made in the industry's use of food safety technologies and practices between 2004 and 2014. The percentage of plants using advanced pasteurization technology and an integrated, computerized processing system increased by almost 30 percentage points. Over 90% of plants voluntarily use a written hazard analysis and critical control point (HACCP) plan to address food safety for at least one production step. Further, 90% of plants have management employees who are trained in a written HACCP plan. Most plants (93%) conduct voluntary microbiological testing. The percentage of plants conducting this testing on egg products before pasteurization has increased by almost 30 percentage points since 2004. The survey findings identify strengths and weaknesses in egg product plants' food safety practices and can be used to guide regulatory policymaking and to conduct required regulatory impact analysis of potential regulations.

33 CFR 147.847 - Safety Zone; BW PIONEER Floating Production, Storage, and Offloading System Safety Zone.

Science.gov (United States)

2010-07-01

... Production, Storage, and Offloading System Safety Zone. 147.847 Section 147.847 Navigation and Navigable... ZONES § 147.847 Safety Zone; BW PIONEER Floating Production, Storage, and Offloading System Safety Zone. (a) Description. The BW PIONEER, a Floating Production, Storage and Offloading (FPSO) system, is in...

77 FR 76003 - Submission for OMB Review; Comment Request-Safety Standard for Omnidirectional Citizens Band Base...

Science.gov (United States)

2012-12-26

... Request--Safety Standard for Omnidirectional Citizens Band Base Station Antennas AGENCY: Consumer Product... information associated with the Commission's safety standard for omnidirectional citizens band base station... information required in the Safety Standard for Omnidirectional Citizens Band Base Station (16 CFR Part 1204...

Nuclear Regulatory Commission issuances. Volume 23, No. 3

International Nuclear Information System (INIS)

1986-03-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), and the Directors' Decisions (DD)

Safety policy in the production of electricity

International Nuclear Information System (INIS)

Siddall, E.

1983-01-01

When safety is properly understood, defined and quantified, it can be seen that the development of our present industrial civilization has resulted in a progressive and great improvement in human safety which is still continuing. Increased safety has come with increased wealth in such close association that a high degree of cause-and-effect relationship must be considered. The quantitative relationship between wealth production and safety improvement is derived from different sources of evidence. When this is applied to the wealth production from electricity generation in a standard module of population in an advanced society, a safety benefit is indicated which exceeds the assessed direct risk associated with the electricity generation by orders of magnitude. It appears that a goal or policy intended to confer the greatest safety benefit to the population would result in attitudes and actions diametrically opposite to those which are conventional at the moment

Management present situation and countermeasures of coal mines safety in production

Institute of Scientific and Technical Information of China (English)

ZHANG Shu-dong; YU Chang-wu

2008-01-01

Analyzed of the present situation of Chinese coal mines safety in production and the reasons for coal mining accident, and realized the coal mines safety in production,which should increase the legal safeguards of coal mine safety in production, and safety input, established the comprehensive coal mine safety evaluation system, comprehensively enhance quality of coal mine workers, established and improved early warning mechanism of safety production of coal mine.

How Productive Is Workplace Health and Safety?

DEFF Research Database (Denmark)

Buhai, I. Sebastian; Cottini, Elena; Westergaard-Nielsen, Niels

2017-01-01

In this paper, we investigate the causal impact of workplace health and safety practices on firm performance, using Danish longitudinal matched employer–employee data merged with unique cross-sectional representative firm survey data on work environment conditions. We estimate standard production...... functions, augmented with workplace environment indicators, addressing both time-invariant and time-varying potentially relevant unobservables in the production process. We find positive and large productivity effects of improved physical dimensions of the health and safety environment, specifically...

Nuclear Regulatory Commission issuance, pages 933-1089

International Nuclear Information System (INIS)

1981-11-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors Denial (DD), and the Denial of Petitions for Rulemaking

42 CFR 3.208 - Continued protection of patient safety work product.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Continued protection of patient safety work product... GENERAL PROVISIONS PATIENT SAFETY ORGANIZATIONS AND PATIENT SAFETY WORK PRODUCT Confidentiality and Privilege Protections of Patient Safety Work Product § 3.208 Continued protection of patient safety work...

Study of the effectiveness of the US safety standard for child resistant cigarette lighters

OpenAIRE

Smith, L; Greene, M; Singh, H

2002-01-01

Objective: The purpose of this research is to evaluate the effectiveness of the US Consumer Product Safety Commission's (CPSC) Safety Standard for Cigarette Lighters, which requires that disposable cigarette lighters be resistant to operation by children younger than age 5.

EFSA NDA Panel (EFSA Panel on Dietetic Products, Nutrition and Allergies), 2013 . S tatement on the safety of ' Cetyl Myristoleate Complex ' as an ingredient in food supplements

DEFF Research Database (Denmark)

Tetens, Inge

Following a request from the European Commission, the Panel on Dietetic Products, Nutrition and Allergies was asked to update its opinion on the safety of „Cetyl Myristoleate Complex‟ (CMC) as a novel food ingredient in the light of a new repeated dose 90-day oral toxicity study in mice. In its p...

Review report: safety and reliability issues on digital instrumentation and control systems in nuclear power plants and United States Nuclear Regulatory Commission`s dispositions

Energy Technology Data Exchange (ETDEWEB)

Watanabe, Norio; Suzudo, Tomoaki [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1998-09-01

Recently, digital instrumentation and control (I and C) systems have been applied to nuclear power plants (NPPs) in various countries. Introduction of digital I and C systems, however, raises special issues on design, implementation, safety and licensing. Since FY 1997, the Japan Atomic Energy Research Institute (JAERI) has been carrying out a project, Study on Reliability of Digital I and C Systems, which includes extensive reviews of design approaches, technical standards, regulatory processes, especially, in the United States. This report summarizes the results from the study of National Research Council (NRC) and the U.S. Nuclear Regulatory Commission`s (USNRC`s) responses to the recommendations made by the NRC`s study. That study identified six technical key issues (system aspects of digital I and C technology, software quality assurance, common-mode software failure potential, safety and reliability assessment methods, human factors and man-machine interface, dedication of commercial off-the-shelf hardware and software) and two strategic key issues (case-by-case licensing process, adequacy of technical infrastructure) that arise from the introduction of digital I and C technology and then, made recommendations to the USNRC for coping with digital I and C applications. The USNRC responded to each recommendation and showed their own dispositions in which the USNRC agreed with most of the recommendations. In Japan, it is expected that introduction of digital I and C technology is inevitable in NPPs because the vendors are gradually discontinuing support and stocking of analog components. To cope with such situations, there is a need to develop and update the standards and guidelines applicable to digital I and C technology. The key issues and the USNRC`s dispositions provided in this report is believed to be useful for developing and updating them. (J.P.N.)

Safety issues at the defense production reactors

International Nuclear Information System (INIS)

1987-01-01

The United States produces plutonium and tritium for use in nuclear weapons at the defense production reactors endash the N Reactor in Washington and the Savannah River reactors in South Carolina. This report reaches general conclusions about the management of those reactors and highlights a number of safety and technical issues that should be resolved. The report provides an assessment of the safety management, safety review, and safety methodology employed by the Department of Energy and the private contractors who operate the reactors for the federal government. The report is necessarily based on a limited review of the defense production reactors. It does not address whether any of the reactors are ''safe,'' because such an analysis would involve a determination of acceptable risk endash a matter of obvious importance, but one that was beyond the purview of the committee. It also does not address whether the safety of the production reactors is comparable to that of commercial nuclear power stations, because even this narrower question extended beyond the charge to the committee and would have involved detailed analyses that the committee could not undertake

International co-operation in safety matters within the framework of the Commission of the European Communities

International Nuclear Information System (INIS)

Vinck, W.; Balz, W.; Essler, W.; Tolley, B.; Gabolde, J.

1981-01-01

European Community (EC) countries realize that their energy demand cannot be met without a nuclear component, which is almost a necessity owing to its major economic advantages. Two typical areas where the Commission has stimulated intense international co-operation are as follows: The first broad area deals with efforts towards a gradual harmonization of regulatory health and safety practices and requirements for reactors of an industrially developed type, more specifically (light) water-cooled reactors. The second area concerns joint research programmes and co-ordination activities in research on nuclear safety (LWRs and LMFBRs). These two broad areas are closely interconnected. Information is also given on the existing network of bilateral and multilateral arrangements for the exchange of information of interest to the EC. In conclusion, some problems are highlighted where improvements could be made or where it seems crucial that increased international co-operation and especially agreement should come about. (author)

Continuity and enhancement of quality management during commissioning of W7-X

Energy Technology Data Exchange (ETDEWEB)

Vilbrandt, Reinhard, E-mail: reinhard.vilbrandt@ipp.mpg.de; Bosch, Hans-Stephan; Feist, Jost-Henrich; Klinger, Thomas

2015-10-15

Highlights: • Commissioning follows the W7-X structure into appropriate components, subsystems and systems. • Local and integrated commissioning steps are carried out alternately. • An exact and detailed preparation of all commissioning is absolutely necessary. • Templates support instruction manuals, safety analyses, and commissioning instructions. • Because of safety special attention must be paid to the first putting into service. - Abstract: The commissioning of Wendelstein 7-X, the first numerically optimized stellarator, is a new phase in the project. The general planning and execution of the commissioning of the entire W7-X system follow its structure into appropriate components, subsystems and systems. The approach for taking these systems into operation will lead to so-called local commissioning which is usually executed for individual systems in connection with the necessary peripheral devices and auxiliary systems. The subsequent step-wise testing and commissioning of the systems in connection with the central device of W7-X, including the central safety control, and the central data acquisition system is performed in the second step, the so-called integrated commissioning. This leads directly to the preparation of first plasma operation. New organizational and quality management elements have been added to the running system, or existing, proven tools have been modified. The major new organizational structures and tasks and the quality planning and assurance tools are described in more detail. The experience during the first commissioning steps of the vacuum and cryogenic systems is outlined.

Experience relevant to safety obtained from reactor decommissioning operations in the French Atomic Energy Commission

International Nuclear Information System (INIS)

Giraudel, B.; Langlois, G.

1979-01-01

From among the nuclear facilities constructed in France the authors cite eight large reactors, ranging from critical assemblies to power reactors, that have been finally shut-down since 1965. A brief account is given of the way in which the various operations were carried out after the final control rod drop, a distinction being drawn between the shut-down proper and the containment and dismantling work. A description is also given, from the technical and regulatory standpoint, of the final stage attained, and mention is made of French safety arrangements and of the part played by the safety services during decommissioning operations. Among the lessons derived from French experience, the authors mention the completion of operations without any serious safety problems, and with guarantees for the protection of personnel and the population as a whole, by conventional techniques; the advantage of planning decommissioning operations from the very beginning of construction of the facilities; and the importance of filing descriptive documents. In view of the experience gained, the French Atomic Energy Commission has devised internal procedures for facilitating the application of regulations governing the shut-down and decommissioning phases, which are aimed at preserving surveillance procedures similar to those in force during normal operation. (author)

U.S. Nuclear Regulatory Commission Safety Culture Oversight

International Nuclear Information System (INIS)

Sieracki, D. J.

2016-01-01

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

Relevance of microbial finished product testing in food safety management

DEFF Research Database (Denmark)

Zwietering, Marcel H.; Jacxsens, Liesbeth; Membré, Jeanne Marie

2016-01-01

Management of microbiological food safety is largely based on good design of processes, products and procedures. Finished product testing may be considered as a control measure at the end of the production process. However, testing gives only very limited information on the safety status of a food......-active way by implementing an effective food safety management system. For verification activities in a food safety management system, finished product testing may however be useful. For three cases studies; canned food, chocolate and cooked ham, the relevance of testing both of finished products....... If a hazardous organism is found it means something, but absence in a limited number of samples is no guarantee of safety of a whole production batch. Finished product testing is often too little and too late. Therefore most attention should be focussed on management and control of the hazards in a more pro...

Experience gained during commissioning and trial operation of Mochovce Nuclear Power Plant

International Nuclear Information System (INIS)

GaL, P.; Adamica, T.; Marosik, V.; Rehak, A.

2000-01-01

In this paper authors describe the experience gained during commissioning and trial operation of Mochovce NPP (EMO). The first year of EMO operation from the point of view of safety and reliability was successful. Evidently we were challenged with certain problems characteristic to this stage of operation which resulted in automatic reactor shutdown. There were 11 automatic shutdowns in 1998 by action of the quick emergency protection AO-1 and two manual shutdowns by the AO-1 key. In 1999, there were 6 automatic shutdowns by action of the quick emergency protection AO-1. Three of them was connected to the falsely activated binary signal of MCP switch of, in two cases the reason came out from the turbo-generator (TG) cooling water system. Very positive trend in the operation of both units shows the fact that during all commissioning period of the second unit there were only three automatic reactor shutdowns by the signal AO-1. All these actions were done in frame of commissioning tests. All causes which activated the automatic unit shutdowns were found out and rectified, the overall tuning of the cooling water system is on the process now. The solution of this problem is possible only power commissioning, and in the stage of the trial operation had no direct impacts on the nuclear, radiation, or technical safety respectively. In 1998 two events according to the INES scale after second unit commissioning because of two unit links of the cooling water system. The operational events during the commissioning tests, start-up tests, physical commissioning, were ranked the category 1 ('Action of SIS U040 p po <8,34 MPa at the system 2 and 3' and 'Breaching the L and C'). In 1999 only events occurred that were ranked in the category safety insignificant events and lower (category 0, or off the scale respectively). In the frame of the safety culture principles adopted, such as critical attitude, exact and careful approach, and communication, these problems were given the

Characterization of the animal by-product meal industry in Costa Rica: Manufacturing practices through the production chain and food safety.

Science.gov (United States)

Leiva, A; Granados-Chinchilla, F; Redondo-Solano, M; Arrieta-González, M; Pineda-Salazar, E; Molina, A

2018-06-01

Animal by-product rendering establishments are still relevant industries worldwide. Animal by-product meal safety is paramount to protect feed, animals, and the rest of the food chain from unwanted contamination. As microbiological contamination may arise from inadequate processing of slaughterhouse waste and deficiencies in good manufacturing practices within the rendering facilities, we conducted an overall establishment's inspection, including the product in several parts of the process.An evaluation of the Good Manufacturing Practices (GMP) was carried out, which included the location and access (i.e., admission) to the facilities, integrated pest management programs, physical condition of the facilities (e.g., infrastructure), equipments, vehicles and transportation, as well as critical control points (i.e., particle size and temperature set at 50 mm, 133°C at atmospheric pressure for 20 min, respectively) recommended by the OIE and the European Commission. The most sensitive points according to the evaluation are physical structure of the facilities (avg 42.2%), access to the facilities (avg 48.6%), and cleaning procedures (avg 51.4%).Also, indicator microorganisms (Salmonella spp., Clostridium spp., total coliforms, E. coli, E. coli O157:H7) were used to evaluate the safety in different parts of the animal meal production process. There was a prevalence of Salmonella spp. of 12.9, 14.3, and 33.3% in Meat and Bone Meal (MBM), poultry by-products, and fish meal, respectively. However, there were no significant differences (P = 0.73) in the prevalence between the different animal meals, according to the data collected.It was also observed that renderings associated with the poultry industry (i.e., 92.0%) obtained the best ratings overall, which reflects a satisfactory development of this sector and the integration of its production system as a whole.

Commissioning quality assurance for nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

NONE

1986-09-01

This standard contains the requirements for the quality assurance program applicable to the commissioning phase of a nuclear power plant. This standard embodies the relevant quality assurance requirements of CSA Standard CAN3-N286.0, and is the governing Standard for commissioning quality assurance activities in the event of any conflicting requirements. This Standard applies to the commissioning of safety-related equipment, systems, and structures as identified by the owner. It may be applied to other equipment, systems, and structures at the discretion of the owner. 1 fig.

Commissioning quality assurance for nuclear power plants

International Nuclear Information System (INIS)

1986-09-01

This standard contains the requirements for the quality assurance program applicable to the commissioning phase of a nuclear power plant. This standard embodies the relevant quality assurance requirements of CSA Standard CAN3-N286.0, and is the governing Standard for commissioning quality assurance activities in the event of any conflicting requirements. This Standard applies to the commissioning of safety-related equipment, systems, and structures as identified by the owner. It may be applied to other equipment, systems, and structures at the discretion of the owner. 1 fig

78 FR 29392 - Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied...

Science.gov (United States)

2013-05-20

... NUCLEAR REGULATORY COMMISSION [NRC-2013-0098] Embedded Digital Devices in Safety-Related Systems, Systems Important to Safety, and Items Relied on for Safety AGENCY: Nuclear Regulatory Commission. ACTION... (NRC) is issuing for public comment Draft Regulatory Issue Summary (RIS) 2013-XX, ``Embedded Digital...

Nuclear Regulatory Commission issuances, Volume 18, No. 5

International Nuclear Information System (INIS)

1983-11-01

This report includes the issuances received during November, 1983, from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances. Volume 22, No. 1

International Nuclear Information System (INIS)

1985-07-01

This report includes the issuances received during July 1985 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 22, No. 5

International Nuclear Information System (INIS)

1985-11-01

This report includes the issuances received during November 1985 from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Targetry at the LANL 100 MeV isotope production facility: lessons learned from facility commissioning

Energy Technology Data Exchange (ETDEWEB)

Nortier, F. M. (Francois M.); Fassbender, M. E. (Michael E.); DeJohn, M.; Hamilton, V. T. (Virginia T.); Heaton, R. C. (Richard C.); Jamriska, David J.; Kitten, J. J. (Jason J.); Lenz, J. W.; Lowe, C. E.; Moddrell, C. F.; McCurdy, L. M. (Lisa M.); Peterson, E. J. (Eugene J.); Pitt, L. R. (Lawrence R.); Phillips, D. R. (Dennis R.); Salazar, L. L. (Louie L.); Smith, P. A. (Paul A.); Valdez, Frank O.

2004-01-01

The new Isotope Production Facility (IPF) at Los Alamos National Laboratory has been commissioned during the spring of 2004. Commissioning activities focused on the establishment of a radionuclide database, the review and approval of two specific target stack designs, and four trial runs with subsequent chemical processing and data analyses. This paper highlights some aspects of the facility and the targetry of the two approved target stacks used during the commissioning process. Since one niobium encapsulated gallium target developed a blister after the extended irradiation of 4 days, a further evaluation of the gallium targets is required. Beside this gallium target, no other target showed any sign of thermal failure. Considering the uncertainties involved, the production yields obtained for targets irradiated in the same energy slot are consistent for all three 'Prototype' stacks. A careful analysis of the temperature profile in the RbCl targets shows that energy shifts occur in the RbCl and Ga targets. Energy shifts are a result of density variations in the RbCl disk under bombardment. Thickness adjustments of targets in the prototype stack are required to ensure maximum production yields of {sup 82}Sr and {sup 68}Ge in the design energy windows. The {sup 68}Ge yields obtained are still consistently lower than the predicted yield value, which requires further investigation. After recalculation of the energy windows for the RbCl and Ga targets, the measured {sup 82}Sr production yields compare rather well with values predicted on the basis of evaluated experimental excitation function data.

77 FR 51731 - All-Terrain Vehicle Safety Summit

Science.gov (United States)

2012-08-27

...; Physical sizing of ATVs 2. Consumer Awareness Suggested topics: Point-of-purchase information; on-product... safety require additional research that is beyond the Commission's current budget and resources. CPSC.... The Summit will take place over 2 days and will feature a mix of rulemaking and nonrulemaking topic...

77 FR 52272 - Safety Standard for Play Yards

Science.gov (United States)

2012-08-29

... for Laboratory Sciences, Consumer Product Safety Commission, 5 Research Place, Rockville, MD 20850.... Introduction The Regulatory Flexibility Act (``RFA''), 5 U.S.C. 601-612, requires agencies to consider the... political subdivision of a state may establish or continue in effect a requirement dealing with the same...

Packaging Evaluation Approach to Improve Cosmetic Product Safety

OpenAIRE

Benedetta Briasco; Priscilla Capra; Arianna Cecilia Cozzi; Barbara Mannucci; Paola Perugini

2016-01-01

In the Regulation 1223/2009, evaluation of packaging has become mandatory to assure cosmetic product safety. In fact, the safety assessment of a cosmetic product can be successfully carried out only if the hazard deriving from the use of the designed packaging for the specific product is correctly evaluated. Despite the law requirement, there is too little information about the chemical-physical characteristics of finished packaging and the possible interactions between formulation and packag...

Theoretical Application of Supervision over Quality and Safety of Agricultural Products

Institute of Scientific and Technical Information of China (English)

Xin; CHENG; Ying; ZHANG

2013-01-01

Supervision over quality and safety of agricultural products has received high attention of management department.Competent authorities have formulated and issued many measures to strengthen supervision over quality and safety of agricultural products and improve China’s agricultural product quality and safety level.From the perspective of management science,this paper elaborates basic contents of two basic management theories,Broken Windows Effect and Effect of Heat Furnace.Then,it analyzes influence of Broken Windows Effect and Effect of Heat Furnace on supervision over quality and safety of agricultural products.Finally,it comes up with recommendations for supervision over quality and safety of agricultural products.

Analysis on safety production in coal mines Henan Province

Institute of Scientific and Technical Information of China (English)

KONG Liu-an; ZHANG Wen-yong

2006-01-01

Based on the rigorous situation of safety production in coal mines, the paper analyzed the statistical data of recent accidents indexes in Henan's coal mines. Using investigation and comparison analysis methods, a specified analysis on mining conditions, technical facility level, safety input and vocational quality of workers in Henan's coal mines was conducted. The result indicates that there have been existing such main safety production problems as weak safety management, low-level facilities, inadequate safety input and poor vocational quality and so on. Finally it proposes such reference solutions as to establish and perfect coal mining supervision and management system, to increase safety investment into techniques and facilities and to strengthen workers' safety education and introduction of more high-level professional talents.

76 FR 69481 - Testing and Labeling Pertaining to Product Certification

Science.gov (United States)

2011-11-08

... 1107 Testing and Labeling Pertaining to Product Certification; Final Rule #0;#0;Federal Register / Vol... Pertaining to Product Certification AGENCY: Consumer Product Safety Commission. ACTION: Final rule. SUMMARY... that the product complies with the certification requirements under section 14(a) of the Consumer...

Nuclear Regulatory Commission Issuances. Opinions and decisions of the Nuclear Regulatory Commission with selected orders: July 1, 1992--December 31, 1992, Volume 36, Pages 1--396

Energy Technology Data Exchange (ETDEWEB)

1992-12-31

This is the thirty-sixth volume of issuances (1-396) of the Nuclear Regulatory Commission and its Atomic Safety and Licensing Boards, Administrative Law Judges, and Office Directors. It covers the period from July 1, 1992-December 31, 1992. Atomic Safety and Licensing Boards are authorized by Section 191 of the Atomic Energy Act of 1954. These Boards, comprised of three members conduct adjudicatory hearings on applications to construct and operate nuclear power plants and related facilities and issue initial decisions which, subject to internal review and appellate procedures, become the final Commission action with respect to those applications. Boards are drawn from the Atomic Safety and Licensing Board Panel, comprised of lawyers, nuclear physicists and engineers, environmentalists, chemists, and economists. The Atomic Energy Commission first established Licensing Boards in 1962 and the Panel in 1967.

77 FR 22564 - Proposed Collection; Comment Request; Safety Standards for Full-Size Baby Cribs and Non-Full-Size...

Science.gov (United States)

2012-04-16

... CONSUMER PRODUCT SAFETY COMMISSION [Docket No. CPSC-2012-0019] Proposed Collection; Comment Request; Safety Standards for Full- Size Baby Cribs and Non-Full-Size Baby Cribs; Compliance Form AGENCY... safety standards for full-size and non-full-size baby cribs in response to the direction under section...

Optimization of safety production supervision mode of coalmining enterprises

Energy Technology Data Exchange (ETDEWEB)

Zhou, M.; Xiao, Z. [China University of Mining and Technology, Xuzhou (China). School of Management

2005-12-01

In view of the fact that safety production supervision of coal mines in China features low efficacy, this paper applies principles of cybernetics to simulate the dynamic process of safety supervision, and proposes that institutional variables be controlled to support intermediate goals, which in turn contribute to the ultimate safety production objective. Rather than focussing all attention on safety issues of working faces, supervising departments of coalmines are advised to pay much more attention to institutional factors that may impact people's attitude and behavior, which are responsible for most coalmine accidents. It is believed that such a shift of attention can effectively reduce coalmining production accidents and greatly enhance supervision efficacy. 8 refs., 5 figs.

Nuclear Regulatory Commission issuances. Vol. 16, No. 5

International Nuclear Information System (INIS)

1982-11-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 17, No. 4

International Nuclear Information System (INIS)

1983-04-01

This report includes the issuances received during the specified period from the Commission (CLi), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances. Volume 23, No. 1

International Nuclear Information System (INIS)

1986-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 20, No. 4

International Nuclear Information System (INIS)

1984-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 22, No. 6

International Nuclear Information System (INIS)

1985-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 20, No. 2

International Nuclear Information System (INIS)

1984-08-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 21, No. 6

International Nuclear Information System (INIS)

1985-06-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 21, No. 5

International Nuclear Information System (INIS)

1985-05-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Vol. 16, No. 4

International Nuclear Information System (INIS)

1982-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Vol. 16, No. 1

International Nuclear Information System (INIS)

1982-07-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions For Rulemaking (DPRM)

Nuclear Regulatory Commission Issuances. Volume 23, No. 2

International Nuclear Information System (INIS)

1986-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

COMMISSIONING AND DETECTOR PERFORMANCE GROUPS (DPG)

CERN Multimedia

Tiziano Camporesi

Pit commissioning activities The last 4 months have seen various major achievements in hardware commissioning, global data taking, readiness of the DPGs to deal with LHC data flows and alignment and calibration workflows. Since February, the global commissioning has been characterized on the one side by more and more of the final CMS detector becoming available for global readout and triggering and on the other side by consolidation of many of the central software infrastructure and of most of the services infrastructure. The reliability of services like cooling, power, gas has markedly improved with respect to what we observed in the second half of 2007.   Of particular note are the delivery of all low voltage power supplies, the commissioning of the final power distribution, the progressive commissioning ( still ongoing)  of the Detector Safety System and of the associated DCS early warning and alarm system. On the detector side, while already we are used to seeing all of HCAL being exe...

The Canadian Nuclear Safety Commission regulatory process for decommissioning a uranium mining facility

International Nuclear Information System (INIS)

Scissons, K.; Schryer, D.M.; Goulden, W.; Natomagan, C.

2002-01-01

The Canadian Nuclear Safety Commission (CNSC) regulates uranium mining in Canada. The CNSC regulatory process requires that a licence applicant plan for and commit to future decommissioning before irrevocable decisions are made, and throughout the life of a uranium mine. These requirements include conceptual decommissioning plans and the provision of financial assurances to ensure the availability of funds for decommissioning activities. When an application for decommissioning is submitted to the CNSC, an environmental assessment is required prior to initiating the licensing process. A case study is presented for COGEMA Resources Inc. (COGEMA), who is entering the decommissioning phase with the CNSC for the Cluff Lake uranium mine. As part of the licensing process, CNSC multidisciplinary staff assesses the decommissioning plan, associated costs, and the environmental assessment. When the CNSC is satisfied that all of its requirements are met, a decommissioning licence may be issued. (author)

HTGR safety research at the Los Alamos National Laboratory

International Nuclear Information System (INIS)

Stroh, K.R.; Anderson, C.A.; Kirk, W.L.

1982-01-01

This paper summarizes activities undertaken at the Los Alamos National Laboratory as part of the High-Temperature Gas-Cooled Reactor (HTGR) Safety Research Program sponsored by the US Nuclear Regulatory Commission. Technical accomplishments and analysis capabilities in six broad-based task areas are described. These tasks are: fission-product technology, primary-coolant impurities, structural investigations, safety instrumentation and control systems, accident delineation, and phenomena modeling and systems analysis

Atomic Energy Commission reports. Volume 6. Opinions and decisions of the Atomic Energy Commission with selected orders, January 1, 1973 to December 31, 1973

International Nuclear Information System (INIS)

1974-01-01

Issuances of the Atomic Energy Commission, the Atomic Safety and Licensing Appeal Boards, the Atomic Safety and Licensing Boards, and the Board of Contract Appeals including the Contract Adjustment Board are presented. (U.S.)

Guidelines for residential commissioning

Energy Technology Data Exchange (ETDEWEB)

Wray, Craig P.; Walker, Iain S.; Sherman, Max H.

2003-01-31

Currently, houses do not perform optimally or even as many codes and forecasts predict, largely because they are field assembled and there is no consistent process to identify problems or to correct them. Residential commissioning is a solution to this problem. This guide is the culmination of a 30-month project that began in September 1999. The ultimate objective of the project is to increase the number of houses that undergo commissioning, which will improve the quality, comfort, and safety of homes for California citizens. The project goal is to lay the groundwork for a residential commissioning industry in California focused on end-use energy and non-energy issues. As such, we intend this guide to be a beginning and not an end. Our intent is that the guide will lead to the programmatic integration of commissioning with other building industry processes, which in turn will provide more value to a single site visit for people such as home energy auditors and raters, home inspectors, and building performance contractors. Project work to support the development of this guide includes: a literature review and annotated bibliography, which facilitates access to 469 documents related to residential commissioning published over the past 20 years (Wray et al. 2000), an analysis of the potential benefits one can realistically expect from commissioning new and existing California houses (Matson et al. 2002), and an assessment of 107 diagnostic tools for evaluating residential commissioning metrics (Wray et al. 2002). In this guide, we describe the issues that non-experts should consider in developing a commissioning program to achieve the benefits we have identified. We do this by providing specific recommendations about: how to structure the commissioning process, which diagnostics to use, and how to use them to commission new and existing houses. Using examples, we also demonstrate the potential benefits of applying the recommended whole-house commissioning approach to

Nuclear Regulatory Commission issuances, September 1995. Volume 42, Number 3

International Nuclear Information System (INIS)

1995-09-01

This book contains an issuance of the Atomic Safety and Licensing Board and a Director's Decision, both of the US Nuclear Regulatory Commission. The issuance concerns the dismissal of a case by adopting a settlement reached by the Staff of the Nuclear Regulatory Commission and a Radiation Safety Officer of a hospital in which the safety officer pled guilty to deliberate misconduct. The Director's Decision was to deny a petition to impose a fine on Tennessee Valley Authority concerning alleged harassment of the petitioner and to appoint an independent arbitration board to review all past complaints filed against TVA concerning the Watts Bar Nuclear Plant

Nuclear Regulatory Commission issuances, September 1995. Volume 42, Number 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-09-01

This book contains an issuance of the Atomic Safety and Licensing Board and a Director`s Decision, both of the US Nuclear Regulatory Commission. The issuance concerns the dismissal of a case by adopting a settlement reached by the Staff of the Nuclear Regulatory Commission and a Radiation Safety Officer of a hospital in which the safety officer pled guilty to deliberate misconduct. The Director`s Decision was to deny a petition to impose a fine on Tennessee Valley Authority concerning alleged harassment of the petitioner and to appoint an independent arbitration board to review all past complaints filed against TVA concerning the Watts Bar Nuclear Plant.

16 CFR 1211.24 - Product certification and labeling by manufacturers.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Product certification and labeling by manufacturers. 1211.24 Section 1211.24 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT... § 1211.24 Product certification and labeling by manufacturers. (a) Form of permanent label of...

Indexes to Nuclear Regulatory Commission issuances, January-March 1987

International Nuclear Information System (INIS)

1987-09-01

Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document

42 CFR 3.206 - Confidentiality of patient safety work product.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Confidentiality of patient safety work product. 3... individually identifiable health information in such patient safety work product, the direct identifiers listed at 45 CFR 164.514(e)(2) have been removed. (5) Disclosure of nonidentifiable patient safety work...

Nuclear Regulatory Commission issuances, April 1994

International Nuclear Information System (INIS)

1994-04-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, June 1992

International Nuclear Information System (INIS)

1992-06-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, December 1991

International Nuclear Information System (INIS)

1991-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, January 1992

International Nuclear Information System (INIS)

1992-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Defense (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, May 1992

International Nuclear Information System (INIS)

1992-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, July 1992

International Nuclear Information System (INIS)

1992-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, December 1993

International Nuclear Information System (INIS)

1993-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, December 1992

International Nuclear Information System (INIS)

1992-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, September 1992

International Nuclear Information System (INIS)

1992-09-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, February 1992

International Nuclear Information System (INIS)

1992-01-01

This report includes the issuances received during the specified period from the Commission (CLl), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Director's Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, March 1993

International Nuclear Information System (INIS)

1993-03-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, July 1993

International Nuclear Information System (INIS)

1993-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, August 1992

International Nuclear Information System (INIS)

1992-08-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, August 1991

International Nuclear Information System (INIS)

1991-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, February 1993

International Nuclear Information System (INIS)

1993-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, November 1992

International Nuclear Information System (INIS)

1992-11-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, April 1993

International Nuclear Information System (INIS)

1993-04-01

This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

16 CFR 1211.25 - Product certification and labeling by importers.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Product certification and labeling by importers. 1211.25 Section 1211.25 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT... § 1211.25 Product certification and labeling by importers. (a) General. The importer of any automatic...

Safety of Nuclear Power Plants: Commissioning and Operation. Specific Safety Requirements (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication describes the requirements to be met to ensure the safe operation of nuclear power plants. It takes into account developments in areas such as long term operation of nuclear power plants, plant ageing, periodic safety review, probabilistic safety analysis and risk informed decision making processes. In addition, the requirements are governed by, and must apply, the safety objective and safety principles that are established in the IAEA Safety Standards Series No. SF-1, Fundamental Safety Principles. A review of Safety Requirements publications was commenced in 2011 following the accident in the Fukushima Daiichi nuclear power plant in Japan. The review revealed no significant areas of weakness and resulted in just a small set of amendments to strengthen the requirements and facilitate their implementation, which are contained in the present publication.

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

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

International Nuclear Information System (INIS)

Ramsey, Kevin M.

2013-01-01

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

Summary of the contributions to reactor safety research commissioned by the Republic of Austria and done by the Forschungszentrum Seibersdorf from 1987 to 1990

International Nuclear Information System (INIS)

Sonneck, G.; Sdouz, G.

1991-09-01

In 1987 the Forschungszentrum Seibersdorf was commissioned by the Republic of Austria with the collaboration in the Nuclear Safety Research Index, the OECD-LOFT-Programme and the International Coordinated Assessment and Application Programme (ICAAP). This report summarises the work done from 1987 to 1990, mainly in the field of thermal hydraulics, fuel rod behaviour and source term. Besides some analyses for experiments done in loops based on BWRs and PWRs of western design the work concentrated on safety researchs for WWERS. (Authors)

Safety tests file

International Nuclear Information System (INIS)

2011-01-01

The design and operation of nuclear power plants is governed by strict and clearly defined regulations designed to ensure their safety in all circumstances. Since the first nuclear reactors were commissioned, the basic safety principles and the corresponding practical requirements have constantly evolved and been enhanced, benefiting from operating experience feedback from reactors around the world (about 500 production reactors currently in service). Reactor safety has from the outset been built around the 'defense in depth' concept, which aims to prevent melting of the core and radioactive releases into the environment. It can be summarized as follows: over and above all the measures taken to prevent accidents, the principle that accidents do occur has to be accepted. We then assess their consequences and take steps to contain them at the level of severity at which they occur. (authors)

Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank

International Nuclear Information System (INIS)

Scofield, N.R.; Hardy, H.A.; Laats, E.T.

1983-02-01

The United States Nuclear Regulatory Commission (NRC) has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water safety research programs. Local direction of the program is provided by E G and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data that is to be used by code development and assessment groups in meeting the code and correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the NRC. The NRC/DAE Data Bank and the capabilities of the data access software are described

Nuclear Regulatory Commission issuances, September 1988

International Nuclear Information System (INIS)

1988-09-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

Relevance of microbial finished product testing in food safety management

NARCIS (Netherlands)

Zwietering, M.H.; Jacxsens, L.; Membre, J.M.; Nauta, M.; Peterz, M.

2016-01-01

Management of microbiological food safety is largely based on good design of processes, products and procedures. Finished product testing may be considered as a control measure at the end of the production process. However, testing gives only very limited information on the safety status of a food.

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1997-11-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1997-09-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

Nuclear Regulatory Commission Issuances

International Nuclear Information System (INIS)

1994-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

Nuclear Regulatory Commission issuances

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-09-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance.

CLI technical commission. Additional safety assessments within the EDF nuclear stock

International Nuclear Information System (INIS)

2011-01-01

This slides presentation addresses additional safety assessments within the EDF nuclear stock. It describes the context and challenges of these assessments (institutional framework, European coherence, major objectives for EDF). It describes how EDF is organised to perform these assessments: a global project after Fukushima, assessments and tests which are beyond the existing safety referential, the three defence lines and their tests. It addresses the content of assessment reports for each topic (earthquake, flooding, loss of water, loss of electric supply, accident management). It indicates some improvements proposed after the first assessments. It describes the improvements concerning the Gravelines power plant. It recalls the assessment agenda, proposes a brief overview of events, comments the results of the third decennial visit of production unit no. 1 which comprised some proof test on the primary circuit, on the reactor vessel and on the reactor building

DIVERSIFICATION OF A SAFETY FOOTWEAR PRODUCT

Directory of Open Access Journals (Sweden)

HARNAGEA Marta Cătălina

2017-05-01

Full Text Available Product diversification is a usual strategy of footwear producers. As a requirement related to competitiveness in this domain, diversification can be done by practical application of some criteria. Considering this aspect, the paper proposes a research on the diversification in the case of a safety footwear product by modifying its component patterns, while keeping the initial shape of the product. Thus, starting from a safety shoe model, diversification was performed by changing the configuration in the joining area of two patterns of the product. By joining the tongue with the bellows tongue, the upper with the quarter, the heel counter with the quarter and the collar and heel counter with quarter has resulted a family of models characterized by a reduction of the number of patterns in the product. The size of the set presents a significant influence on the theoretical nesting factor and implicitly on the size of the wastes. The analysis of the resulting new model types lead to highlighting the influence of the patterns number of the uppers and the area of the set on the usage index of the leather surface when cutting the parts and on the specific consumption.

Nuclear Regulatory Commission issuances. Volume 47, Number 3

International Nuclear Information System (INIS)

1998-03-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). The two issuances included here are: (1) the Commission issuance to the US Enrichment Corporation and (2) the Director's Decision to the North Atlantic Energy Service Corporation

77 FR 73354 - Safety Standard for Hand-Held Infant Carriers

Science.gov (United States)

2012-12-10

.... Edwards, Project Manager, Directorate for Engineering Sciences, U.S. Consumer Product Safety Commission, 5..., allergic reactions and near- choking episodes are the most common injuries reported in the remaining 58... modification of the ASTM standard to address the requirements for flammability, surface chemicals, cords...

Innovation of Supervision System for Quality and Safety of Edible Agricultural Products

Institute of Scientific and Technical Information of China (English)

Xingxing; MEI; Zhongchao; FENG

2014-01-01

This paper elaborated multidimensional characteristics of quality and safety of agricultural products,introduced current situation of quality and safety supervision of edible agricultural products in China,analyzed existing problems of quality and safety supervision system and corresponding reasons,and finally came up with recommendations for innovation of supervision system for quality and safety of agricultural products.

Annual Report to Congress of the Atomic Energy Commission for 1963

Energy Technology Data Exchange (ETDEWEB)

Seaborg, Glenn T.

1964-01-30

The document represents the 1963 Annual Report of the Atomic Energy Commission (AEC) to Congress. Beginning with this year's report, an index is included as part of the document, rather than as a separate publication.The report is divided into 7 areas for 1963, plus 11 appendices and the index. Section names are: Part One, The Atomic Energy Program - 1963; Part Two, Production and Weapons Programs; Part Three, Nuclear Reactor Programs; Part Four, Public Safety; Part Five, Other Major Activities; Part Six, Support-Type Activities; and Part Seven, Regulatory Activities.

Indexes to Nuclear Regulatory Commission issuances, January--March 1989

International Nuclear Information System (INIS)

1989-07-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

A primer of drug safety surveillance: an industry perspective. Part II: Product labeling and product knowledge.

Science.gov (United States)

Allan, M C

1992-01-01

To place the fundamentals of clinical drug safety surveillance in a conceptual framework that will facilitate understanding and application of adverse drug event data to protect the health of the public and support a market for pharmaceutical manufacturers' products. Part II of this series discusses specific issues regarding product labeling, such as developing the labeling, changing the labeling, and the legal as well as commercial ramifications of the contents of the labeling. An adverse event report scenario is further analyzed and suggestions are offered for maintaining the product labeling as an accurate reflection of the drug safety surveillance data. This article also emphasizes the necessity of product knowledge in adverse event database management. Both scientific and proprietary knowledge are required. Acquiring product knowledge is a part of the day-to-day activities of drug safety surveillance. A knowledge of the history of the product may forestall adverse publicity, as shown in the illustration. This review uses primary sources from the federal laws (regulations), commentaries, and summaries. Very complex topics are briefly summarized in the text. Secondary sources, ranging from newspaper articles to judicial summaries, illustrate the interpretation of adverse drug events and opportunities for drug safety surveillance intervention. The reference materials used were articles theoretically or practically applicable in the day-to-day practice of drug safety surveillance. The role of clinical drug safety surveillance in product monitoring and drug development is described. The process of drug safety surveillance is defined by the Food and Drug Administration regulations, product labeling, product knowledge, and database management. Database management is subdivided into the functions of receipt, retention, retrieval, and review of adverse event reports. Emphasis is placed on the dynamic interaction of the components of the process. Suggestions are offered

Recommendations of the Reactor Safety Commission (RSK) 1975-1977. Vol. 3

International Nuclear Information System (INIS)

Schneider, M.

1978-08-01

After the recommendations are published in the 'Bundesanzeiger' the Office of the RSK publishes them as a closed report, by order of the Federal Minister of the Interior. The reports are devided in two parts: Part I contains the recommendations which are given by the RSK; part II contains the official notices concerning the RSK. There also is a subject index. Three volumes are published by now: Volume 1: IRS-A-9 (December 1975), Recommendations of the RSK 1971 to 1974 (68th to 96th meeting), pages: I-1 to I-116 and II-1 to II-23 appendix a: RSK-guide lines for PWR, edition 04.74; Volume 2: IRS-A-11 (August 1976), Recommendations of the RSK 1974 to 1975, (97th to 105th meeting), pages: I-117 to I-145; Volume 3: GRS-12 (August 1978), Recommendations of the RSK 1975 to 1977 (106th to 129th meeting), pages: I-146 to I-276 and II-24 to II-25. Volume 3 also contains the recommendation on German Fuel Cycle Center which was given by the Reactor Safety Commision (RSK) in community with the Radiological Protection Commission (SSK), in autumn 1977. (orig./HP) 891 HP [de

Proceedings of the twenty-fifth annual institute on mining health, safety and research

Energy Technology Data Exchange (ETDEWEB)

Tinney, G.R.; Bacho, A.; Karmis, M. [eds.

1994-12-31

The keynote session included papers on the US Bureau of Mines - a vision for the future; clean, green and lean; and the psychology of occupational safety. The technical sessions include panel discussions on Virginia`s revised mine safety regulations, and on independent contractors. Other papers covered: criminal enforcement of regulatory violations; accidents during surface mine mobile equipment; Federal Mine Safety and Health Review Commission; safety, technological and productivity potentials of highwall mining; and accidents caused by falls of unsupported roof.

Application of Mixed Group Decision Making to Safety Evaluation of Agricultural Products

Institute of Scientific and Technical Information of China (English)

2012-01-01

In view of the gravity of issues concerning safety of agricultural products and urgency of resolving these issues,after analyzing the problems existing in safety of agricultural products,this article offers a method for evaluating safety of agricultural products on the basis of mixed group decision making.First of all,it introduces the factors influencing safety evaluation of agricultural products;subsequently,given that the judgment matrices offered by the group of experts contain both reciprocal and complementary judgment matrices in the process of jointly participating in evaluation arising from personal preference,it proposes to assemble expert information in order to obtain indicator weight using the OWA operator;finally,the process of evaluating safety of agricultural products is given.

The influence of farmland pollution on the quality and safety of agricultural products

Science.gov (United States)

Ma, Z. L.; Li, L. Y.; Ye, C.; Lin, X. Y.; B, C.; Wei

2018-02-01

The quality and safety of agricultural products is not only a major livelihood issues for people’s health, but also the main barriers to international trade of agricultural products nowadays. The soil is the foundation to the production of agricultural products and the guarantee of agricultural development. The farmland soil quality is directly related to the quality and safety of agricultural products. Our country’s soil has been polluted by a series of pollution, Such as the excessive discharge of industrial wastes, the encroachment of household waste, and the unreasonable use of pesticides and fertilizers. Soil degradation is a serious threat to the quality and safety of agricultural products, so eliminating soil degradation is the fundamental way out for quality and safety of agricultural products. By analyzing problems of the quality and safety of agricultural products in our country, and exploring the farmland soil influence on the quality and safety of agricultural products. This article provides a reference for improving the control level of quality and safety of agricultural products and the farmland soil quality.

Overview of Recent Activities on Safety Culture and Human and Organizational Factors Carried Out at the Joint Research Centre of the European Commission

International Nuclear Information System (INIS)

Stručić, M.; Manna, G.

2016-01-01

The Institute for Energy and Transport (IET) of the Joint Research Centre (JRC) of the European Commission (EC) is since more than ten years active in the field of Safety Culture (SC) and Human and Organizational Factors (HOF). Several activities related to SC and HOF have been and are carried out in the frame of the EU Nuclear Safety Clearinghouse for Operating Experience Feedback (Clearinghouse). The Clearinghouse was established in 2008 to enhance nuclear safety through the lessons learned from NPP events, and to provide help in Operational Experience Feedback (OEF) process primarily to nuclear safety Regulatory Authorities and to their Technical Support Organizations within the EU. Additionally to these activities, during the Fukushima accident, Clearinghouse has been regularly providing reports on the status and progress of the accident to the EU Regulatory Authorities. Moreover, experts, selected from the JRC staffing, were directly engaged in the EU-wide risk and safety assessments of nuclear power plants known as “the Stress Tests”.

Danish initiatives to improve the safety of meat products

DEFF Research Database (Denmark)

Wegener, Henrik Caspar

2010-01-01

and Campylobacter, and to a lesser extent Yersinia, Escherichia coli O157 and Listeria. Danish initiatives to improve the safety of meat products have focused on the entire production chain from the farm to the consumer, with a special emphasis on the pre-harvest stage of production. The control of bacterial......During the last two decades the major food safety problems in Denmark, as determined by the number of human patients, has been associated with bacterial infections stemming from meat products and eggs. The bacterial pathogens causing the majority of human infections has been Salmonella...

Safety system upgrades to a research reactor: A regulatory perspective

International Nuclear Information System (INIS)

Lamarre, G.B.; Martin, W.G.

2003-01-01

The NRU (National Research Universal) reactor, located at the Chalk River Laboratories of Atomic Energy of Canada Limited (AECL), first achieved criticality November 3, 1957. AECL continues to operate NRU for research to support safety and reliability studies for CANDU reactors and as a major supplier of medical radioisotopes. Following a detailed systematic review and assessment of NRU's design and the condition of its primary systems, AECL formally notified the Canadian Nuclear Safety Commission's (CNSC) predecessor - the Atomic Energy Control Board - in 1992 of its intention to upgrade NRU's safety systems. AECL proposed seven major upgrades to provide improvements in shutdown capability, heat removal, confinement, and reactor monitoring, particularly during and after a seismic event. From a CNSC perspective, these upgrades were necessary to meet modern safety standards. From the start of the upgrades project, the CNSC provided regulatory oversight aimed at ensuring that AECL maintained a structured approach to the upgrades. The elements of the approach include, but are not limited to, the determination of project milestones and target dates; the formalization of the design process and project quality assurance requirements; the requirements for updated documentation, including safety reports, safety notes and commissioning reports; and the approval and authorization process. This paper details, from a regulatory perspective, the structured approach used in approving the design, construction, commissioning and subsequent operation of safety system upgrades for an existing and operating research reactor, including the many challenges faced when attempting to balance the requirements of the upgrades project with AECL's need to keep NRU operating to meet its important research and production objectives. (author)

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest: Commission, Appeal Board and Licensing Board decisions, July 1972--March 1992

International Nuclear Information System (INIS)

1993-02-01

This 5th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to March 31, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

United States Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board and Licensing Board decisions, July 1972--December 1991

International Nuclear Information System (INIS)

1992-11-01

This 4th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to December 31, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

Safety managements of the linear IFMIF/EVEDA prototype accelerator

International Nuclear Information System (INIS)

Takahashi, Hiroki; Maebara, Sunao; Kojima, Toshiyuki; Narita, Takahiro; Tsutsumi, Kazuyoshi; Sakaki, Hironao; Suzuki, Hiromitsu; Sugimoto, Masayoshi

2014-01-01

Highlights: •Safety management is needed to secure the personnel safety from high dose rate. •The management of access to the accelerator vault is mainly performed by PPS. •The operation management is needed for safety during Injector and RFQ commissioning. •Pulse Duty Management system is newly developed for Injector commissioning for operation management. •PDM system is useful to reduce the radioactivation of equipment and the radiation exposure during and after beam operation. -- Abstract: On the Linear IFMIF/EVEDA Prototype Accelerator (LIPAc), the validation up to 9 MeV deuteron beam with 125 mA continuous wave is planned in Rokkasho, Aomori, Japan. Since the deuteron beam power exceeds 1 MW, safety issue related to γ-ray and neutron production is critical. To establish the safety management indispensable to reduce radiation exposure for personnel and activation of accelerator equipment, Personnel Protection System (PPS) of LIPAc control system, which works together with Radiation Monitoring System and Access Control System, was developed for LIPAc. The management of access to the accelerator vault by PPS and the beam duty management of PPS are presented in details

Report made on behalf of the inquiry commission for the enforcement of the measures preconized for the safety of the maritime transport of hazardous or polluting products and for the evaluation of their efficiency; Rapport fait au nom de la commission d'enquete sur l'application des mesures preconisees en matiere de securite du transport maritime des produits dangereux ou polluants et l'evaluation de leur efficacite

Energy Technology Data Exchange (ETDEWEB)

NONE

2003-07-01

On February 5, 2003, three years after the creation of an inquiry commission about the Erika tanker-ship wreck, the principle of a new inquiry commission about the safety of maritime transports was decided by the French house of commons. Its mission is: to evaluate the efficiency of the existing measures of prevention of marine pollution by hydrocarbons, to examine if the preconized safety measures for the transport of dangerous or polluting products are effectively enforced, and to evaluate the status of the transposition of the European directives relative to the control of hazardous ships. This document is the first tome of the report made on behalf of this inquiry commission. It comprises four parts dealing with: 1 - the Prestige tanker-ship wreck and the pollution of Spanish and French coasts: similarities with the Erika wreck but differences in the conditions of crisis management, diverging accident analyses, problems encountered in Spain, a significantly improved management of the crisis by the French administration, the public opinion and the local economy, the global increase of maritime transport and the reduction of accidents frequency; 2 - the real improvements after the Erika wreck: the significant advances but their partial implementation, the acceleration of actions following the Prestige wreck; 3 - the expected and realistic perspectives: the sustain of the political will at the national scale, the concretizing of the European decisions and the follow up of the retained trends, the need for more outstanding evolutions at the international scale; 4 - the international liability and compensation regime: its limitation to the hydrocarbons pollution, the lack of victims indemnification in the case of chemical pollution, the need for an increase of the liability of all actors of the maritime transport and the improvement of the compensation system, a community compensation fund to compensate the inefficiencies of the international compensation mechanisms

The Traceability and Safety of Fishery Products

OpenAIRE

Gheorghe Adrian ZUGRAVU; Ionica SOARE

2012-01-01

The paper follows two main objectives: to understand consumers’ perception of safety trasability and quality of fishery products and to identify communication levers in order to improve the perceived image of fishery products. The present research is focused on the fishery products, regardless of their presentation – fresh, frozen or processed. This paper conducted a questionnaire survey of Romanian consumers’ perception toward fishery products. The empirical study with brands indicated that ...

Present situation and countermeasures for managing expenses of safety in production in enterprise

International Nuclear Information System (INIS)

Pang Liefen

2012-01-01

The paper introduces the evolutions concerning accountant accounting for the capital of safety in production over the recent years, and analyses the present situation and reasons for the problems existed in enterprise as for gathering expenses of safety in production, and propose the countermeasures to reinforce the management of enterprise expenses of safety in production, in order to improve the management of enterprise expenses of safety in production and to enhance the level of the management in safety for the enterprise. (author)

Standard for administration of stable iodine pilulae. Standard of the nuclear safety commission, action for accident in TEPCO Fukushima-1 and recent European trends

International Nuclear Information System (INIS)

Ishihara, Hiroshi

2011-01-01

Preventive taking of stable-iodine tablets is effective to avoid thyroid gland disorder due to internal exposure to the radioactive iodine if radioactive iodine is released outside by any nuclear accident. In Japan, the Nuclear Safety Commission proposed the standard of the preventive taking in 2002, and, at the Fukushima Daiichi nuclear disaster, the head of the local task force instructed to take on the recommendation from the Commission. Author described the action principle of stable-iodine tablets, present concept for the preventive taking, recent change of the concept in Europe for the preventive taking, and some precepts which have shown in past Fukushima Daiichi nuclear disaster. (J.P.N.)

Overview of Nuclear Fuel-Cycle Policy and the Role of the Nuclear Safety Commission in Japan

International Nuclear Information System (INIS)

Higashi, K.; Nishinosono, S.

2008-01-01

Since the first generation of electricity by the Japan Power Demonstration Reactor in 1963, Japan has been extensively developing nuclear technologies solely for peaceful purposes. The country now operates 55 nuclear power plants consisted of BWRs and PWRs. Although Japan is one of the largest consumers of energy in the world, the country has very limited domestic energy resources. Therefore, Japan considers the nuclear power generation very important as plutonium and uranium recovered from spent fuels can be used in new nuclear fuels as quasi-domestic energy resource. For recycle use of nuclear fuels, the establishment of nuclear fuel recycling technologies including reprocessing technologies is essential. Since 1977, Japan has been recovering plutonium and uranium by a small scale reprocessing plant built by French technology. Recently, 800 ton/year scale commercial reprocessing plant is under construction. After overcoming the current technical problem in the vitrification facility, the commercial plant is expected to be in full operation soon. Concerning the disposal of radioactive wastes, which arises from nuclear utilization, sallow land disposal has already been implemented and medium depth (50 to 100 m) disposal plan is in progress. For high-level waste, possible candidate sites for disposal are being sought. In this paper, the statuses of nuclear power plants and of nuclear fuel cycle facilities in Japan are summarized. As safety is essential for these nuclear installations, safety regulations in Japan are briefly presented from the viewpoint of Nuclear Safety Commission. Furthermore, as the most significant recent safety issue in Japan, the impacts of the large near-site earthquake hit Kashiwazaki-Kariwa NPP last July are reported.(author)

Nuclear Regulatory Commission issuances

International Nuclear Information System (INIS)

1996-04-01

This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services

Nuclear Regulatory Commission issuances

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-04-01

This report includes the issuances received during the April 1996 reporting period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors` Decisions, and the Decisions on Petitions for Rulemaking. Included are issuances pertaining to: (1) Yankee Nuclear Power Station, (2) Georgia Tech Research Reactor, (3) River Bend Station, (4) Millstone Unit 1, (5) Thermo-Lag fire barrier material, and (6) Louisiana Energy Services.

Recent Cases: Administrative Law--Occupational Safety and Health Act

Science.gov (United States)

Harvard Law Review, 1976

1976-01-01

Implications of the Occupational Safety and Health Act of 1970 are described in two cases: Brennan v. Occupational Safety and Health Review Commission (Underhill Construction Corp.), and Anning-Johnson Co. v. United States Occupational Safety and Health Review Commission. (LBH)

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2004-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2003-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations. To be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources. And to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

Safety of nuclear power plants: Operation. Safety requirements

International Nuclear Information System (INIS)

2000-01-01

The safety of a nuclear power plant is ensured by means of its proper siting, design, construction and commissioning, followed by the proper management and operation of the plant. In a later phase, proper decommissioning is required. This Safety Requirements publication supersedes the Code on the Safety of Nuclear Power Plants: Operation, which was issued in 1988 as Safety Series No. 50-C-O (Rev. 1). The purpose of this revision was: to restructure Safety Series No. 50-C-O (Rev. 1) in the light of the basic objectives, concepts and principles in the Safety Fundamentals publication The Safety of Nuclear Installations; to be consistent with the requirements of the International Basic Safety Standards for Protection against Ionizing Radiation and for the Safety of Radiation Sources; and to reflect current practice and new concepts and technical developments. Guidance on fulfillment of these Safety Requirements may be found in the appropriate Safety Guides relating to plant operation. The objective of this publication is to establish the requirements which, in the light of experience and the present state of technology, must be satisfied to ensure the safe operation of nuclear power plants. These requirements are governed by the basic objectives, concepts and principles that are presented in the Safety Fundamentals publication The Safety of Nuclear Installations. This publication deals with matters specific to the safe operation of land based stationary thermal neutron nuclear power plants, and also covers their commissioning and subsequent decommissioning

75 FR 65263 - Virginia Graeme Baker Pool and Spa Safety Act; Public Accommodation; Withdrawal of Proposed Rule

Science.gov (United States)

2010-10-22

...'' or ``Act'') as ``an inn, hotel, motel, or other place of lodging, except for an establishment located... interpretive rule to interpret ``public accommodations facility'' in the VGB Act as ``an inn, hotel, motel, or... CONSUMER PRODUCT SAFETY COMMISSION 16 CFR Part 1450 Virginia Graeme Baker Pool and Spa Safety Act...

Nuclear safety research

International Nuclear Information System (INIS)

1996-01-01

The topics 'Large-sized PWR-NPP Safety Techniques Research',and 'The Key Techniques Research on the Safety Supervision and Control for Operation of Nuclear Installations' have been adopted as an apart of 'the National 9th five Year Programs for Tacking the Key Scientific and Technical Topics' which are organized by the State Planning Commission (SPC) and State Science and Technology Commission (SSTC) respectively, and have obtained a financial support from them. To play a better role with the limited fund, the NNSA laid special stress on selecting key sub-topics on nuclear safety, and carefully choosing units which would undertake sub-topics and signing technical contracts with them

Resolution proposal for the creation of an inquiry commission about the safety and transparency risks generated by the opening of the capital and the privatization of the French nuclear industry

International Nuclear Information System (INIS)

2004-12-01

The privatization of the French nuclear industry leads to three types of risks: the dilution of decision prerogatives (need of long-term investment for maintenance and safety purposes which are incompatible with immediate profits), incompatibility between private control and safety, and speculation (need of stable and durable financing for a sustainable safety). For these reasons, the French house of commons has created an inquiry commission about the safety and transparency risks linked with the capital opening and privatization of the French nuclear industry. (J.S.)

Promoting safety in nuclear installations. The IAEA has established safety standards for nuclear reactors and provides expert review and safety services to assist Member States in their application

International Nuclear Information System (INIS)

2002-01-01

More than 430 nuclear power plants (NPPs) are currently operating in 30 countries around the world. The nuclear share of total electricity production ranges from about 20 percent in the Czech Republic and United States to nearly 78 percent in France and Lithuania. Worldwide, nuclear power generates about 16% of the total electricity. The safety of such nuclear installations is fundamental. Every aspect of a power plant must be closely supervised and scrutinized by national regulatory bodies to ensure safety at every phase. These aspects include design, construction, commissioning, trial operation, commercial operation, repair and maintenance, plant upgrades, radiation doses to workers, radioactive waste management and, ultimately, plant decommissioning. Safety fundamentals comprise defence-in-depth, which means having in place multiple levels of protection. nuclear facilities; regulatory responsibility; communicating with the public; adoption of the international convention on nuclear safety including implementation of IAEA nuclear safety standards. This publication covers topics of designing for safety (including safety concepts, design principles, and human factors); operating safety (including safety culture and advance in operational safety); risk assessment and management

COMMISSIONING AND DETECTOR PERFORMANCE GROUPS

CERN Document Server

T. Camporesi

The major progress made during the last months has been in the consolidation of services for the +endcaps and three barrel wheels (YB+2, YB+1 and YB0): all subdetectors have now final power connections (including Detector Safety protection), the gas systems have been commissioned for all gas detectors (the recirculation is not yet activated for the RPC though) and detector cooling has also been commissioned. Their integration with final services is the necessary condition for being able to operate larger fractions the detector. Recent weeks have seen full HCAL, more than 50% of EB and full wheels of DTs and CSC being operated using final services. This has not yet translated into major progress of global integration due to major interruptions of central services, which have not allowed the necessary debugging and commissioning time to all the subdetec¬tors and central activities like DAQ and trigger. Moreover the running in of the final central services has introduced instabilities related to the co...

Nuclear Regulatory Commission issuances: August 1994. Volume 40, Number 2

International Nuclear Information System (INIS)

1994-08-01

This report contains the collected issuances of the US Nuclear Regulatory Commission for the month of August, 1994. The report includes issuances of the Commission, the Atomic Safety and Licensing Boards, and the Directors' Decisions. Some of the entities involved include Gulf States Utility company, Sequoyah Fuels Corporation and General Atomics, Georgia Power Company, and Arizona Public Service Company

Nuclear Regulatory Commission issuances, Volume 47, No. 1

International Nuclear Information System (INIS)

1998-01-01

This report includes the issuances received during the specified period from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking

Nuclear Regulatory Commission issuances, April 1986. Volume 23, No. 4

International Nuclear Information System (INIS)

1986-04-01

This report includes the issuances recieved during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, December 1982. Vol. 16, No. 6

International Nuclear Information System (INIS)

1982-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, June 1986. Volume 23, No. 6

International Nuclear Information System (INIS)

1986-06-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

75 FR 82071 - In the Matter of Certain Flash Memory Chips and Products Containing Same; Notice of Commission...

Science.gov (United States)

2010-12-29

... Memory Chips and Products Containing Same; Notice of Commission Decision Not To Review the ALJ's Final... flash memory chips and products containing the same by reason of infringement of various claims of... practices or exploits the '877 patent does not exist, nor is such an industry in the process of being...

Preparation of physics commissioning of Mochovce units 3 and 4

International Nuclear Information System (INIS)

Sedlacek, M.; Chrapciak, V.

2010-01-01

The Project 'Mochovce Units 3 and 4 Completion' started in 2009 and it will be finished in 2013. VUJE, Inc. is one of the five main Project contractors for the Nuclear Island and it is responsible, inter alia, for Mochovce Units 3 and 4 commissioning. The commissioning of Units 3 and 4 includes the stages of Physics Commissioning and Power Commissioning. This paper deals with the preparation of Mochovce Units 3 and 4 Physics Commissioning. In the paper there is presented a preparation of some commissioning documents, e.g. 'Quality Assurance Programme', 'Commissioning Programme', 'Stage Programme for Physics Commissioning', 'Test working programmes', 'Neutron-physics characteristics for Physics and Power Commissioning', etc. The scope of Physics Commissioning is presented by list of tests. For assessment of tests results so-called three-level acceptance criteria will be applied: realization, design and safety criteria. In the paper there are also presented computer codes, which will be used for neutron-physics characteristics calculation and the fuel loading scheme for the reactor core of Mochovce Unit 3. (Authors)

Nuclear Regulatory Commission issuances: Volume 39, Number 6

International Nuclear Information System (INIS)

1994-06-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). Issuances of the Nuclear Regulatory Commission include: (1) Advanced Medical Systems, Inc.; (2) Henry Allen, Diane Marrone, and Susan Settino; and (3) Westinghouse Electric Corporation. Issuances of the Atomic Safety and Licensing Boards include: (1) Sequoyah Fuels Corporation and General Atomics Corporation and (2) Umetco Minerals Corporation. Issuances of Director's Decisions include: (1) Advanced Medical Systems, Inc., and (2) Boston Edison Company and all boiling water reactors. The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or have any independent legal significance

Indexes to Nuclear Regulatory Commission issuances, July-September 1983

International Nuclear Information System (INIS)

1983-01-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as guide to the issuances

Nuclear reactor safety research in Idaho

International Nuclear Information System (INIS)

Zeile, H.J.

1983-01-01

Detailed information about the performance of nuclear reactor systems, and especially about the nuclear fuel, is vital in determining the consequences of a reactor accident. Fission products released from the fuel during accidents are the ultimate safety concern to the general public living in the vicinity of a nuclear reactor plant. Safety research conducted at the Idaho National Engineering Laboratory (INEL) in support of the U.S. Nuclear Regulatory Commission (NRC) has provided the NRC with detailed data relating to most of the postulated nuclear reactor accidents. Engineers and scientists at the INEL are now in the process of gathering data related to the most severe nuclear reactor accident - the core melt accident. This paper describes the focus of the nuclear reactor safety research at the INEL. The key results expected from the severe core damage safety research program are discussed

Standard model for safety analysis report of hexafluoride power plants from natural uranium

International Nuclear Information System (INIS)

1983-01-01

The standard model for safety analysis report for hexafluoride production power plants from natural uranium is presented, showing the presentation form, the nature and the degree of detail, of the minimal information required by the Brazilian Nuclear Energy Commission - CNEN. (E.G.) [pt

White paper on nuclear safety in 1981

International Nuclear Information System (INIS)

1981-01-01

The measures to research, develop and utilize atomic energy in Japan have been strengthened since the Atomic Energy Act was instituted in 1955, always on the major premise of securing the safety. The Nuclear Safety Commission established in October, 1978, has executed various measures to protect the health and safety of the nation as the center of the atomic energy safety regulation administration in Japan. Now, the Nuclear Safety Commission has published this annual report on atomic energy safety, summarizing various activities for securing the safety of atomic energy since its establishment to the end of March, 1981. This report is the inaugural issue, and the course till the Nuclear Safety Commission has made its start is also described. The report is composed of general remarks, response to the TMI accident, the safety regulation and security of nuclear facilities, the treatment and disposal of radioactive wastes, the investigation of environmental radioactivity, the countermeasures for preventing disasters around nuclear power stations and others, the research on the safety of atomic energy, international cooperation, and the improvement of the basis for securing the safety. Various related materials are attached. (Kako, I.)

Improving occupational safety and health by integration into product development

DEFF Research Database (Denmark)

Broberg, Ole

1996-01-01

A cross-sectional case study was performed in a large company producing electro-mechanical products for industrial application. The objectives were: (i) to study the product development process and the role of key actors', (ii) to identify current practice on integrating occupational safety and h...... and studies of documents. A questionnaire regarding product development tasks and occupational safety and health were distributed to 30 design and production engineers. A total of 27 completed the questionnaire corresponding to a response rate of 90 per cent.......A cross-sectional case study was performed in a large company producing electro-mechanical products for industrial application. The objectives were: (i) to study the product development process and the role of key actors', (ii) to identify current practice on integrating occupational safety...... and health into the development process, especially the efforts and attitudes of design and production engineers', and (iii) to identify key actors'reflections on how to improve this integration. The study was based on qualitative as well as quantitative methods including interviews, questionnaires...

Seismic safety margins research program overview

International Nuclear Information System (INIS)

Tokarz, F.J.; Smith, P.D.

1978-01-01

A multiyear seismic research program has been initiated at the Lawrence Livermore Laboratory. This program, the Seismic Safety Margins Research Program (SSMRP) is funded by the U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research. The program is designed to develop a probabilistic systems methodology for determining the seismic safety margins of nuclear power plants. Phase I, extending some 22 months, began in July 1978 at a funding level of approximately $4.3 million. Here we present an overview of the SSMRP. Included are discussions on the program objective, the approach to meet the program goal and objectives, end products, the probabilistic systems methodology, and planned activities for Phase I

42 CFR 3.210 - Required disclosure of patient safety work product to the Secretary.

Science.gov (United States)

2010-10-01

... 42 Public Health 1 2010-10-01 2010-10-01 false Required disclosure of patient safety work product... HUMAN SERVICES GENERAL PROVISIONS PATIENT SAFETY ORGANIZATIONS AND PATIENT SAFETY WORK PRODUCT Confidentiality and Privilege Protections of Patient Safety Work Product § 3.210 Required disclosure of patient...

Safety re-assessment of AECL test and research reactors

International Nuclear Information System (INIS)

Winfield, D.J.

1990-01-01

Atomic Energy of Canada Limited currently has four operating engineering test/research reactors of various sizes and ages; a new isotope-production reactor Maple-X10, under construction at Chalk River Nuclear Laboratories (CRNL), and a heating demonstration reactor, SDR, undergoing high-power commissioning at Whiteshell Nuclear Research Establishment (WNRE). The company is also performing design studies of small reactors for hot water and electricity production. The older reactors are ZED-2, PTR, NRX, and NRU; these range in age from 42 years (NRX) to 29 years (ZED-2). Since 1984, limited-scope safety re-assessments have been underway on three of these reactors (ZED-2, NRX AND NRU). ZED-2 and PTR are operated by the Reactor Physics Branch; all other reactors are operated by the respective site Reactor Operations Branches. For the older reactors the original safety reports produced were entirely deterministic in nature and based on the design-basis accident concept. The limited scope safety re-assessments for these older reactors, carried out over the past 5 years, have comprised both quantitative probabilistic safety-assessment techniques, such as event tree and fault analysis, and/or qualitative techniques, such as failure mode and effect analysis. The technique used for an individual assessment was dependent upon the specific scope required. This paper discusses the types of analyses carried out, specific insights/recommendations resulting from the analysis, and the plan for future analysis. In addition, during the last four years safety assessments have been carried out on the new isotope-, heat-, and electricity-producing reactors, as part of the safety design review, commissioning and licensing activities

Packaging Evaluation Approach to Improve Cosmetic Product Safety

Directory of Open Access Journals (Sweden)

Benedetta Briasco

2016-09-01

Full Text Available In the Regulation 1223/2009, evaluation of packaging has become mandatory to assure cosmetic product safety. In fact, the safety assessment of a cosmetic product can be successfully carried out only if the hazard deriving from the use of the designed packaging for the specific product is correctly evaluated. Despite the law requirement, there is too little information about the chemical-physical characteristics of finished packaging and the possible interactions between formulation and packaging; furthermore, different from food packaging, the cosmetic packaging is not regulated and, to date, appropriate guidelines are still missing. The aim of this work was to propose a practical approach to investigate commercial polymeric containers used in cosmetic field, especially through mechanical properties’ evaluation, from a safety point of view. First of all, it is essential to obtain complete information about raw materials. Subsequently, using an appropriate full factorial experimental design, it is possible to investigate the variables, like polymeric density, treatment, or type of formulation involved in changes to packaging properties or in formulation-packaging interaction. The variation of these properties can greatly affect cosmetic safety. In particular, mechanical properties can be used as an indicator of pack performances and safety. As an example, containers made of two types of polyethylene with different density, low-density polyethylene (LDPE and high-density polyethylene (HDPE, are investigated. Regarding the substances potentially extractable from the packaging, in this work the headspace solid-phase microextraction method (HSSPME was used because this technique was reported in the literature as suitable to detect extractables from the polymeric material here employed.

Indexes to Nuclear Regulatory Commission issuances, January-June 1987

International Nuclear Information System (INIS)

1988-02-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

Indexes to Nuclear Regulatory Commission issuances, July-December 1986

International Nuclear Information System (INIS)

1987-07-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

Indexes to Nuclear Regulatory Commission issuances, July-September 1986

International Nuclear Information System (INIS)

1987-06-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

Indexes to Nuclear Regulatory Commission issuances, July-December 1987

International Nuclear Information System (INIS)

1988-04-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

Indexes to Nuclear Regulatory Commission issuances, January-June 1982

International Nuclear Information System (INIS)

1982-01-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

Indexes to Nuclear Regulatory Commission issuances, July--December 1989

International Nuclear Information System (INIS)

1990-05-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

Improved safety at CERN

CERN Multimedia

2006-01-01

As announced in Weekly Bulletin No. 43/2006, a new approach to the implementation of Safety at CERN has been decided, which required taking some managerial decisions. The guidelines of the new approach are described in the document 'New approach to Safety implementation at CERN', which also summarizes the main managerial decisions I have taken to strengthen compliance with the CERN Safety policy and Rules. To this end I have also reviewed the mandates of the Safety Commission and the Safety Policy Committee (SAPOCO). Some details of the document 'Safety Policy at CERN' (also known as SAPOCO42) have been modified accordingly; its essential principles, unchanged, remain the basis for the safety policy of the Organisation. I would also like to inform you that I have appointed Dr M. Bona as the new Head of the Safety Commission until 31.12.2008, and that I will proceed soon to the appointment of the members of the new Safety Policy Committee. All members of the personnel are deemed to have taken note of the d...

Nuclear Regulatory commission issuances, Volume 42, No. 5

International Nuclear Information System (INIS)

1995-11-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 42, No. 6

International Nuclear Information System (INIS)

1995-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, Volume 45, No. 2

International Nuclear Information System (INIS)

1997-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Director's Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 42, No. 4

International Nuclear Information System (INIS)

1995-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances. Volume 42, No. 4

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

Nuclear Regulatory Commission issuances. Volume 38, No. 2

Energy Technology Data Exchange (ETDEWEB)

1993-08-01

This report includes the issuances received during the specified period from the commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors; Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

White paper on nuclear safety in 2005

International Nuclear Information System (INIS)

2006-04-01

The white paper consists of four parts. The first part described the outline of international discussions on safety culture and activities promoted by utilities and regulatory bodies in Japan. The second part explained the main activities of the Nuclear Safety Commission of Japan and nuclear regulatory authorities on nuclear safety regulation. The third part introduced various activities for ensuring overall nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster measures at nuclear facilities, progress in nuclear research, nuclear safety regulation by risk-informed utilization, environmental radiation surveys, international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission of Japan. (J.P.N.)

Report of nuclear utility industry responses to Kemeny Commission recommendations

Energy Technology Data Exchange (ETDEWEB)

NONE

1989-02-15

The purpose of this paper is to provide a report of nuclear utility industry progress in responding to the recommendations of the President's Commission on the Accident at Three Mile Island (The Kemeny Commission). On April 11, 1979, in response to TMI, President Carter established a Commission to conduct '.... a comprehensive study and investigation of the recent accident involving the nuclear power facility on Three Mile Island in Pennsylvania'. The Commission was chaired by Dr. John G. Kemeny, then President of Dartmouth College. (A list of all members of The Kemeny Commission is provided in Attachment to the Appendix ). The report of the commission's findings and recommendations was transmitted to the President in October 1979. During this same period, the nuclear utility industry responded to TMI by creating the Institute of Nuclear Power Operations (INPO) with a mission to promote the highest levels of safety and reliability - to promote excellence - in the operation of nuclear electric generating plants. In addition, the Nuclear Safety Analysis Center (NSAC) was established at the Electric Power Research Institute (EPRI to evaluate the accident and assist in determining the best industry response. In a White House paper (and press release) of December 7 1979, the President announced that he agreed fully with the spirit and intent of al the Kemeny Commission recommendations and requested that the industry and The Nuclear Regulatory Commission (NRC) comply with the recommendations. The President also recognized the industry initiative in establishing INPO and called for several actions involving the Institute; the President directed the Department of Energy and other government agencies to provide assistance to INPO and the industry. An overall status of the nuclear utility industry responses to Kemeny Commission recommendations in the key areas directly related to nuclear plant operations is provided below. A more detailed status of industry responses to the

Report of nuclear utility industry responses to Kemeny Commission recommendations

International Nuclear Information System (INIS)

1989-02-01

The purpose of this paper is to provide a report of nuclear utility industry progress in responding to the recommendations of the President's Commission on the Accident at Three Mile Island (The Kemeny Commission). On April 11, 1979, in response to TMI, President Carter established a Commission to conduct '.... a comprehensive study and investigation of the recent accident involving the nuclear power facility on Three Mile Island in Pennsylvania'. The Commission was chaired by Dr. John G. Kemeny, then President of Dartmouth College. (A list of all members of The Kemeny Commission is provided in Attachment to the Appendix ). The report of the commission's findings and recommendations was transmitted to the President in October 1979. During this same period, the nuclear utility industry responded to TMI by creating the Institute of Nuclear Power Operations (INPO) with a mission to promote the highest levels of safety and reliability - to promote excellence - in the operation of nuclear electric generating plants. In addition, the Nuclear Safety Analysis Center (NSAC) was established at the Electric Power Research Institute (EPRI to evaluate the accident and assist in determining the best industry response. In a White House paper (and press release) of December 7 1979, the President announced that he agreed fully with the spirit and intent of al the Kemeny Commission recommendations and requested that the industry and The Nuclear Regulatory Commission (NRC) comply with the recommendations. The President also recognized the industry initiative in establishing INPO and called for several actions involving the Institute; the President directed the Department of Energy and other government agencies to provide assistance to INPO and the industry. An overall status of the nuclear utility industry responses to Kemeny Commission recommendations in the key areas directly related to nuclear plant operations is provided below. A more detailed status of industry responses to the

Present status and improvement approach of atomic energy laws and safety standards

International Nuclear Information System (INIS)

Oh, B. J.; An, H. J.; Kim, S. W.; Kim, C. B.; Kang, S. C.; Lee, J. I.

2000-01-01

Major revision to the atomic energy act, which is currently undergoing are introduced: increase of members of nuclear safety commission, adoption of standard design certification, periodic safety review, production license system of radioactive isotope facilities, preparation for implementation of IAEA convention. Improvement of the notice of ministry of science and technology are discussed in accordance with the new atomic energy act, enforcement detect, and enforcement regulations, whose revision were completed in May 2000. Allocation of the code number to the notice, development procedures for the safety and regulatory guides are also introduced

Product Engineering Class in the Software Safety Risk Taxonomy for Building Safety-Critical Systems

Science.gov (United States)

Hill, Janice; Victor, Daniel

2008-01-01

When software safety requirements are imposed on legacy safety-critical systems, retrospective safety cases need to be formulated as part of recertifying the systems for further use and risks must be documented and managed to give confidence for reusing the systems. The SEJ Software Development Risk Taxonomy [4] focuses on general software development issues. It does not, however, cover all the safety risks. The Software Safety Risk Taxonomy [8] was developed which provides a construct for eliciting and categorizing software safety risks in a straightforward manner. In this paper, we present extended work on the taxonomy for safety that incorporates the additional issues inherent in the development and maintenance of safety-critical systems with software. An instrument called a Software Safety Risk Taxonomy Based Questionnaire (TBQ) is generated containing questions addressing each safety attribute in the Software Safety Risk Taxonomy. Software safety risks are surfaced using the new TBQ and then analyzed. In this paper we give the definitions for the specialized Product Engineering Class within the Software Safety Risk Taxonomy. At the end of the paper, we present the tool known as the 'Legacy Systems Risk Database Tool' that is used to collect and analyze the data required to show traceability to a particular safety standard

The Trends and their Impact on Fishery Products Safety and Quality

Directory of Open Access Journals (Sweden)

Gheorghe Adrian ZUGRAVU

2012-11-01

Full Text Available The paper follows two main objectives: to understand consumers’ perception of safety and quality of fishery products and to identify communication levers in order to improve the perceived image of fishery products. The present research is focused on the fishery products, regardless of their presentation – fresh, frozen or processed. This paper conducted a questionnaire survey of Romanian consumers’ perception toward fishery products. The empirical study with brands indicated that consumers are different awareness to domestic and foreign safety fish products. National fishery products got more attention from the consumers.

Present activities of the Nuclear Energy Commission in the field of safety of radiation sources and security of radioactive materials in Mongolia

International Nuclear Information System (INIS)

Oyuntulkhuur, N.

2001-01-01

The Radiation Safety Department of the Nuclear Energy Commission (NEC) is a regulatory body in Mongolia established in 1997. The paper gives a general overview of the main activities of the NEC on regulatory control of radiation sources in Mongolia. Mongolia declared itself a nuclear-weapon-free zone in 1992. Legal framework and waste management issues are described. The regulatory authority's co-operation with other agencies in radiation protection is also presented in this paper. (author)

The extent and influence of Asbestos Safety Awareness training among managers who had previously commissioned an asbestos survey in their workplace buildings

OpenAIRE

HICKEY, Jane; SAUNDERS, Jean; DAVERN, Peter

2015-01-01

A telephone survey was conducted among a sample of managers (n=30) in Ireland who had previously commissioned an asbestos survey in their workplace buildings. The aims of the telephone survey were to examine the extent to which managers had completed Asbestos Safety Awareness (ASA) training, and to assess how such training might influence (i) their instinctive thoughts on asbestos, and (ii) their approach to aspects of asbestos management within their buildings. Managers’ motivations for comm...

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1992-02-01

This revision of the sixth edition of the NRC Practice and Procedure Digest contains a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to March 31, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

Nuclear Regulatory Commission issuances. Volume 22, No. 4

International Nuclear Information System (INIS)

1985-10-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Appeal Boards (ALAB), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not to be deemed a part of those opinions or to have any independent legal significance

The role of the Federal Trade Commission in advertising health products and services.

Science.gov (United States)

Daynard, Matthew

2004-01-01

The Federal Trade Commission plays a unique role in enforcing well-established standards ensuring that consumers can make informed purchase and use decisions about health-related products and services based on truthful, non-misleading advertising claims while encouraging competition. Deceptive and unfair practices are defined. The importance of the "net impression" that ads convey to consumers and the need for substantiation of objective, factual claims is explained. The FTC uses its enforcement powers and consumer and industry outreach to create a climate for preventing misleading advertising.

White paper on nuclear safety in 2000

International Nuclear Information System (INIS)

2001-04-01

This report is composed of three parts and a subjective part Part 1 includes special articles on the measures for the security of nuclear safety and the future problems described from the beginning of the security. Taking consideration that there exists potential risk in the utilization of nuclear energy in addition to the previous accidents in the area of nuclear energy, future measures to take for safety security were discussed as well as the reorganization of government facilities. In addition, the measures for nuclear safety according to the special nuclear disaster countermeasure law and the future problems were described. In Part 2, the trend of nuclear safety in 2000 and the actual effects of 'the basic principle for the countermeasures of the hour' proposed by the nuclear safety commission were outlined. Moreover, the activities of the commission in 2000 were briefly described. In Part 3, various activities for security of nuclear safety, the safety regulation system and the disaster protection system in nuclear facilities, nuclear safety researches in Japan were described in addition to international cooperation as to nuclear safety. Finally, various materials related to the nuclear safety commission, and the materials on the practical activities for nuclear safety were listed in the subjective part. (M.N.)

Introductory user's manual for the US Nuclear Regulatory Commission Reactor Safety Research Data Bank. Revision 3

International Nuclear Information System (INIS)

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

1985-03-01

The United States Nuclear Regulatory Commission (USNRC) has established the NRC/Division of Accident Evaluation (DAE) Data Bank Program to collect, store, and make available data from the many domestic and foreign water reactor safety research programs. Local direction of the program is provided by EG and G Idaho, Inc., prime contractor for the Department of Energy (DOE) at the Idaho National Engineering Laboratory (INEL). The NRC/DAE Data Bank Program provides a central computer storage mechanism and access software for data to be used by code development and assessment groups in meeting the code correlation needs of the nuclear industry. The administrative portion of the program provides data entry, documentation, training, and advisory services to users and the USNRC. The NRC/DAE Data Bank and the capabilities of the data access software are described in this document

Nuclear Regulatory Commission issuances, March 1975

International Nuclear Information System (INIS)

1975-04-01

Reactor licensing actions taken by the Nuclear Regulatory Commission, the Atomic Safety and Licensing Appeal Board and the Atomic Safety and Licensing Boards for March 1975 are presented. Action was included for the following reactors: Big Rock Point Nuclear Plant; West Valley Reprocessing Plant; Limerick Generating Station, Units 1 and 2; Midland Plants, Units 1 and 2; Wolf Creek Generating Station, Unit 1; Monticello Nuclear Generating Plant, Unit 1; Douglas Point Nuclear Generating Station, Units 1 and 2; Seabrook Station, Units 1 and 2; Vermont Yankee Nuclear Power Station; and WPPSS Hanford Units 1 and 4. (U.S.)

The European community and nuclear safety

International Nuclear Information System (INIS)

Brinkhorst, L.J.

1992-01-01

Full text: Since the inception of the EURATOM Treaty (1957) the use of nuclear power has made an enormous progress. The nuclear sector has become a very important component of the production of energy. Prisoner of its success further development of the use of nuclear energy is confronted with the challenge of ensuring its integration within the framework of modern environment protection concepts. The link between the radiation protection objective and the responsibilities of the State's Authorities in the control of the design and operation of nuclear industrial facilities has become evident. On the other hand, the evolution in the perception of the transfrontier character of the nuclear risk by the population and. the drive for the political integration of Europe have led the Community Member States to an increasing concentration between their nuclear policy-making organs and in particular between their Nuclear Safety Authorities It is quite natural that the Community institutions, the Council of Ministers and the Commission and more recently the European Parliament have become active hosts and catalysts of the concentration of the Member States on the nuclear safety objectives which are at the source of the protection of the population and of the environment. The joint efforts of the Member States and the Commission have led to a reinforcement of the process of harmonisation of safety requirements for nuclear installations at Community level. A parallel concentration effort has been done by Community Member States concerning the back-end of the fuel cycle, in particular radioactive waste management. The European Community meets the conditions to become a key driving force for nuclear safety progress beyond its region because of the advanced stage of nuclear safety in the Community which includes the flexibility and completeness of its fuel cycle and the long experience of Community institutions in the promotion of harmonisation of safety objectives, criteria and

Safety evaluation of the nuclear power plant at Cattenom

International Nuclear Information System (INIS)

Anon.

1987-01-01

This is a systematic compilation of the material which was dealt with at the level of the German-French Commission (on questions of the safety of nuclear installations) in this discussions about the nuclear power plant at Cattenom. As a supplement to the report published already in 1982, the Commission has officially released its deliberation results on the subjects constructive safety measures, radiological effects, and precautions in case of an emergency. The allegations according to which the installation is wanting in safety are countered by the joint statement of the chairmen of GPR (Permanent Group on Reactors) and RSK (German Commission on Reactor Safety) of August 29, 1986. (HSCH) [de

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1992-08-01

This 2nd revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to September 30, 1991, interpreting the NRC's Rules of Pratice in 10 CFR Part 2

United States Nuclear Regulatory Commission Staff practice and procedure digest

International Nuclear Information System (INIS)

1990-08-01

This Revision Number 7 of the fifth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period July 1, 1972 to March 31, 1990, interpreting the NRC's Rules of Practice in 10 CFR Part 2

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1992-05-01

This 2nd revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to June 30, 1991, interpreting the NRC's Rules of Practice in 10 CFR Part 2

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest

International Nuclear Information System (INIS)

1993-08-01

This 7th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to September 30, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

United States Nuclear Regulatory Commission Staff practice and procedure digest

International Nuclear Information System (INIS)

1993-05-01

This 6th revision of the sixth edition of the NRC Practice and Procedure Digest contains a digest of a number of commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period of July 1, 1972 to June 30, 1992, interpreting the NRC's Rules of Practice in 10 CFR Part 2

Nuclear Regulatory Commission issuances, May 1993

International Nuclear Information System (INIS)

1993-05-01

This report contains the issuances received during the specified period (May 1993) from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM). The summaries and headnotes preceding the opinions reported herein are not deemed a part of these opinions or have any independent legal significance. Contents of this document include an Issuance of the Nuclear Regulatory Commission with respect to the Sacramento Municipal Utility District and Issuances of Directors' Decisions concerning the Interstate Nuclear Service Corporation; Niagara Mohawk Power Corporation; and Texas Utilities Electric Company, et al. and All Nuclear Power Plants with Thermo-Lag Fire Barriers

Efficacy and Safety of Pomegranate Medicinal Products for Cancer

Science.gov (United States)

Vlachojannis, Christian

2015-01-01

Preclinical in vitro and in vivo studies demonstrate potent effects of pomegranate preparations in cancer cell lines and animal models with chemically induced cancers. We have carried out one systematic review of the effectiveness of pomegranate products in the treatment of cancer and another on their safety. The PubMed search provided 162 references for pomegranate and cancer and 122 references for pomegranate and safety/toxicity. We identified 4 clinical studies investigating 3 pomegranate products, of which one was inappropriate because of the low polyphenol content. The evidence of clinical effectiveness was poor because the quality of the studies was poor. Although there is no concern over safety with the doses used in the clinical studies, pomegranate preparations may be harmful by inducing synthetic drug metabolism through activation of liver enzymes. We have analysed various pomegranate products for their content of anthocyanins, punicalagin, and ellagic acid in order to compare them with the benchmark doses from published data. If the amount of coactive constituents is not declared, patients risk not benefiting from the putative pomegranate effects. Moreover, pomegranate end products are affected by many determinants. Their declaration should be incorporated into the regulatory guidance and controlled before pomegranate products enter the market. PMID:25815026

77 FR 24722 - Draft Guidance for Industry: Safety of Nanomaterials in Cosmetic Products; Availability

Science.gov (United States)

2012-04-25

...] Draft Guidance for Industry: Safety of Nanomaterials in Cosmetic Products; Availability AGENCY: Food and... safety assessment of nanomaterials in cosmetic products. This guidance is intended to assist industry in... Cosmetic Products.'' The draft guidance is intended to assist industry in identifying the potential safety...

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Chinese Edition)

International Nuclear Information System (INIS)

2014-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation protection and safety of radiation sources: International basic safety standards. General safety requirements. Pt. 3 (French Edition)

International Nuclear Information System (INIS)

2016-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Radiation Protection and Safety of Radiation Sources: International Basic Safety Standards. General Safety Requirements. Pt. 3 (Arabic Edition)

International Nuclear Information System (INIS)

2015-01-01

This publication is the new edition of the International Basic Safety Standards. The edition is co-sponsored by seven other international organizations — European Commission (EC/Euratom), FAO, ILO, OECD/NEA, PAHO, UNEP and WHO. It replaces the interim edition that was published in November 2011 and the previous edition of the International Basic Safety Standards which was published in 1996. It has been extensively revised and updated to take account of the latest finding of the United Nations Scientific Committee on the Effects of Atomic Radiation, and the latest recommendations of the International Commission on Radiological Protection. The publication details the requirements for the protection of people and the environment from harmful effects of ionizing radiation and for the safety of radiation sources. All circumstances of radiation exposure are considered

Description of data-sources used in SafetyCube, Deliverable 3.1 of the H2020 project SafetyCube (Safety CaUsation, Benefits and Efficiency).

NARCIS (Netherlands)

Hagström, L. Thomson, R. Hermitte, T. Weijermars, W. Bos, N. Talbot, R. Thomas, P. Dupont, E. Martensen, H. Bauer, R. Hours, M. Høye, E. Jänsch, M. Murkovic, A. Niewöhner, W. Papadimitriou, E. Pérez, C. Phan, V. Usami, D. & Vázquez-de-Prada, J.

2017-01-01

Safety CaUsation, Benefits and Efficiency (SafetyCube) is a European Commission supported Horizon 2020 project with the objective of developing an innovative road safety Decision Support System (DSS) that will enable policy-makers and stakeholders to select and implement the most appropriate

Kemeny commission report. Comments by NPC (Nuclear Power Company)

Energy Technology Data Exchange (ETDEWEB)

1979-01-01

Following the accident at Three Mile island in March 1979 the Nuclear Power Company (NPC) has made evaluations of the available information and carried out preliminary investigations of the implications of the accident for all UK AGR's and for the PWR design. The results are summarized. Recommendations of the President's Commission are discussed with especial reference to those under the following headings: (1) The utility and its suppliers. (2) Training of operating personnel. (3) Technical assessment. It is concluded that while many of the relevant recommendations in the report of the President's Commission are already satisfied by UK practices for nuclear safety, and are being applied by NPC in their current programmes of work on AGR's and PWR's it is realised that it is of the utmost importance that complacent attitudes to safety are not allowed to develop. The accident at TMI and report of the Commision have provided a sharp reminder of the necessity to maintain unremitting vigilance in all aspects of design, construction and operation which are involved with the safety of the public and operators.

H.R. 5448: a bill to amend the Atomic Energy Act of 1954, as amended, to reorganize the functions of the Nuclear Regulatory Commission by abolishing the Commission and in its place establishing the Nuclear Regulation and Safety Agency. Introduced in the House of Representatives, Ninety-Ninth Congress, Second Session, August 15, 1986

International Nuclear Information System (INIS)

Anon.

1986-01-01

The Omnibus Nuclear Safety Act of 1986 amends the Atomic Energy Act of 1954 by replacing the Nuclear Regulatory Commission with a new entity, the Nuclear Regulation and Safety Agency. The purposes are to promote an energy policy that is better coordinated and more consistent with the protection of public health and safety. The new agency would also expedite licensing for construction and operation of nuclear power plants by using pre-approved standardized designs and sites

Indexes to Nuclear Regulatory Commission issuances, January--June 1989

International Nuclear Information System (INIS)

1989-09-01

Digests and indexes for issuances of the Commission, the Atomic Safety and Licensing Appeal Panel, the Atomic Safety and Licensing Board Panel, the Administrative Law Judge, the Directors' Decisions, and the Denials of Petitions of Rulemaking are presented in this document. The information elements are displayed in one or more of five separate formats. These formats are case named index digests and headers, legal citations index, subject index, and facility index

Design of agricultural product quality safety retrospective supervision system of Jiangsu province

Science.gov (United States)

Wang, Kun

2017-08-01

In store and supermarkets to consumers can trace back agricultural products through the electronic province card to query their origin, planting, processing, packaging, testing and other important information and found that the problems. Quality and safety issues can identify the responsibility of the problem. This paper designs a retroactive supervision system for the quality and safety of agricultural products in Jiangsu Province. Based on the analysis of agricultural production and business process, the goal of Jiangsu agricultural product quality safety traceability system construction is established, and the specific functional requirements and non-functioning requirements of the retroactive system are analyzed, and the target is specified for the specific construction of the retroactive system. The design of the quality and safety traceability system in Jiangsu province contains the design of the overall design, the trace code design and the system function module.

Work and safety managements for on-site installation, commissioning, tests by EU of quench protection circuits for JT-60SA

International Nuclear Information System (INIS)

Yamauchi, Kunihito; Okano, Jun; Shimada, Katsuhiro; Ohmori, Yoshikazu; Terakado, Tsunehisa; Matsukawa, Makoto; Koide, Yoshihiko; Kobayashi, Kazuhiro; Ikeda, Yoshitaka; Fukumoto, Masahiro; Kushita, Kouhei N.

2016-03-01

The superconducting Satellite Tokamak machine “JT-60SA” under construction in Naka Fusion Institute is an international collaborative project between Japan Atomic Energy Agency (JAEA) as the Implementing Agency (IA) of Japan (JA) and Fusion for Energy (F4E) as the IA of Europe (EU). The contributions for this project are based on the supply of components, and thus European manufacturer shall conduct the installation, commissioning and tests on Naka site under the general supervision by F4E via the designated institute in each EU nation. This means that JAEA had an issue to manage the works by European workers and their safety although there is no direct contract. This report describes the approaches for the work and safety managements, which were agreed with EU after the negotiation, and the completed on-site works for Quench Protection Circuits (QPC) as the first experience for EU in JT-60SA project. (author)

Jules Horowitz Reactor: Organisation for the Preparation of the Commissioning Phase and Normal Operation

Energy Technology Data Exchange (ETDEWEB)

Estrade, J.; Fabre, J. L.; Marcille, O. [French Alternative Energies end Atomic Energy Commission, Provence (France)

2013-07-01

The Jules Horowitz Reactor (JHR) is a new modern Material Testing Reactor (MTR) currently under construction at CEA Cadarache research centre in the south of France. It will be a major research facility in support to the development and the qualification of materials and fuels under irradiation with sizes and environment conditions relevant for nuclear power plants in order to optimise and demonstrate safe operations of existing power reactors as well as to support future reactors design. It will represent also an important research infrastructure for scientific studies dealing with material and fuel behaviour under irradiation. The JHR will contribute also to secure the production of radioisotope for medical application. This is a key public health stake. The construction of JHR which started in 2007 is going-on with target of commissioning by the end of 2017. The design of the reactor provides modern experimental capacity in support to R and D programs for the nuclear energy for the next 60 years. In parallel to the facility construction, the preparation of the future staff and of the organisation to operate the reactor safely, reliably and efficiently is an important issue. In this framework, many actions are in progress to elaborate: Ο the staffing and the organisational structure for the commissioning test phases and also for normal operation, Ο the documentation in support to the reactor operation (safety analysis report, general operating rules, procedures, instructions, ···), Ο the maintenance, in service and periodic test programs, Ο staff training programs by using dedicated facilities (simulator, ···) Ο commissioning test programs for ensuring that the layout of systems and subcomponents is completed in accordance with the design requirements, the specification performances and the safety criteria. These commissioning tests will also be helpful for transferring the knowledge on the installed systems to the operating group. This paper gives the

Scientific management of the commissioning of the Temelin NPP

International Nuclear Information System (INIS)

Pazdera, F.; Vasa, I.; Svoboda, C.

2002-01-01

A Scientific Supervisory Group (SSG) for the commissioning of the Temelin nuclear power plant was set up by the statutory body of CEZ, a.s. (utility which holds responsibility for the start-up of the plant pursuant to Act No. 18/1997). The SSG provides support to the operator through expertise in nuclear safety assurance and nuclear power plant commissioning. Nuclear Research Institute Rez plc was appointed to this function. The article gives the definition and explains the statute of the SSG, highlights its main tasks and responsibilities, and presents the main results of activities of the SSG. The mission of the International Scientific Council for the Commissioning of the Temelin NPP is also briefly outlined. (author)

Safety issues of nuclear production of hydrogen

International Nuclear Information System (INIS)

Piera, Mireia; Martinez-Val, Jose M.; Jose Montes, Ma

2006-01-01

Hydrogen is not an uncommon issue in Nuclear Safety analysis, particularly in relation to severe accidents. On the other hand, hydrogen is a household name in the chemical industry, particularly in oil refineries, and is also a well known chemical element currently produced by steam reforming of natural gas, and other methods (such as coal gasification). In the not-too-distant future, hydrogen will have to be produced (by chemical reduction of water) using renewable and nuclear energy sources. In particular, nuclear fission seems to offer the cheapest way to provide the primary energy in the medium-term. Safety principles are fundamental guidelines in the design, construction and operation both of hydrogen facilities and nuclear power plants. When these two technologies are integrated, a complete safety analysis must consider not only the safety practices of each industry, but any interaction that could be established between them. In particular, any accident involving a sudden energy release from one of the facilities can affect the other. Release of dangerous substances (chemicals, radiotoxic effluents) can also pose safety problems. Although nuclear-produced hydrogen facilities will need specific approaches and detailed analysis on their safety features, a preliminary approach is presented in this paper. No significant roadblocks are identified that could hamper the deployment of this new industry, but some of the hydrogen production methods will involve very demanding safety standards

EPR meeting international safety standards with margin

International Nuclear Information System (INIS)

Mazurkiewicz, S.M.; Brauns, J.; Blombach, J.

2005-01-01

The EPR provides technology that offers a solution to the market's need for safe, economic power. The EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product capable of international licensing. As such, the EPR is a global product with commercial units currently being built in Finland at the Olkiluoto site, and planned for France, at the Flamanville site. Framatome ANP has recently proposed four EPR units to China in response to a request for vendor bids. In addition, Framatome ANP has announced their intent to pursue design certification with the United States Nuclear Regulatory Commission (NRC). This paper discusses how EPR's innovative safety philosophy ensures compliance with international safety standards for advanced light-water reactors (ALWRs). (author)

EPR meeting international safety standards with margin

International Nuclear Information System (INIS)

Mazurkiewicz, S.M.; Brauns, J.; Blombach, J.

2005-01-01

The EPR provides technology that offers a solution to the market's need for safe, economic power. The EPR was originally developed through a joint effort between Framatome ANP and Siemens by incorporating the best technological features from the French and German nuclear reactor fleets into a cost-competitive product capable of international licensing. As such, the EPR is a global product with commercial units currently being built in Finland at the Olkiluoto site, and planned for France, at the Flamanville site. Framatome ANP has recently proposed four EPR units to China in response to a request for vendor bids. In addition, Framatome ANP has announced their intent to pursue design certification in with the United States Nuclear Regulatory Commission (NRC). This paper discusses how EPR's innovative safety philosophy ensures compliance with international safety standards for advanced light-water reactors (ALWRs). (author)

Indexes to Nuclear Regulatory Commission issuances, January 1, 1980--December 31, 1985

International Nuclear Information System (INIS)

1989-11-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

The extent and influence of Asbestos Safety Awareness training among managers who had previously commissioned an asbestos survey in their workplace buildings.

Science.gov (United States)

Hickey, Jane; Saunders, Jean; Davern, Peter

2015-01-01

A telephone survey was conducted among a sample of managers (n=30) in Ireland who had previously commissioned an asbestos survey in their workplace buildings. The aims of the telephone survey were to examine the extent to which managers had completed Asbestos Safety Awareness (ASA) training, and to assess how such training might influence (i) their instinctive thoughts on asbestos, and (ii) their approach to aspects of asbestos management within their buildings. Managers' motivations for commissioning the asbestos survey were also identified. The study found that ASA-trained managers (n=11) were not significantly more likely to work in larger organisations or in organisations which operated an accredited management system. Though ASA-trained managers' instinctive thoughts on asbestos were of a slightly poorer technical quality compared with those of non-ASA-trained managers, they were still significantly more cognisant of their responsibilities towards those of their employees at specific risk of asbestos exposure. Most managers (n=28) commissioned the asbestos survey to satisfy a pre-requisite of external contractors for commencing refurbishment/demolition work in their buildings. Given its potential to positively influence the occupational management of asbestos, the authors recommend the general promotion of suitably tailored ASA-training programmes among building managers and external contractors alike.

Barsebaeck power plant - safety and emergency measures

International Nuclear Information System (INIS)

Anon.

1981-01-01

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

Review of current status of LWR safety research in Japan

International Nuclear Information System (INIS)

Yamada, Tasaburo; Mishima, Yoshitsugu; Ando, Yoshio; Miyazono, Shohachiro; Takashima, Yoichi.

1977-01-01

The Japan Atomic Energy Commission has exerted efforts on the research of the safety of nuclear plants in Japan, and ''Nuclear plant safety research committees'' was established in August 1974, which is composed of the government and the people. The philosophy of safety research, research and development plan, the forwarding procedure of the plan, international cooperation, for example LOFT program, and the effective feed back of the experimental results concerning nuclear safety are reviewed in this paper at first. As for the safety of nuclear reactors the basic philosophy that radio active fission products are contained in fuel or reactors with multiple barriers, (defence in depth) and almost no fission product is released outside reactor plants even at the time of hypothetical accident, is kept, and the research and development history and the future plan are described in this paper with the related technical problems. The structural safety is also explained, for example, on the philosophy ''leak before break'', pipe rupture, pipe restraint and stress analysis. The release of radioactive gas and liquid is decreased as the philosophy ''ALAP''. And probability safety evaluation method, LOCA, reactivity, accident and aseismatic design in nuclear plants in Japan are described. (Nakai, Y.)

Quality and Safety Aspects of Cereals (Wheat) and Their Products.

Science.gov (United States)

Varzakas, Theo

2016-11-17

Cereals and, most specifically, wheat are described in this chapter highlighting on their safety and quality aspects. Moreover, wheat quality aspects are adequately addressed since they are used to characterize dough properties and baking quality. Determination of dough properties is also mentioned and pasta quality is also described in this chapter. Chemometrics-multivariate analysis is one of the analyses carried out. Regarding production weighing/mixing of flours, kneading, extruded wheat flours, and sodium chloride are important processing steps/raw materials used in the manufacturing of pastry products. Staling of cereal-based products is also taken into account. Finally, safety aspects of cereal-based products are well documented with special emphasis on mycotoxins, acrylamide, and near infrared methodology.

Course of atomic energy safety during ten years

International Nuclear Information System (INIS)

1988-10-01

The Nuclear Safety Commission started in the autumn of 1978 as the result of reexamining the system of atomic energy safety regulation in order to deal with the national criticism against the promotion of atomic energy that arose after the radiation leak accident on the nuclear ship 'Mutsu' 1974. For the development of atomic energy, it is indispensable to obtain the understanding and trust of nation on the safety of atomic energy as clearly shown in the Atomic Energy Act and in the background of founding and the policy of hte Nuclear Safety Commission. The Nuclear Safety Commission has carried out the safety examination for the permission of installing nuclear facilities, the decision of guidelines for the examination, the holding of public hearing, the promotion of safety research and so on. In this book, the reform of the system of atomic energy safety regulation, the countermeasures after TMI accident, the public hearing and others taking root, the further heightening of reliability of LMRs, efforts for operation managment and environment safety, the substantiating of the research on atomic energy safety, the diversification of the objects of safety regulation, the treatment and disposal of radioactive waste, the countermeasures after the chernobyl-4 accident and the positive promotion of international cooperation are described. (Kako, I.)

77 FR 8257 - Sunshine Act Open Commission Meeting

Science.gov (United States)

2012-02-14

... Safety and Title: The Proposed Extension of Part 4 Homeland Security. of the Commission's Rules Regarding Outage Reporting to Interconnected Voice Over Internet Protocol Service Providers and Broadband Internet... outage reporting under Part IV of the rules to interconnected Voice over Internet Protocol (VoIP) service...

Regulatory view on licensing and commissioning of Temelin NPP

International Nuclear Information System (INIS)

Drabova, D.; Boehm, K.; Brandejs, P.; Tipek, Z.

2004-01-01

The competencies delegated to the Czech State Office for Nuclear Safety by Czech legislation are highlighted and the history of construction and commissioning of the Temelin nuclear power plant in relation to the licensing process is described. (P.A.)

75 FR 73946 - Worker Safety and Health Program: Safety Conscious Work Environment

Science.gov (United States)

2010-11-30

... Environment AGENCY: Office of the General Counsel, Department of Energy (DOE). ACTION: Notice of denial of... Nuclear Regulatory Commission's ``Safety-Conscious Work Environment'' guidelines as a model. DOE published.... Second, not only would instituting a ``Safety-Conscious Work Environment'' by regulation be redundant...

United State Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board, and Licensing Board decisions, July 1972--June 1988

International Nuclear Information System (INIS)

1989-04-01

This fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to June 30, 1988 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This edition replaces in their entirety earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through June 30, 1988

Screening-Level Safety Assessment of Personal Care Product Constituents Using Publicly Available Data

Directory of Open Access Journals (Sweden)

Ernest S. Fung

2018-06-01

Full Text Available Organizations recommend evaluating individual ingredients when assessing the safety of personal care or cosmetic products. The goal of this study was to present a screening-level safety assessment methodology to evaluate the safety of a product by identifying individual ingredients, determining their frequency of use in on-market products, and examining published safe-level-of-use information for each ingredient. As a case study, we evaluated WEN by Chaz Dean (WCD cleansing conditioners since there have been claims of adverse health effects associated with product use. We evaluated 30 ingredients in three on-market WCD cleansing conditioners. We then analyzed the National Library of Medicine’s Household Products Database and the Environmental Working Group’s (EWG Skin Deep Cosmetic Database, two of the largest publicly available databases, for other on-market personal care and cosmetic products that contained these ingredients. Safe-level-of-use information for each ingredient was obtained by reviewing peer-reviewed literature, the Food and Drug Administration’s (FDA generally recognized as safe (GRAS database, available Cosmetic Ingredient Review (CIR publications, and available product safety publications. The results of this analysis showed that more than 20,000 personal care and cosmetic products contained one or more of the evaluated ingredients used in WCD cleaning conditioners. Published safety information was available for 21 of the 30 evaluated ingredients: seven identified ingredients were designated as GRAS by the FDA and 16 ingredients had safe-level-of-use information available from the CIR. This study presents a screening-level safety assessment methodology that can serve as an initial screening tool to evaluate the safety of an ingredient intended for use in personal care and cosmetic products before a product is launched onto the market. This study provides evidence that the evaluated WCD cleansing conditioner ingredients

MANAGING PRODUCT SAFETY SYSTEM HACCP ON THE EXAMPLE OF BEET-SUGAR PRODUCTION

Directory of Open Access Journals (Sweden)

V. A. Golybin

2015-01-01

Full Text Available The most effective safety management system of food production in all industrialized countries in the world recognized by the system based on the principles of HACCP. In Russia, the conformity assessment carried out by the HACCP system certification. The essence of the HACCP system is to identify and control the critical points. Critical Control Point – this is the stage of the process, which is subject to control for hazard identification and risk management in order to avoid the production of unsafe products. Implementation of HACCP system allows to tighten and coordinate the quality control system, which will improve the competitiveness of the products produced in the sugar market in Russia and abroad. In the early stages of food production HACCP system to prevent the occurrence of danger. It is based on the preventive approach to ensuring quality and safety in the production process, and can also be used in the development of new products. HACCP system is based on seven main principles to ensure the implementation and management of the system in production. 1. Creation of a working group of the coordinator and the technical secretary and various consultants. 2. Information on materials and products, in this case of sugar beet and sugar. 3. Information about the production. 4. Risk analysis of the available chemical, physical and microbiological factors. To determine the critical control points according to the results obtained for each factor is determined by a special chart the extent of its accounting. The need to consider the potential hazard is determined by the order in which area it has got. 5. The production program of mandatory preliminary activities in the production of sugar. 6. Determination of critical control points. 7. Making worksheets HACCP. It is shown that the use of HACCP in sugar beet production has several advantages.

Safety guidance and inspection program for particle accelerator

Energy Technology Data Exchange (ETDEWEB)

Lee, Do Whey [Korea Institute of Nuclear Safety, Taejon (Korea, Republic of); Lee, Hee Seock; Yeo, In Whan [Pohang Accelerator Laboratory, Pohang (Korea, Republic of)] (and others)

2001-03-15

The inspection program and the safety guidance were developed to enhance the radiation protection for the use of particle accelerators. First the classification of particle accelerators was conducted to develop the safety inspection protocol efficiently. The status of particle accelerators which were operated at the inside and outside of the country, and their safety programs were surveyed. The characteristics of radiation production was researched for each type of particle accelerators. Two research teams were launched for industrial and research accelerators and for medical accelerators, respectively. In each stages of a design, a fabrication, an installation, a commissioning, and normal operation of accelerators, those safety inspection protocols were developed. Because all protocols resulted from employing safety experts, doing the questionnaire, and direct facility surveys, it can be applicable to present safety problem directly. The detail improvement concepts were proposed to revise the domestic safety rule. This results might also be useful as a practical guidance for the radiation safety officer of an accelerator facility, and as the detail standard for the governmental inspection authorities.

White paper on nuclear safety in 2004

International Nuclear Information System (INIS)

2005-05-01

The white paper consists of four parts. The first part described the regulation of nuclear facility decommissioning and the clearance level at which the decommissioned waste materials are not necessarily treated as radioactive materials. The second part explained the main operations of the nuclear safety regulation of the Nuclear Safety Commission and the regulatory bodies in 2004 and Mihama unit 3 accident. The third part introduced various activities for the general preservation of nuclear safety in Japan, such as safety regulation systems for nuclear facilities, disaster preparedness of nuclear facilities, progress in nuclear research, environmental radiation surveys and international cooperation on nuclear safety. The forth part contained various materials and data related to the Nuclear Safety Commission. (J.P.N.)

Study on the Problems and Countermeasure in the Animal Products Quality and Safety

Institute of Scientific and Technical Information of China (English)

Shishan; WANG

2013-01-01

As the supply chain of animal products is long,there are many factors which would influence the quality safety of animal production.Therefore,by focusing on the present and having a vision for future,Jiaozuo government promulgated Ten Polices on the Food Safety in Jiaozuo City,which pushed forward the technological development,intensified measures to monitor the quality of animal products,set up a series of mechanism,and provided reference for the food quality and safety monitoring.

2008 annual site restoration report of the BC Oil and Gas Commission

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-15

Oil and gas operators in British Columbia are responsible for all issues related to the surface reclamation of a site, including the management of contaminated sites. They require a certificate of restoration (CoR) for lands no longer required in the extraction of hydrocarbons. The CoR program ensures that the land used for oil and development is restored to a safe and productive state. The restoration process promotes the timely recovery of wellsite and facility locations and helps in managing environmental impacts. The BC Oil and Gas Commission oversees the restoration process by oil and gas operators through the application of regulations, compliance and enforcement. The Commission balances a broad range of environmental, economic and social considerations. Among its specific objectives are public safety, conservation of petroleum resources, promoting a healthy environment, and equitable participation in production. This report included a review of performance measures that have been developed to evaluate restoration programs, including well plugging. Site reclamation requirements for lands within the Agricultural Land Reserve (ALR) were also described along with orphan site reclamation activities. A CoR is issued after a permit holder demonstrates that the remediation criteria have been met. There are currently 3,814 sites that have received a CoR in the province. refs., tabs., figs.

A proposal for safety design philosophy of HTGR for coupling hydrogen production plant

International Nuclear Information System (INIS)

Sato, Hiroyuki; Ohashi, Hirofumi; Tazawa, Yujiro; Imai, Yoshiyuki; Nakagawa, Shigeaki; Tachibana, Yukio; Kunitomi, Kazuhiko

2013-06-01

Japan Atomic Energy Agency (JAEA) has been conducting research and development for hydrogen production utilizing heat from High Temperature Gas-cooled Reactors (HTGRs). Towards the realization of nuclear hydrogen production, coupled hydrogen production plants should not be treated as an extension of a nuclear plant in order to open the door for the entry of non-nuclear industries as well as assuring reactor safety against postulated abnormal events initiated in the hydrogen production plants. Since hydrogen production plant utilizing nuclear heat has never been built in the world, little attention has been given to the establishment of a safety design for such system including the High Temperature engineering Test Reactor (HTTR). In the present study, requirements in order to design, construct and operate hydrogen production plants under conventional chemical plant standards are identified. In addition, design considerations for safety design of nuclear facility are suggested. Furthermore, feasibility of proposed safety design and design considerations are evaluated. (author)

Design, production and first commissioning results of the electrical feedboxes of the LHC

International Nuclear Information System (INIS)

Perin, A.; Atieh, S.; Benda, V.; Bertarelli, A.; Bouillot, A.; CERN; Brodzinski, K.; Wroclaw Tech. U.; Folch, R.; CERN; Fydrych, J.; Wroclaw Tech. U.; Genet, M.; Koczorowski, S.; Metral, L.; CERN; Serpukhov, IHEP; Fermilab; CERN; Serpukhov, IHEP; CERN; Serpukhov, IHEP

2007-01-01

A total of 44 CERN designed cryogenic electrical feedboxes are needed to power the LHC superconducting magnets. The feedboxes include more than 1000 superconducting circuits fed by high temperature superconductor and conventional current leads ranging from 120 A to 13 kA. In addition to providing the electrical current to the superconducting circuits, they also ensure specific mechanical and cryogenic functions for the LHC. The paper focuses on the main design aspects and related production operations and gives an overview of specific technologies employed. Results of the commissioning of the feedboxes of the first LHC sectors are presented

Construction and commissioning experience of evolutionary water cooled nuclear power plants

International Nuclear Information System (INIS)

2004-04-01

Electricity market liberalization is an established fact in several countries and there is a trend to adopt it in other countries. The essential aim of market liberalization is to improve the overall economic efficiency. In order that nuclear power remains a viable option for electricity generation, its costs should be competitive with alternative sources while, at the same time, it should have a safe and reliable operation record. The capital cost of nuclear power plants (NPPs) generally accounts for 43-70% of the total nuclear electricity generation costs, compared to 26-48% for coal plants and 13-32% for gas plants. Most of these expenditures are incurred during the construction phase of a NPP. The achievement of shorter construction periods using improved technology and construction methods has a significant benefit on the costs incurred prior to any production of electricity. This document is intended to make the recent worldwide experience on construction and commissioning of evolutionary water cooled NPPs available to Member States and especially to those with nuclear power plants under construction/planning, and to those seriously considering nuclear power projects in the future. The final aim is to assist utilities and other organizations in Member States to improve the construction of nuclear power plants and achieve shortened schedules and reduced costs without compromising quality and safety. This document aims to provide an overview of the most advanced technologies, methods and processes used in construction and commissioning of recent nuclear projects. To better achieve this objective the presentation is selectively focused more on the new developments rather than providing a full review of all issues related to construction and commissioning. The experience described in this TECDOC applies to managers, engineers, supervisors, technicians and workers in various organizations dealing with the site construction and commissioning of nuclear power plants

16 CFR 1115.1 - Purpose.

Science.gov (United States)

2010-01-01

... Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SUBSTANTIAL PRODUCT HAZARD REPORTS General Interpretation § 1115.1 Purpose. The purpose of this part 1115 is to set forth the Consumer Product Safety Commission's (Commission's) interpretation of the reporting requirements imposed on...

MANAGEMENT OF QUALITY AND SAFETY OF FOOD PRODUCTS OF ANIMAL ORIGIN

Directory of Open Access Journals (Sweden)

Goryana Yonkova

2016-12-01

Full Text Available Bulgaria is famous not only in Europe but throughout the world, except for its rich natural and cultural heritage, but also traditional dairy products (yogurt and cheese - cow, sheep, buffalo and goats; yellow cheese, honey and bee products, rose oil. To be competitive on national and international markets, food production must meet the requirements for quality assurance and food safety. The article presents the key economic indicators and threats related to quality management and safety of food products of animal origin in relation to the conservation of components of the environment and human health.

Off-site emergency preparedness activities within the European Commission

International Nuclear Information System (INIS)

Kelly, G.N.

1998-01-01

Increasing attention is being given by the European Commission to off-site emergency preparedness as part of its broader contribution to improving nuclear safety in Eastern Europe. The main initiatives being taken or planned by the Commission in this area are summarised. Particular attention is given to two topics: Firstly, the development of the RODOS (Real-time On-line DecisiOn Support) system for supporting off-site emergency management in the event of a nuclear accident; and, secondly, the work of an Inter-Service Group on nuclear Off-Site Emergency Preparedness (OSEP) in Eastern Europe that has been established within the Commission. The contribution that each is making to improving emergency preparedness, both in Eastern Europe and in Europe more widely, is described. (orig.)

European commission contribution to improving off-site emergency preparedness

International Nuclear Information System (INIS)

Kelly, G.N.

1996-01-01

Increasing attention is being given by the European Commission to off-site emergency preparedness as part of its broader contribution to improving nuclear safety in Eastern Europe. The main initiatives being taken or planned by the Commission in this area are summarized. Particular attention is given to two topics: firstly, the development of the RODOS (Real-time On-line Decision Support) system for supporting off-site emergency management in the event of a nuclear accident; and, secondly, the work of an Inter-Service Group on nuclear Off-Site Emergency Preparedness (OSEP) in Eastern Europe that has recently been established within the Commission. The contribution that each is making to improving emergency preparedness, both in Eastern Europe and in Europe more widely, is described

Using resources for scientific-driven pharmacovigilance: from many product safety documents to one product safety master file.

Science.gov (United States)

Furlan, Giovanni

2012-08-01

Current regulations require a description of the overall safety profile or the specific risks of a drug in multiple documents such as the Periodic and Development Safety Update Reports, Risk Management Plans (RMPs) and Signal Detection Reports. In a resource-constrained world, the need for preparing multiple documents reporting the same information results in shifting the focus from a thorough scientific and medical evaluation of the available data to maintaining compliance with regulatory timelines. Since the aim of drug safety is to understand and characterize product issues to take adequate risk minimization measures rather than to comply with bureaucratic requirements, there is the need to avoid redundancy. In order to identify core drug safety activities that need to be undertaken to protect patient safety and reduce the number of documents reporting the results of these activities, the author has reviewed the main topics included in the drug safety guidelines and templates. The topics and sources that need to be taken into account in the main regulatory documents have been found to greatly overlap and, in the future, as a result of the new Periodic Safety Update Report structure and requirements, in the author's opinion this overlap is likely to further increase. Many of the identified inter-document differences seemed to be substantially formal. The Development Safety Update Report, for example, requires separate presentation of the safety issues emerging from different sources followed by an overall evaluation of each safety issue. The RMP, instead, requires a detailed description of the safety issues without separate presentation of the evidence derived from each source. To some extent, however, the individual documents require an in-depth analysis of different aspects; the RMP, for example, requires an epidemiological description of the indication for which the drug is used and its risks. At the time of writing this article, this is not specifically

Nitric Acid Revamp and Upgrading of the Alarm & Protection Safety System at Petrokemija, Croatia

Directory of Open Access Journals (Sweden)

Hoško, I.

2012-04-01

Full Text Available Every industrial production, particularly chemical processing, demands special attention in conducting the technological process with regard to the security requirements. For this reason, production processes should be continuously monitored by means of control and alarm safety instrumented systems. In the production of nitric acid at Petrokemija d. d., the original alarm safety system was designed as a combination of an electrical relay safety system and transistorized alarm module system. In order to increase safety requirements and modernize the technological process of nitric acid production, revamping and upgrading of the existing alarm safety system was initiated with a new microprocessor system. The newly derived alarm safety system, Simatic PCS 7, links the function of "classically" distributed control (DCS and logical systems in a common hardware and software platform with integrated engineering tools and operator interface to meet the minimum safety standards with safety integrity level 2 (SIL2 up to level 3 (SIL3, according to IEC 61508 and IEC 61511. This professional paper demonstrates the methodology of upgrading the logic of the alarm safety system in the production of nitric acid in the form of a logical diagram, which was the basis for a further step in its design and construction. Based on the mentioned logical diagram and defined security requirements, the project was implemented in three phases: analysis and testing, installation of the safety equipment and system, and commissioning. Developed also was a verification system of all safety conditions, which could be applied to other facilities for production of nitric acid. With the revamped and upgraded interlock alarm safety system, a new and improved safety boundary in the production of nitric acid was set, which created the foundation for further improvement of the production process in terms of improved analysis.

Indexes to Nuclear Regulatory Commission issuances, January--March 1996

International Nuclear Information System (INIS)

1996-01-01

This publication is the 1st quarter 1996 index to issuances by the US NRC. These include issuances by the Commission, the Atomic Safety and Licensing Board Panel, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking

16 CFR 1025.33 - Production of documents and things.

Science.gov (United States)

2010-01-01

... Section 1025.33 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION GENERAL RULES OF PRACTICE FOR... (including writings, drawings, graphs, charts, photographs, phono-records, and any other data compilation..., custody, or control of the party upon whom the request is served, or (2) To permit entry upon designated...

Indexes to Nuclear Regulatory Commission issuances, July--September 1997

International Nuclear Information System (INIS)

1998-01-01

This digest and index lists the Nuclear Regulatory Commission (NRC) issuances for July to September 1997. Issuances are from the Commission, the Atomic Safety and Licensing Boards, the Administrative Law Judges, the Directors' Decisions, and the Decisions on Petitions for Rulemaking. There are five sections to this index: (1) case name index, (2) headers and digests, (3) legal citations index, (4) subject index, and (5) facility index. The digest provides a brief narrative of the issue, including the resolution of the issue and any legal references used for resolution

Traffic legislation and safety in Europe concerning the moped and the A1 category (125 cc) motorcycle : a literature and questionnaire study commissioned by the Swedish National Road Administration

NARCIS (Netherlands)

Schoon, C.C.

2004-01-01

A study, commissioned by the Swedish National Road Administration, of the safety aspects of mopeds and the light motorcycle A1 category (max. 125 cc) has been carried out. The study consists of a comparison of European countries. An important part of the information was gathered using questionnaires

Implementation of safety goals in NRC's regulatory process

International Nuclear Information System (INIS)

Murley, T.E.

1985-01-01

In May 1983 the Nuclear Regulatory Commission issued a policy statement on Safety Goals For Nuclear Power Plant Operation. The Commission at the same time judged that a two-year evaluation period was necessary to judge the effectiveness of the goals and design objectives, and directed the staff to develop information and understanding as to how to further define and use the design objectives and the cost-benefit guidelines. In carrying out the Commission's mandate, the staff framed three major questions to be addressed during the safety goal evaluation period. These three questions are: 1) to what extent is it practical to use safety goals in the regulatory process. 2) Should the quantitative design objectives be modified or supplemented. If so, how. 3) How should the safety goals be implemented at the end of the evaluation period. The staff's conclusions are discussed

Safety and efficacy of personal care products containing colloidal oatmeal.

Science.gov (United States)

Criquet, Maryline; Roure, Romain; Dayan, Liliane; Nollent, Virginie; Bertin, Christiane

2012-01-01

Colloidal oatmeal is a natural ingredient used in the formulation of a range of personal care products for relief of skin dryness and itchiness. It is also used as an adjunctive product in atopic dermatitis. The safety of personal care products used on vulnerable skin is of particular importance and the risk of developing further skin irritations and/or allergies should be minimized. In a series of studies, we tested the safety of personal care products containing oatmeal (creams, cleansers, lotions) by assessing their irritant/allergenic potential on repeat insult patch testing, in safety-in-use and ocular studies using subjects with nonsensitive and sensitive skin. We also tested the skin moisturizing and repair properties of an oatmeal-containing skin care product for dry skin. We found that oatmeal-containing personal care products had very low irritant potential as well as a very low allergenic sensitization potential. Low-level reactions were documented in 1.0% of subjects during the induction phase of repeat insult patch testing; one of 2291 subjects developed a persistent but doubtful low-level reaction involving edema during the challenge phase in repeat insult patch testing. No allergies were reported by 80 subjects after patch testing after in-use application. Sustained skin moisturizing was documented in subjects with dry skin that lasted up to 2 weeks after product discontinuation. Our results demonstrate that colloidal oatmeal is a safe and effective ingredient in personal care products. No allergies were reported by consumers of 445,820 products sold during a 3-year period.

United States Nuclear Regulatory Commission Staff Practice and Procedure Digest: Commission, Appeal Board and Licensing Board decisions, July 1972-December 1986

International Nuclear Information System (INIS)

1987-11-01

This Revision 6 of the fourth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1986, interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 6 replaces in part earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through December 31, 1986

United States Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board and Licensing Board decisions, July 1972--December 1989

International Nuclear Information System (INIS)

1990-06-01

This Revision 6 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to December 31, 1989 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 6 replaces in part earlier editions and revisions and includes appropriate changes reflecting the amendments to the Rules of Practice effective through December 31, 1989

United States Nuclear Regulatory Commission Staff practice and procedure digest: Commission, Appeal Board and Licensing Board Decisions, July 1972-March 1987

International Nuclear Information System (INIS)

1987-12-01

This Revision 7 of the fourth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to March 31, 1987 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 7 replaces in part earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through March 31, 1987

United States Nuclear Regulatory Commission staff practice and procedure digest: Commission, Appeal Board and Licensing Board decisions, July 1972--September 1988

International Nuclear Information System (INIS)

1989-04-01

This Revision 1 of the fifth edition of the NRC Staff Practice and Procedure Digest contains a digest of a number of Commission, Atomic Safety and Licensing Appeal Board, and Atomic Safety and Licensing Board decisions issued during the period from July 1, 1972 to September 30, 1988 interpreting the NRC's Rules of Practice in 10 CFR Part 2. This Revision 1 replaces in part earlier editions and supplements and includes appropriate changes reflecting the amendments to the Rules of Practice effective through September 30, 1988

A Practical Guide for Commissioning Existing Buildings

Energy Technology Data Exchange (ETDEWEB)

Haasl, T.

1999-05-11

Although this guide focuses on the retrocommissioning process and its advantages, all three types of commissioning--retrocommissioning, commissioning, and recommissioning--play an equally important role in ensuring that buildings perform efficiently and provide comfortable, safe, and productive work environments for owners and occupants. For new construction and retrofit projects, commissioning should be incorporated early, during design, and last throughout the length of the project. For buildings that were never commissioned, the retrocommissioning process can yield a wealth of cost-saving opportunities while enhancing a building's environment. Finally, once a building is commissioned or retrocommissioned, incorporating recommissioning into the organization's O and M program (by periodically reapplying the original diagnostic testing and checklist procedures) helps ensure that cost savings and other benefits gained from the original process persist over time.

A Practical Guide for Commissioning Existing Buildings

Energy Technology Data Exchange (ETDEWEB)

Haasl, T.; Sharp, T.

1999-04-01

Although this guide focuses on the retrocommissioning process and its advantages, all three types of commissioning--retrocommissioning, commissioning, and recommissioning--play an equally important role in ensuring that buildings perform efficiently and provide comfortable, safe, and productive work environments for owners and occupants. For new construction and retrofit projects, commissioning should be incorporated early, during design, and last throughout the length of the project. For buildings that were never commissioned, the retrocommissioning process can yield a wealth of cost-saving opportunities while enhancing a building's environment. Finally, once a building is commissioned or retrocommissioned, incorporating recommissioning into the organization's O and M program (by periodically reapplying the original diagnostic testing and checklist procedures) helps ensure that cost savings and other benefits gained from the original process persist over time.

Indexes to Nuclear Regulatory Commission issuances, July--December 1988

International Nuclear Information System (INIS)

1989-04-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These information elements are displayed in one or more of five separate formats arranged as follows: case name index, digests and headers, legal citations index, subject index, and facility index

Indexes to Nuclear Regulatory Commission issuances, July--September 1988

International Nuclear Information System (INIS)

1989-01-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These information elements are displayed in one or more of five separate formats. These formats are case name index, digests and headers, legal citations index, subject index and facility index

Specific problems and practical experience of regulatory inspection during commissioning in the United Kingdom

International Nuclear Information System (INIS)

Lewis, G.

1977-01-01

The commissioning of nine Magnox and two Advanced Gas-cooled Reactor Nuclear Power Plants in the United Kingdom during the last sixteen years under the regulatory control of the Nuclear Installations Inspectorate of the Health and Safety Executive has been based on a Stage Approval Philosophy starting with proof-testing of the primary gas circuit and concluding with tests on the reactor at full power. The practical experience gained during this period has enabled the Nuclear Installations Inspectorate to rationalise the procedures and test requirements without comporomising safety standards. The Operating Rules and Maintenance Schedules are approved for commissioning and during this period are reviewed for their adequacy for future power operation of the plant. The organisation, documentation, test procedures and the commissioning programme used for the Advanced Gas-cooled Reactors are briefly explained. (author)

Safety analysis of an irradiation device for 99Mo production in RA-3 reactor

International Nuclear Information System (INIS)

Lerner, Ana Maria; Madariaga, Marcelo; Waldman, Ricardo

2000-01-01

The Argentine RA-3 research reactor (5 MW) has been converted to LEU fuel more than nine years ago. Since then, it has been operating with LEU fuel, which has been designed and fabricated at the National Atomic Energy Commission (CNEA). The Nuclear Regulatory Authority (ARN) is the institution in charge of the installation safety control. It is under this framework that the ARN has elaborated a neutronic calculation model for the RA-3 core, paying special attention to the device presently used for the irradiation of (HEU) 235 U targets required to obtain 9 '9Mo as a fission product. A regulatory analysis of results is carried out in the framework of ARN standards for fixed experiments. For such purpose, calculated reactivity values associated with such device are compared with recently measured values at the installation. Finally, and according to guidelines established in the first part of this work, a calculation model for a new device proposed by CNEA for the irradiation of metallic (LEU) uranium targets and still at its design stage, is here analysed. (author)

Commissioning of indigenous microwave test facility for development and pilot production of 2 MW S-band magnetrons

International Nuclear Information System (INIS)

Shrivastava, Purushottam; Wanmode, Y.D.; Hannurkar, P.R.; Prasad, Sharda

2005-01-01

To have self reliance in the field of microwave devices and to have consistent supply of pulsed magnetrons for the Indian accelerator programme. CAT initiated development of 2 MW S-Band pulsed magnetrons in collaboration with CEERI, Pilani. The design, development and testing of the microwave test facilities for ageing. conditioning and performance testing of Indian magnetrons, was successfully done by CAT indigenously. After the rigorous testing. the test facility was shifted, installed and commissioned at CEERI, Pilani by CAT. Over a period of 10 years, nine prototypes were aged and tested, two magnetrons were life tested and five magnetrons under production programme have been successfully conditioned and tested. Testing of more numbers is underway. The system details. commissioning aspects are discussed, results are shown. (author)

An emergent proposal on the Committee of Uranium Processing Factory Criticality Accident Survey of the Nuclear Safety Commission. A meantime report dated on November 5, 1999

International Nuclear Information System (INIS)

2000-01-01

The Nuclear Safety Commission was received a decision on thorough investigations of accident reason on criticality accident at the Tokai-mura uranium processing factory of the JCO Incorporation occurred on September 30, 1999, to establish the Committee of Uranium Processing Factory Criticality Accident Survey to elucidate its reason thoroughly and contribute to set up a sufficient reforming prevention countermeasure. This Committee judged that it was important to propose a countermeasure directly obtainable by grasping some fact relations clarified before now as soon as possible and intended to conduct this meantime report of 'emergent proposal' by arrangement of such fact relations. Here were described on accidental conditions and their effects, response to the accident (on prevention of the accident), its reasons and their relating conditions, and some emergent proposals. In the last items, safety security at accidental site, health countermeasures to residents and others, establishment of safety security for nuclear business workers and others, and reconstruction on safety regulation in national government. (G.K.)

Indexes to Nuclear Regulatory Commission issuances, July-December 1985. Volume 22, Index 2

International Nuclear Information System (INIS)

1986-03-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document

76 FR 15340 - In the Matter of Certain GPS Devices and Products Containing Same; Notice of Commission...

Science.gov (United States)

2011-03-21

... INTERNATIONAL TRADE COMMISSION [Inv. No. 337-TA-602] In the Matter of Certain GPS Devices and... importation, or the sale within the United States after importation of certain GPS devices and products... Determination in all respects. See SiRF Tech., Inc. v. Int'l Trade Comm'n, 601 F.3d 1319 (Fed. Cir. 2010). On...

The LHC from commissioning to operation

CERN Document Server

Lamont, M

2011-01-01

In 2011 the LHC moved from commissioning into the physics production phase with the aim of accumulating 1 fb-1 by the end of the year. The progress from commissioning to operation is described. Emphasis is put on the beam performance, but also on the performance of the different hardware systems. The role of collimation and machine protection is discussed, in view of the very high stored beam and magnet energy.

Refurbishment and safety upgradation of research reactor Cirus

International Nuclear Information System (INIS)

Marik, S.K.; Rao, D.V.H.; Bhatnagar, A.; Pant, R.C.; Tikku, A.C.; Sankar, S.

2006-01-01

Cirus, a 40 MW t, vertical tank type research reactor, having wide range of research facilities, was commissioned in the year 1960. This research reactor, situated at Mumbai, India has been operated and utilized extensively for isotope production, material testing and neutron beam research for nearly four decades. With a view to assess the residual life of the reactor, detailed ageing studies were carried out during the early 1990s. Based on these studies, refurbishment of Cirus for its life extension was taken up. During refurbishment, additional safety features were incorporated in various systems to qualify them for the current safety standards. This paper gives the details of the operating experiences, utilization of the reactor along with methodologies followed for carrying out detailed ageing studies, refurbishment and safety upgradation for its life extension

Indexes to Nuclear Regulatory Commission issuances, July-September 1981. Index 1

International Nuclear Information System (INIS)

1981-01-01

Digests and indexes for issuances of the Commission (CLI), the Atomic Safety and Licensing Appeal Panel (ALAB), the Atomic Safety and Licensing Board Panel (LBP), the Administrative Law Judge (ALJ), the Directors' Decisions (DD), and the Denials of Petitions of Rulemaking are presented in this document. These digests and indexes are intended to serve as a guide to the issuances

Overview of the Nuclear Regulatory Commission's safety research program

International Nuclear Information System (INIS)

Beckjord, E.S.

1989-01-01

Accomplishments during 1988 of the Office of Nuclear Regulatory Research and the program of safety research are highlighted, and plans, expections, and needs of the next year and beyond are discussed. Topics discussed include: ECCS Appendix K Revision; pressurized thermal shock; NUREG-1150, or the PRA method performance document; resolution of station blackout; severe accident integration plan; nuclear safety research review committee; and program management

European vehicle passive safety network

NARCIS (Netherlands)

Wismans, J.S.H.M.; Janssen, E.G.

1999-01-01

The general objective of the European Vehicle Passive Safety Network is to contribute to the reduction of the number of road traffic victims in Europe by passive safety measures. The aim of the road safety policy of the European Commission is to reduce the annual total of fatalities to 18000 in

The reorganisation of the French Atomic Energy Commission

International Nuclear Information System (INIS)

Glaize, G.

1977-01-01

The Atomic Energy Commission (CEA) has somewhat distinctive features when compared to other French public administrations. The Commission had been designed, when created in 1945, as a body very close to the Head of Government with, at the same time, great freedom of action; these two aspects demonstrated the importance accorded to its duties and the desire to assure its efficiency. The evolution of the Commission subsequently resulted in reducing these differences and strengthening the ministerial supervision as well as the role of the Administrator-General as compared with that of the High Commissioner. In the 1970s the Commission's structures developed in another direction, in view of the reorientation of its duties in the perspective of the development of the private nuclear sector and the increasing importance of nuclear safety questions. This reorganisation resulted in the creation of fairly autonomous operational units and a number of subsidiary bodies and specialised institutes. The outcome of this exercise has been to give the CEA a very diversified structure which is not as centralised as previously. (NEA) [fr

IT safety in production data networks (PDN). Tracking, evaluation and elimination of safety threats; IT-Sicherheit in Produktionsnetzen (PDN). Aufspueren, einschaetzen und beseitigen von Sicherheitsbedrohungen

Energy Technology Data Exchange (ETDEWEB)

Neider, Ulrich [DETACK GmbH, Ludwigsburg (Germany)

2013-03-01

This contribution reports on the threats of production data networks. Within the context of the IT security, the risks of production data networks are not only based on a possible contamination by computer viruses. The author of this contribution increases awareness of dangers to whose production systems are faced. The author also presents a phase model from his own consulting practice in order to increase the safety of production data systems by implementation of a safety control. This phase model consists of the six following steps: (a) Stock taking of the state of the art; (b) Determination of the target (development of a safety concept); (c) Creation of an IT safety policy; (d) Application of IT safety policy; (e) Audit of the results (IT safety audit); (f) Regular safety tests.

The use of non-animal alternatives in the safety evaluations of cosmetics ingredients by the Scientific Committee on Consumer Safety (SCCS).

Science.gov (United States)

Vinardell, M P

2015-03-01

In Europe, the safety evaluation of cosmetics is based on the safety evaluation of each individual ingredient. Article 3 of the Cosmetics Regulation specifies that a cosmetic product made available on the market is to be safe for human health when used normally or under reasonably foreseeable conditions. For substances that cause some concern with respect to human health (e.g., colourants, preservatives, UV-filters), safety is evaluated at the Commission level by a scientific committee, presently called the Scientific Committee on Consumer Safety (SCCS). According to the Cosmetics Regulations, in the EU, the marketing of cosmetics products and their ingredients that have been tested on animals for most of their human health effects, including acute toxicity, is prohibited. Nevertheless, any study dating from before this prohibition took effect is accepted for the safety assessment of cosmetics ingredients. The in vitro methods reported in the dossiers submitted to the SCCS are here evaluated from the published reports issued by the scientific committee of the Directorate General of Health and Consumers (DG SANCO); responsible for the safety of cosmetics ingredients. The number of studies submitted to the SCCS that do not involve animals is still low and in general the safety of cosmetics ingredients is based on in vivo studies performed before the prohibition. Copyright © 2014 Elsevier Inc. All rights reserved.

Safety and risk assessment of ceramide 3 in cosmetic products.

Science.gov (United States)

Choi, Seul Min; Lee, Byung-Mu

2015-10-01

Ceramide 3 is used mainly as a moisturizer in various cosmetic products. Although several safety studies on formulations containing pseudo-ceramide or ceramide have been conducted at the preclinical and clinical levels for regulatory approval, no studies have evaluated the systemic toxicity of ceramide 3. To address this issue, we conducted a risk assessment and comprehensive toxicological review of ceramide and pseudo-ceramide. We assumed that ceramide 3 is present in various personal and cosmetic products at concentrations of 0.5-10%. Based on previously reported exposure data, the margin of safety (MOS) was calculated for product type, use pattern, and ceramide 3 concentration. Lipsticks with up to 10% ceramide 3 (MOS = 4111) are considered safe, while shampoos containing 0.5% ceramide 3 (MOS = 148) are known to be safe. Reported MOS values for body lotion applied to the hands (1% ceramide 3) and back (5% ceramide 3) were 103 and 168, respectively. We anticipate that face cream would be safe up to a ceramide 3 concentration of 3% (MOS = 149). Collectively, the MOS approach indicated no safety concerns for cosmetic products containing less than 1% ceramide 3. Copyright © 2015 Elsevier Ltd. All rights reserved.

[Evaluation of the medical value of a drug. A necessity for the Transparency Commission].

Science.gov (United States)

Avouac, B

1992-01-01

The marketing approval (AMM) is based on criteria of pharmaceutical quality, efficacy and safety of use. Before marketing, the data are collected by means of double-blind, randomized, prospective clinical trials that compare the study product to a reference product. A post-AMM assessment is needed to define the increase of the medical benefit (ASMR) and the therapeutic value of the new drugs. The quantification of the ASMR is essential for registration on the list of drugs reimbursable for those who benefit from Social Security. The evaluation of the therapeutic value and the nature of the affection treated are the criteria upon which the reimbursement ratio is chosen. After marketing, the reevaluation of the medical benefit and the drugs' usefulness may be compared to the treatment's net medical cost (direct + indirect cost--avoided cost) in cost/utility or cost/benefit studies. The Transparency Commission has worked out a scale of assessment of the ASMR which will orient recommendation, or non-recommendation, of registration on the list of reimbursable drugs as well as price fixing proposals. In the future, the Transparency Commission is to strengthen its position regarding the good use of the drug through a better prescriber information system. Thanks to the pharmaco-epidemiology and the pharmaco-vigilance data, the Transparency Commission will be able to guarantee the post-marketing follow-up of the drugs. The examination of the products' conditions of use, the reevaluation of the treatment's advantages based on the utility studies and the epidemiological surveys, and the cost-benefit studies will contribute to a medical control of health spending linked to drug consumption.

Nuclear Regulatory Commission issuances, March 1995. Volume 41, No. 3

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-06-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

Nuclear Regulatory Commission issuances, May 1995. Volume 41, No. 5

International Nuclear Information System (INIS)

1995-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, March 1995. Volume 41, No. 3

International Nuclear Information System (INIS)

1995-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, May 1995. Volume 41, No. 5

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-07-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

Nuclear Regulatory Commission issuances, April 1994. Volume 39, No. 4

Energy Technology Data Exchange (ETDEWEB)

1994-04-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

Nuclear Regulatory Commission issuances, December 1994. Volume 40, No. 6

Energy Technology Data Exchange (ETDEWEB)

NONE

1994-12-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM).

Nuclear Regulatory Commission issuances, September 1994. Volume 40, No. 3

International Nuclear Information System (INIS)

1994-01-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (AU), the Directors' Decisions (DD), and the Denials of Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, February 1996: Volume 43, No. 2

International Nuclear Information System (INIS)

1996-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM)

Nuclear Regulatory Commission issuances, February 1996: Volume 43, No. 2

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors` Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM).

The European space suit, a design for productivity and crew safety

Science.gov (United States)

Skoog, A. Ingemar; Berthier, S.; Ollivier, Y.

In order to fulfil the two major mission objectives, i.e. support planned and unplanned external servicing of the COLUMBUS FFL and support the HERMES vehicle for safety critical operations and emergencies, the European Space Suit System baseline configuration incorporates a number of design features, which shall enhance the productivity and the crew safety of EVA astronauts. The work in EVA is today - and will be for several years - a manual work. Consequently, to improve productivity, the first challenge is to design a suit enclosure which minimizes movement restrictions and crew fatigue. It is covered by the "ergonomic" aspect of the suit design. Furthermore, it is also necessary to help the EVA crewmember in his work, by giving him the right information at the right time. Many solutions exist in this field of Man-Machine Interface, from a very simple system, based on cuff check lists, up to advanced systems, including Head-Up Displays. The design concept for improved productivity encompasses following features: • easy donning/doffing thru rear entry, • suit ergonomy optimisation, • display of operational information in alpha-numerical and graphical from, and • voice processing for operations and safety critical information. Concerning crew safety the major design features are: • a lower R-factor for emergency EVA operations thru incressed suit pressure, • zero prebreath conditions for normal operations, • visual and voice processing of all safety critical functions, and • an autonomous life support system to permit unrestricted operations around HERMES and the CFFL. The paper analyses crew safety and productivity criteria and describes how these features are being built into the design of the European Space Suit System.

78 FR 4366 - Appeal Proceedings Before the Commission

Science.gov (United States)

2013-01-22

... significant adverse effect on competition, employment, investment, productivity, innovation, or the ability of... assessment is not required. Civil Justice Reform In accordance with Executive Order 12988, the Commission has...(a) and 3(b)(2) of the Order. National Environmental Policy Act The Commission has determined that...

Developments in safety and operations culture in BNFL's thorp reprocessing plant, Sellafield, Cumbria

International Nuclear Information System (INIS)

Kett, P.J.

2000-01-01

One of the best descriptions of Culture is 'how we do things around here'. In a stable organisation it is extremely difficult to change any type of culture, whether it is an operations, customer service or safety culture. To change culture one of two elements are essential. There must be either a significant external pressure felt by all in the organisation or a change in senior management, with authority to set a new direction for the organisation. BNFL had a unique opportunity through the commissioning and operation of the Thorp Reprocessing Plant at Sellafield to shape a new Safety and Operations Culture. Both the key elements for change were present. Thorp was a high profile flagship plant that had attracted multinational investment. It incorporated new technology. The workforce had volunteered to operate the plant. A strong senior management team was specially selected. The plant was being commissioned in an environment where there was significant opposition by 'anti nuclear' groups. It was essential to both BNFL and the wider international nuclear community that Thorp was commissioned and operated safely. A strong operating culture was developed with safety as the corner stone. The culture comprises three key components. Rigorous plant safety case and risk assessments before work commences and modifications to the plant occur; A high level of involvement by all levels of the workforce in both operations and safety matters; Strong supportive leadership which does not allow safety standards to be compromised and encourages open debate on how to improve. During commissioning and early operation of Thorp the robustness of the Safety and Operations Culture was demonstrated. On several occasions, despite intense commercial pressure, operations were halted until the situation was resolved both technically and procedurally. This paper describes how the Safety and Operations Culture was developed. The key factors for success include recruitment, team selection

Commission of the European Communities review of fast reactor activities, March 1981

Energy Technology Data Exchange (ETDEWEB)

Balz, W [Commission of the European Communities, Brussels (Belgium)

1981-05-01

The Commission of the European Communities continued its activities in the field of fast reactors development essentially in the frame of the Fast Reactor Coordinating Committee (FRCC) and by execution of a Reactor Programme at its Joint Research Center (JRC). The study was concerned with introducing fast reactors into European Community, elaboration of preliminary safety criteria and guidelines for typical fast reactor accidents; codes and standards; LMFBR safety, fuel, fuel cycle safety.

Commission of the European Communities review of fast reactor activities, March 1981

International Nuclear Information System (INIS)

Balz, W.

1981-01-01

The Commission of the European Communities continued its activities in the field of fast reactors development essentially in the frame of the Fast Reactor Coordinating Committee (FRCC) and by execution of a Reactor Programme at its Joint Research Center (JRC). The study was concerned with introducing fast reactors into European Community, elaboration of preliminary safety criteria and guidelines for typical fast reactor accidents; codes and standards; LMFBR safety, fuel, fuel cycle safety

47 CFR 95.1125 - RF safety.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 5 2010-10-01 2010-10-01 false RF safety. 95.1125 Section 95.1125 Telecommunication FEDERAL COMMUNICATIONS COMMISSION (CONTINUED) SAFETY AND SPECIAL RADIO SERVICES PERSONAL RADIO SERVICES Wireless Medical Telemetry Service (WMTS) General Provisions § 95.1125 RF safety. Portable devices...

Safety goals for nuclear power

International Nuclear Information System (INIS)

Fischhoff, B.

1984-02-01

The key policy question in managing hazardous technologies is often some variant of How safe is safe enough. The US Nuclear Regulatory Commission has recently broached this topic by adopting safety goals defining acceptable risk levels for nuclear power plants. These goals are analyzed here with a general theory of standard setting (Fischhoff, 1983) which asks: (1) Are standards an appropriate policy tool in this case. (2) Can the Commission's safety philosophy be defended. (3) Do the operational goals capture that philosophy. The anlaysis shows the safety goals proposal to be sophisticated in some respects, incomplete in others. More generally, it points to difficulties with the concept of acceptable risk and any attempt to build policy instruments around it. Although focused on the NRC's safety goals, the present analysis is a prototype of what can be learned by similarly detailed consideration of other standards, not only for nuclear power but also for other hazardous technologies, as well as for issues unrelated to safety

Microbiological safety cabinets, cytotoxic safety cabinets. Choice and use

International Nuclear Information System (INIS)

Balty, I.; Belhanini, B.; Clermont, H.; Cornu, J.C.; Jacquet, M.A.; Texte, J.C.

2003-01-01

Drawn up by a working group composed of prevention professionals, manufacturers and control bodies, this guide is intended to help those responsible for safety in laboratories choose and acquire materials responding to the intended protection objectives. It provides recommendations for the commissioning and control of these materials as well as for their use. After a description of the operational characteristics of safety cabinets, this guide looks at the important points to be taken into account when ordering, accepting and commissioning equipment adapted to precise needs. It also covers verification of correct operation and provides a number of common sense rules relative to precautions for use. Material cleaning and decontamination is described briefly on account of the very specialized character of this activity. Detailed information relative to this subject should be sought in the literature. (authors)

Safety considerations and countermeasures against fire and explosion at an HTGR-hydrogen production system. Proposal of safety design concept

International Nuclear Information System (INIS)

Nishihara, T.; Hada, K.; Shibata, T.; Shiozawa, S.

1996-01-01

Establishment of safety design concept and countermeasures against fire and explosion accidents is among key safety-related issues in an HTGR-hydrogen production system. We propose the different safety design concepts depending upon the origin of fire and explosion which may happen in the HTGR-hydrogen production plant. Against fire and explosion originated outside the reactor building (R/B), namely in the area of hydrogen production plant, the safety design concept is primarily to take a safe distance for preventing the damage on safety-related items or a proof wall if necessary. Because the hydrogen production plant is designed in the same safety level as a conventional chemical plant. The safe distance is proposed to limit an incident overpressure to 10 kPa so as not to suffer any damage on the items and to limit a wall-averaged temperature of concrete structures of the R/B to 175degC according to the current regulation. On the other hand, against a potential possibility of explosion originated inside the R/B, the safety design concept is to minimize the possibility of explosion low enough to assume no occurrence inside the R/B. That is, the measure is to exclude a simultaneous failure of a secondary helium piping and an endothermic chemical reactor. Furthermore, in severe accident condition in which the explosion may be postulated a priori, an incidental overpressure of explosion inside the reactor containment vessel (C/V) should be limited so as not to fail the C/V through restricting the amount of combustible gas ingress into the C/V by means of a combination of C/V isolation valve installed in the helium piping and emergency shut off valve in the process feed gas line. (author)

76 FR 23810 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response...

Science.gov (United States)

2011-04-28

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Emergency Response Interoperability Center Public Safety Advisory Committee Meeting AGENCY... Fullano, Associate Chief, Public Safety and Homeland Security Bureau, Federal Communications Commission...

Nuclear Regulatory Commission issuances. Volume 47, Number 2

International Nuclear Information System (INIS)

1998-02-01

This report includes the issuances received during the specified period from the Commission (CLI), the Atomic Safety and Licensing Boards (LBP), the Administrative Law Judges (ALJ), the Directors' Decisions (DD), and the Decisions on Petitions for Rulemaking (DPRM). They involve: 21st Century Technologies, Inc.; Hydro Resources, Inc.; Northeast Utilities; and Northern States Power Company

Uranium Production Safety Assessment Team. UPSAT. An international peer review service for uranium production facilities

International Nuclear Information System (INIS)

1996-01-01

The IAEA Uranium Production Safety Assessment Team (UPSAT) programme is designed to assist Member States to improve the safe operation of uranium production facilities. This programme facilitates the exchange of knowledge and experience between team members and industry personnel. An UPSAT mission is an international expert review, conducted outside of any regulatory framework. The programme is implemented in the spirit of voluntary co-operation to contribute to the enhancement of operational safety and practices where it is most effective, at the facility itself. An UPSAT review supplements other facility and regulatory efforts which may have the same objective

Proposal of resolution to create an inquiry commission on the french nuclear power plants reliability in case or earthquakes and on the safety, information and warning procedures in case of incidents

International Nuclear Information System (INIS)

2003-01-01

This short paper presents the reasons of the creation of parliamentary inquiry commission of 30 members, on the reliability of the nuclear power plants in France in case of earthquakes and on the safety, information and warning procedures in case of accidents. (A.L.B.)