Health (Radiation Safety) Act 1983 (Victoria) No. 9889 of 17 May 1983

International Nuclear Information System (INIS)

1983-01-01

This Act amends the Health Act 1958 by adding a new Section entitled ''Radiation Safety''. In addition to establishing guidelines for the registration and licensing of certain radiation apparatus and sealed radioactive sources, this new Section authorises the Governor in Council to make regulations concerning, inter alia, transport and disposal of radioactive substances and public health and safety. The Act also sets up a Radiation Advisory Committee and a Radiographers and Radiation Technologists Registration Board of Victoria and amends the Nuclear Activities (Prohibitions) Act 1983 in respect of certain licensing provisions. (NEA) [fr

76 FR 42683 - Establishment of a Team Under the National Construction Safety Team Act

Science.gov (United States)

2011-07-19

...-01] Establishment of a Team Under the National Construction Safety Team Act AGENCY: National..., announces the establishment of a National Construction Safety Team pursuant to the National Construction Safety Team Act. The Team was established to study the effects of the tornado that touched down in Joplin...

OCCUPATIONAL HEALTH AND SAFETY ACT NO.6331 AND TOXICOLOGY

OpenAIRE

AYAN, Burak

2018-01-01

Workers exposureto variety of hazardous chemicals related to the type of work carried out. Regulationsabout chemicals which may be unsafe for workers is regulated at theOccupational Health and Safety Act No.6331.In this review regulatory framework of occupational health and safety forchemicals are assessed in order for chemicals to be used properly andsafely. 

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

International Nuclear Information System (INIS)

1995-01-01

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

Enhancing operational nuclear safety

International Nuclear Information System (INIS)

Sengoku, Katsuhisa

2008-01-01

's safety standards and program which provides the safety objective following the 10 fundamental safety principles. The safety requirements defines the functional conditions required for safety and the safety guides provides user-friendly and up-to-date practical guidance representing good/best practices to fulfill the requirements. The IAEA provides safety review services and fields safety review teams upon request of member states for the regulatory, the International Regulatory Review Team (IRRT) and Operational Safety Review Team (OSART) and Peer Review of the Operational and Safety Performance Experience Review (PROSPER). The OSART programme's purpose is to assist member states in enhancing the operational safety of individual nuclear power plants and to promote the continuous development of operational safety within all member states by the dissemination of information on good practice. The OSART Mission Results (OSMIR) database contains the results from 73 OSART missions and 54 follow up visits from 1991 and its continually updated. The Asian Nuclear Safety Network (ANSN) was established to pool and share existing and new technical knowledge and practical experience to further improve the safety of nuclear installation in Asia. In summary, the enhancement of the GNSR is anchored in the recognition that all the states are in the same boat and the increasing importance of sharing and mutual learning, sharing knowledge and experience through regional and global networking. It requires joint and coordinated strategy by all states. The IAEA is willing and ready to support the GNSR through the establishment and application of safety standards, and safety review and advisory services and international instruments. (Author)

76 FR 31350 - Cruise Vessel Safety and Security Act of 2010, Available Technology

Science.gov (United States)

2011-05-31

... DEPARTMENT OF HOMELAND SECURITY Coast Guard [Docket No. USCG-2011-0357] Cruise Vessel Safety and Security Act of 2010, Available Technology AGENCY: Coast Guard, DHS. ACTION: Notice of request for comments... Security and Safety Act of 2010(CVSSA), specifically related to video recording and overboard detection...

48 CFR 52.250-3 - SAFETY Act Block Designation/Certification.

Science.gov (United States)

2010-10-01

... its terms if they plan to take advantage of SAFETY Act coverage for their technology(ies). (d) All... unlawful. (2) Causes harm, including financial harm, to a person, property, or entity, in the United States... Act certification of a technology class that the Department of Homeland Security (DHS) has determined...

The enhancement of Ignalina NPP in design and operational safety

International Nuclear Information System (INIS)

Negrivoda, G.

1999-01-01

Enhancement of Ignalina NPP design include: core design improvements; fuel channel integrity (multiple pressure tube rupture); improvements of shutdown systems; improvements of instrumentation and control devices; containment strength and tightness; design basis accident analysis; improvements of safety and support systems; seismic safety enhancement; Year 2000 project; cracks in pipes. Enhancement of operational safety includes: quality assurance; configuration management; safety management and safety culture; emergency operating procedures; training and full scope simulator; in-service inspection; fire protection and ageing monitoring and management

Some Subjects and Relations According to the Act about Safety at Work

OpenAIRE

Marino Đ. Učur

2015-01-01

Complex relations in the field of safety at work could not be present without the subjects which have a specific status and specific rights, obligations and responsibilities regulated by the Occupational Health and Safety Act. This paper deals with: employer’s designated employee for the implementation of occupational health and safety activities, employees’ elected representative for health and safety protection at work, occupational medicine specialist, occupational health and safety sp...

NPP Mochovce nuclear safety enhancement program

International Nuclear Information System (INIS)

Cech, J.; Baumester, P.

1997-01-01

Nuclear power plant Mochovce is currently under construction and an extensive nuclear safety enhancement programme is under way. The upgrading and modifications are based on IAEA documents and on those of the Nuclear Regulatory Authority of the Slovak Republic. Based on a contract concluded with Riskaudit from the CEC, safety examinations of the Mochovce design were performed. An extensive list of technical specifications of safety measures is given. (M.D.)

Methods and Effects of Safety Enhancement in Korean PSR

International Nuclear Information System (INIS)

Kim, Young Gab; Park, Jong Woon

2009-01-01

Periodic Safety Review (PSR) is a comprehensive study on a nuclear power plant safety, taking into account aspects such as operational history, ageing, safety analyses and advances in code and standards since the time of construction. In Korea, PSRs have been performed for 20 units and have been effectively used to obtain an overall view of actual plant safety to determine reasonable and practical modifications that should be made in order to obtain a higher level of safety approaching that of modern plants. Among many safety enhancements achieved from Korean PSRs, new safety analyses are the important methods to confirm plant safety by increasing safety margin for specific safety issues. Methods and effects of safety enhancements applied in Korean PSRs are reviewed in this paper in light of new safety analyses to obtain additional safety margins

Some Subjects and Relations According to the Act about Safety at Work

Directory of Open Access Journals (Sweden)

Marino Đ. Učur

2015-01-01

Full Text Available Complex relations in the field of safety at work could not be present without the subjects which have a specific status and specific rights, obligations and responsibilities regulated by the Occupational Health and Safety Act. This paper deals with: employer’s designated employee for the implementation of occupational health and safety activities, employees’ elected representative for health and safety protection at work, occupational medicine specialist, occupational health and safety specialist and the committee for safety at work in the relations of safety at work.

An analysis of the proposed Airline Competition Enhancement Act

OpenAIRE

Smith, Janice S.

1990-01-01

Approved for public release, distribution is unlimited This analysis examines problem issues in the passenger airline industry and determines how the proposed Airline Competition Enhancement Act would impact these issues. A summarization of the history of airline deregulation is followed by an assessment of the factors that are contributing to the call for re-regulation. From this assessment, recommendations for changes to the proposed Airline Competition Enhancement Act are made. Lieut...

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

Science.gov (United States)

2010-10-01

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

Research for enhancing reactor safety

International Nuclear Information System (INIS)

1989-05-01

Recent research for enhanced reactor safety covers extensive and numerous experiments and computed modelling activities designed to verify and to improve existing design requirements. The lectures presented at the meeting report GRS research results and the current status of reactor safety research in France. The GRS experts present results concerning expert systems and their perspectives in safety engineering, large-scale experiments and their significance in the development and verification of computer codes for thermohydraulic modelling of safety-related incidents, the advanced system code ATHLET for analysis of thermohydraulic processes of incidents, the analysis simulator which is a tool for fast evaluation of accident management measures, and investigations into event sequences and the required preventive emergency measures within the German Risk Study. (DG) [de

Occupational Safety and Health Act Handbook for Vocational and Technical Education Teachers.

Science.gov (United States)

Shashack, Willard F., Ed.

The purpose of the handbook is to assist the school shop teacher in participating in voluntary compliance with the standards and regulations of the Occupational Safety and Health Act of 1970. The first major section deals with general shop safety and how the shop teacher can use the checklist to control possible safety violations in his shop. The…

The Occupational Safety and Health Act: Its Goals and Its Achievements. Evaluative Studies Series.

Science.gov (United States)

Smith, Robert Stewart

The safety and health mandate of the Occupational Safety and Health Act of 1970 is examined in reference to its effectiveness in reducing injuries and its consistency with the goal of promoting general welfare. Chapter 1 describes the essential features of the act and its administration to date, and analyzes the mandate as revealed by legislative…

Study on safety educations against individual causal factors of unsafe acts and specification of target trainees

International Nuclear Information System (INIS)

Hirose, Ayako; Takeda, Daisuke

2016-01-01

Many accidents and incidents are caused by unsafe acts. It is important to reduce these unsafe acts for preventing the accidents. The countermeasures for each causal factor behind unsafe acts are needed, however, comparing with improvement of facilities, workers-oriented measures such as safety educations are not sufficient. Then the purposes of this study are as follows: 1) to investigate the individual factors which have great impact of unsafe acts and the existing safety educations which aim to mitigate the impact of these factors, 2) to specify the target trainees to perform these safety educations. To identify common factors that affect unsafe act significantly, a web survey was conducted to 500 workers who have regularly carried out accident prediction training (i.e. Kiken-Yochi training). They were asked the situation which they were apt to act unsafely by free description. As the result, the following three main factors were extracted: impatience, overconfidence, and bothersome. Also, it was found that there were few existing safety educations which aim to mitigate the impact of these factors except for overconfidence. To specify the target trainees to perform safety educations which aim to mitigate the impact of these three factors, another web survey was conducted to 200 personnel in charge of safety at the workplace. They were asked the features of workers who tended to act unsafely by age group. The relationship between the factor that need to mitigate and the trainee who need to receive the education were clarified from the survey. (author)

Proposed amendments to the Accord Acts to incorporate an offshore occupational health and safety regime

Energy Technology Data Exchange (ETDEWEB)

NONE

2010-04-15

The Canada Atlantic Accords signed in 1985 with Newfoundland and Labrador and in 1986 with Nova Scotia facilitate the orderly development of petroleum resources in Canada's Atlantic offshore area. These accords established the Canada-Newfoundland and Labrador Offshore Petroleum Board and the Canada-Nova Scotia Offshore Petroleum Board and made them responsible, on behalf of the federal government and the respective provincial government, for the joint management of petroleum resources in the offshore area. While the federal and provincial governments are responsible for establishing the regime for operational safety and occupational health and safety to be administered by the 2 boards, there is no division of responsibilities between the provincial occupational health and safety regime and the Accord Acts. There is agreement amongst governments that the accord acts should be amended to clarify responsibilities and vest sole authority for occupational health and safety in the accord acts. This document outlined the policy intent of the proposed amendments to the Accord Acts to ground an occupational health and safety regime for the east coast offshore areas in legislation. The document discussed legislation to be amended; governance; and provisions of the occupational health and safety regime. General matters such as the application of the policy, allocation of responsibility and interpretation were also discussed. The general duties of the operators were identified along with specific duties of operators; duties related to transportation; occupational health and safety policy; health and safety management system; codes of practice; notification of accidents; duties of employers; and occupational health and safety program. Compliance and enforcement provisions were also summarized.

16 CFR 1500.88 - Exemptions from lead limits under section 101 of the Consumer Product Safety Improvement Act for...

Science.gov (United States)

2010-01-01

... 101 of the Consumer Product Safety Improvement Act for certain electronic devices. 1500.88 Section... from lead limits under section 101 of the Consumer Product Safety Improvement Act for certain electronic devices. (a) The Consumer Product Safety Improvement Act (CPSIA) provides for specific lead limits...

The safety of osmotically acting cathartics in colonic cleansing

DEFF Research Database (Denmark)

Nyberg, Caroline; Hendel, J.; Nielsen, O.H.

2010-01-01

Efficient cleansing of the colon before a colonoscopy or a radiological examination is essential. The osmotically acting cathartics (those given the Anatomical Therapeutic Chemical code A06AD) currently used for this purpose comprise products based on three main substances: sodium phosphate...... hyperphosphatemia and irreversible kidney damage owing to acute phosphate nephropathy, have been reported after use of sodium-phosphate-based products. The aim of this Review is to provide an update on the potential safety issues related to the use of osmotically acting cathartics, especially disturbances of renal...

Overlapping Nuclear Safety Control Provisions of the Atomic Energy Act and Electric Utility Act

International Nuclear Information System (INIS)

Chang, Gun-Hyun; Kim, Sang-Won; Koh, Jae-Dong; Ahn, Hyung-Joon; Kim, Chang-Bum

2007-01-01

Before May 17, 2005, Korea's nuclear power plant (hereinafter referred to as 'NNP') regulation system was two-pronged. Every NPP system consists of primary or secondary system, and each type was respectively regulated by the Atomic Energy Act(hereinafter referred to as 'AEA') and the Electric Utility Act(hereinafter referred to as 'EUA'). This unusual regulatory regime gave rise to a number of problems with respect to operation and safety. For this reason, the Enforcement Regulation of AEA and applicable Notice were revised on May 17, 2005 to the effect that all regulation on NPPs subject to EUA was brought under the purview of AEA, except regulation on business license for nuclear power generation under Article 7 of EUA and approval of plan of works for setting up electric installations (hereinafter referred to as 'construction plan') (including approval of any changes; the same shall apply hereinafter) under Article 61 thereof. From the point of view of the Ministry of Science and Technology, the regulation of NPPs by a single law has enhanced their safety. However, the Ministry of Commerce, Industry and Energy retains regulatory authority regarding NPPs. It reviews and approves construction plans for secondary system pursuant to Article 61 of EUA and Article 28 of the Enforcement Regulation thereof. This situation arose because Article 28 of the Enforcement Regulation of EUA continues to provide for matters related with nuclear power. Therefore, continued control of NPPs under EUA ignores the relationship and respective nature of AEA and EUA. There is also possibility of violation of a superseding law. Even if said provision is not in violation of a superseding law, Article 28 of the Enforcement Regulation of EUA poses the possibility of overlapping regulation, which may violate the principle of prohibiting excessive regulation, one of the principles of the Korean Constitution. Assessment of the dual regulatory system for review of secondary system requires (i

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...

Perspective channel-type reactor with enhanced safety

International Nuclear Information System (INIS)

Adamov, E.O.; Grozdov, I.I.; Kuznetsov, S.P.; Petrov, A.A.; Rozhdestvensky, M.I.; Cherkashov, Yu.M.

1994-01-01

Following the search for new design solutions to develop within the framework of channel trends the reactor with enhanced safety the Research and Development Institute of Power Engineering has developed the design of the multiloop boiling water reactor (MKER). The MKER enhanced safety is attained when involving the inherent safety features, passive safety systems as well as the accident consequences confinement devices. The design realizes several advantages which are typical of the channel-type reactors, namely: The design desintegration simplifying the manufacture, control, equipment delivery and decreasing, versus the pressure vessel reactors, the accident effect if it proceeds in an explosive manner; small operating reactivity margin and fuel burnup increased due to continuous refuelling; fuel cycle flexibility allowing comparatively easily to adopt the reactor to the conjuncture of the country fuel balance; multiloop circuit of the main coolant which reduces the degree and effect of the accidents connected with the equipment and pipings rupture; monitoring of the channels and fuel assemblies leak-tightness. (orig.)

Physician attitudes towards pharmacological cognitive enhancement: safety concerns are paramount.

Directory of Open Access Journals (Sweden)

Opeyemi C Banjo

2010-12-01

Full Text Available The ethical dimensions of pharmacological cognitive enhancement have been widely discussed in academic circles and the popular media, but missing from the conversation have been the perspectives of physicians - key decision makers in the adoption of new technologies into medical practice. We queried primary care physicians in major urban centers in Canada and the United States with the aim of understanding their attitudes towards cognitive enhancement. Our primary hypothesis was that physicians would be more comfortable prescribing cognitive enhancers to older patients than to young adults. Physicians were presented with a hypothetical pharmaceutical cognitive enhancer that had been approved by the regulatory authorities for use in healthy adults, and was characterized as being safe, effective, and without significant adverse side effects. Respondents overwhelmingly reported increasing comfort with prescribing cognitive enhancers as the patient age increased from 25 to 65. When asked about their comfort with prescribing extant drugs that might be considered enhancements (sildenafil, modafinil, and methylphenidate or our hypothetical cognitive enhancer to a normal, healthy 40 year old, physicians were more comfortable prescribing sildenafil than any of the other three agents. When queried as to the reasons they answered as they did, the most prominent concerns physicians expressed were issues of safety that were not offset by the benefit afforded the individual, even in the face of explicit safety claims. Moreover, many physicians indicated that they viewed safety claims with considerable skepticism. It has become routine for safety to be raised and summarily dismissed as an issue in the debate over pharmacological cognitive enhancement; the observation that physicians were so skeptical in the face of explicit safety claims suggests that such a conclusion may be premature. Thus, physician attitudes suggest that greater weight be placed upon the

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...

New enhancements to SCALE for criticality safety analysis

International Nuclear Information System (INIS)

Hollenbach, D.F.; Bowman, S.M.; Petrie, L.M.; Parks, C.V.

1995-01-01

As the speed, available memory, and reliability of computer hardware increases and the cost decreases, the complexity and usability of computer software will increase, taking advantage of the new hardware capabilities. Computer programs today must be more flexible and user friendly than those of the past. Within available resources, the SCALE staff at Oak Ridge National Laboratory (ORNL) is committed to upgrading its computer codes to keep pace with the current level of technology. This paper examines recent additions and enhancements to the criticality safety analysis sections of the SCALE code package. These recent additions and enhancements made to SCALE can be divided into nine categories: (1) new analytical computer codes, (2) new cross-section libraries, (3) new criticality search sequences, (4) enhanced graphical capabilities, (5) additional KENO enhancements, (6) enhanced resonance processing capabilities, (7) enhanced material information processing capabilities, (8) portability of the SCALE code package, and (9) other minor enhancements, modifications, and corrections to SCALE. Each of these additions and enhancements to the criticality safety analysis capabilities of the SCALE code system are discussed below

76 FR 10362 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

Science.gov (United States)

2011-02-24

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal... Cybersecurity and Communications Reliability Public Safety and Homeland Security Bureau, Federal Communications...

77 FR 12054 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

Science.gov (United States)

2012-02-28

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal..., Associate Bureau Chief, Public Safety and Homeland Security Bureau, Federal Communications Commission, 445...

76 FR 54234 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

Science.gov (United States)

2011-08-31

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal.... Postal Service Mail to Jeffery Goldthorp, Associate Bureau Chief, Public Safety and Homeland Security...

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

Energy Technology Data Exchange (ETDEWEB)

NONE

2006-12-22

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

Experience gained in enhancing operational safety at ComEd's nuclear power plants

International Nuclear Information System (INIS)

Elias, D.

1997-01-01

The following aspects of experience gained in enhancing operational safety at Comed's nuclear power plants are discussed: nuclear safety policy; centralization/decentralization; typical nuclear operating organization; safety review boards; human performance enhancement; elements of effective nuclear oversight

75 FR 9899 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

Science.gov (United States)

2010-03-04

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council; Notice of Public Meeting... Analysis Division, Public Safety and Homeland Security Bureau, Federal Communications Commission, 445 12th...

Nuclear safety and control act, chapter 9: An Act to establish the Canadian Nuclear Safety Commission and to make consequential amendements to other Acts

International Nuclear Information System (INIS)

1997-01-01

The purpose of this Act is to provide for: the limitation, to a reasonable level and in a manner that is consistent with Canada's international obligations, of the risks to national security, the health and safety of persons and the environment that are associated with the development, production and use of nuclear energy and the production, possession and use of nuclear substances, prescribed equipment and prescribed information; and the implementation in Canada of measures to which Canada has agreed respecting international control of the development, production and use of nuclear energy, including the non-proliferation of nuclear weapons and nuclear explosive devices

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework. 1. ed.

International Nuclear Information System (INIS)

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

Australian Radiation Protection and Nuclear Safety Act 1998. Guide to the Australian radiation protection and nuclear safety licensing framework; 1. ed

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-03-01

The purpose of this guide is to provide information to Commonwealth entities who may require a license under the Australian Radiation Protection and Nuclear Safety (ARPANS) Act 1998 to enable them to posses, have control of, use, operate or dispose of radiation sources. The guide describes to which agencies and what activities require licensing. It also addresses general administrative and legal matters such as appeal procedures, ongoing licensing requirements, monitoring and compliance. Applicants are advised to consult the Australian Radiation Protection and Nuclear Safety Act 1998 and accompanying Regulations when submitting applications

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

Science.gov (United States)

2013-02-13

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

76 FR 64354 - Burden of Food and Drug Administration Food Safety Modernization Act Fee Amounts on Small...

Science.gov (United States)

2011-10-18

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2011-N-0529] Burden of Food and Drug Administration Food Safety Modernization Act Fee Amounts on Small Business... amounts on small business, as set forth in the FDA Food Safety Modernization Act (FSMA). In particular...

76 FR 45818 - Burden of Food and Drug Administration Food Safety Modernization Act Fee Amounts on Small...

Science.gov (United States)

2011-08-01

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Food and Drug Administration [Docket No. FDA-2011-N-0529] Burden of Food and Drug Administration Food Safety Modernization Act Fee Amounts on Small Business... burden of fee amounts on small business, as set forth in the FDA Food Safety Modernization Act (FSMA...

An examination of the Hazardous Materials Transportation Uniform Safety Act (HMTUSA): A southern perspective

International Nuclear Information System (INIS)

1992-03-01

On November 16,1990, President Bush signed into law the most comprehensive amendments to the Hazardous Materials Transportation Act (HMTA) in 15 years. The Hazardous Materials Transportation Uniform Safety Act of 1990 (HMTUSA) was created by Congress in an effort to strengthen and clarify the HMTA. This paper will discuss the act's provisions as they affect shipments of spent fuel and high-level radioactive materials as well as the impact of those provisions on routing and emergency response issues in the southern region. HMTUSA consists of seven key provisions that affect radioactive materials: clarification of regulatory jurisdiction; highway routing standards; broadened industry registration; safety permits for motor carriers of high risk materials; expanded nuclear transportation requirements; new provisions for emergency response training and planning; and a public process for assessing the feasibility of a federally operated central reporting system and data center. In addition to amending various HMTA provisions, the new HMTUSA act provides appropriations to carry out the specific goals of the legislation. The act authorizes appropriations for the 1991, 1992 and 1993 fiscal years

Experience gained in enhancing operational safety at ComEd`s nuclear power plants

Energy Technology Data Exchange (ETDEWEB)

Elias, D [Commonwealth Edison Co. (United States)

1997-09-01

The following aspects of experience gained in enhancing operational safety at Comed`s nuclear power plants are discussed: nuclear safety policy; centralization/decentralization; typical nuclear operating organization; safety review boards; human performance enhancement; elements of effective nuclear oversight.

Thermal-Responsive Polymers for Enhancing Safety of Electrochemical Storage Devices.

Science.gov (United States)

Yang, Hui; Leow, Wan Ru; Chen, Xiaodong

2018-03-01

Thermal runway constitutes the most pressing safety issue in lithium-ion batteries and supercapacitors of large-scale and high-power density due to risks of fire or explosion. However, traditional strategies for averting thermal runaway do not enable the charging-discharging rate to change according to temperature or the original performance to resume when the device is cooled to room temperature. To efficiently control thermal runaway, thermal-responsive polymers provide a feasible and reversible strategy due to their ability to sense and subsequently act according to a predetermined sequence when triggered by heat. Herein, recent research progress on the use of thermal-responsive polymers to enhance the thermal safety of electrochemical storage devices is reviewed. First, a brief discussion is provided on the methods of preventing thermal runaway in electrochemical storage devices. Subsequently, a short review is provided on the different types of thermal-responsive polymers that can efficiently avoid thermal runaway, such as phase change polymers, polymers with sol-gel transitions, and polymers with positive temperature coefficients. The results represent the important development of thermal-responsive polymers toward the prevention of thermal runaway in next-generation smart electrochemical storage devices. © 2018 WILEY-VCH Verlag GmbH & Co. KGaA, Weinheim.

Execution of the Occupational Safety and Health Act (1994 in the Construction Industry from Contractors’ Point of View

Directory of Open Access Journals (Sweden)

Awang H.

2014-01-01

Full Text Available Construction is one of the highest contributing industries to occupational accidents by sector in Malaysia. Statistics have been drawn from year to year that show an increasing number of cases of accidents by industry sector. While it is impossible to completely eliminate all accidents, with a proper and effective safety and health policy or rules set by top management, especially contractors, the rate of accidents on construction sites can be reduced. The main objective of this study is to analyse the degree of application of the Occupational Safety and Health Act 1994 (OSHA 1994 in the construction industry and to identify the contributing factors leading to a lack of execution of OSHA 1994 on construction sites with a primary focus on contractors’ point of view. Five on-going construction projects in Perak were selected as case studies and site inspections were conducted. The results showed that none of the contractors have fully implemented the rules and regulations provided by the government. Within this report, some recommendations are made towards enhancing the safety and health issues on construction sites.

Act No. 15 of 22 April 1980 setting up the Nuclear Safety Council

International Nuclear Information System (INIS)

1980-01-01

The Spanish authorities are in the process or reorganising the public nuclear sector in order to separate the promotional and research aspects of the uses of nuclear energy for peaceful purposes from the regulation and control of such activities. To this effect this Act sets up a Nuclear Safety Council which takes over part of the duties and the personnel of the Junta de Energia Nuclear provided for by the Act of 29th April 1964 on Nuclear Energy. The new Nuclear Safety Council is a body which is independent of the State central administration and has legal personality as well as its own financial resources required to carry out its duties. The latter comprise, inter alia, proposing to the Government the regulations required in matters of nuclear safety and radiation protection; this includes the setting-up of standards and criteria for the selection of nuclear installation sites, in consultation with the local competent bodies. (NEA) [fr

Safety enhancement in NPP Bohunice

International Nuclear Information System (INIS)

Lipar, M.; Mihalik, M.

1997-01-01

The upgrading and safety enhancement of both the Bohunice V-1 and V-2 reactors is described in detail. The total estimated cost of the gradual reconstruction of these two units during 1996 to 1999 is 180 mil. US dollars. For the 1995 to 1997 period, the actions common for both units include a quality assurance programme, a personnel training programme, installation of a multifunction simulator, implementation of symptom-oriented operation procedures, installation of diagnostic systems, of a site security system, and of a teledosimetric system. At present, the main maintenance tasks are: to carry out major repair of units, to remedy service interruptions, to enhance equipment service availability, to enhance the technical level of corrective actions at equipment. Investment into maintenance level upgrade has grown from 7.5 mil. Slovak crowns in 1994 to estimated 32 mil. in 2000. The partners of international cooperation are mentioned. (M.D.)

The Validity of Warrantless Searches under the Occupational Safety and Health Act of 1970

Science.gov (United States)

Shanks, Michael D.

1975-01-01

One of the most controversial federal acts providing for random administrative searches is the Occupational Safety and Health Act of 1970 (OSHA). The author reviews the search and seizure law and concludes that abandonment of Fourth Amendment rights should not be predicated on the mere convenience of even a justifiable regulatory scheme. (JT)

Challenges and Enhancements to the Safety Culture of the Regulatory Body

International Nuclear Information System (INIS)

Niel, Jean-Christophe; Chevet, Pierre Franck; Sheron, Brian; Boyd, Michael; Carlsson, Lennart; Tiippana, Petteri; Burns, Stephen; Jamieson, Terry; Fuketa, Toyoshi; Rzentkowski, Greg; Weiss, Frank Peter; Le Guen, Bernard

2015-06-01

The workshop opened with presentations by both the NEA Director-General and the chair of the three committees directly involved with the safety culture of the regulatory body (SCRB). The opening session set the scene and gave an overview of the SCRB together with presentations and discussions on priorities and challenges. The main session focused on the principles of the SCRB, its implementation and the challenges and enhancements that are being raised and considered. The workshop concluded with a session that looked at findings and conclusions, the way forward and an agreed position on the SCRB. This document brings together the available presentations (slides) given at the workshop: 1 - Introduction: Challenges and Enhancements to the Safety Culture of the Regulatory Body (J-C. Niel); 2 - Thoughts on Safety Culture from a CSNI Perspective (B. Sheron); 3 - Radiological Protection Culture: CRPPH Work (M. Boyd); 4 - Challenges and Enhancements to Safety Culture of the Regulatory Body (L. Carlsson); 5 - Principles for the safety culture of the regulatory body (P. Tiippana); 6 - NRC's Internal Safety Culture: Successes, Challenges, and the Path Forward (S.G. Burns); 7 - Insights on the Canadian Nuclear Safety Commission's Safety Culture Journey (T. Jamieson); 8 - Lessons Learned from the Fukushima Dai-ichi Accident regarding Safety Culture of Regulatory Body (T. Fuketa); 9 - Challenges to Regulatory Bodies' safety culture (P-F. Chevet); 10 - Regulatory Safety Culture: International Perspective (G. Rzentkowski); 11 - Integration of Safety Research into Safety Culture Concepts (F-P. Weiss); 12 - Radiation Protection and Emergency Management Aspects: Culture drawn up by RP professionals (B. Le Guen); 13 - Closing session panel (L. Carlsson)

Sociological refigurations of patient safety; ontologies of improvement and 'acting with' quality collaboratives in healthcare.

Science.gov (United States)

Zuiderent-Jerak, Teun; Strating, Mathilde; Nieboer, Anna; Bal, Roland

2009-12-01

The increasing focus on patient safety in the field of health policy is accompanied by research programs that articulate the role of the social sciences as one of contributing to enhancing safety in healthcare. Through these programs, new approaches to studying safety are facing a narrow definition of 'usefulness' in which researchers are to discover the factors that support or hamper the implementation of existing policy agendas. This is unfortunate since such claims for useful involvement in predefined policy agendas may undo one of the strongest assets of good social science research: the capacity to complexify the taken-for-granted conceptualizations of the object of study. As an alternative to this definition of 'usefulness', this article proposes a focus on multiple ontologies in the making when studying patient safety. Through such a focus, the role of social scientists becomes the involvement in refiguring the problem space of patient safety, the relations between research subjects and objects, and the existing policy agendas. This role gives medical sociologists the opportunity to focus on the question of which practices of 'effective care' are being enacted through different approaches for dealing with patient safety and what their consequences are for the care practices under study. In order to explore these questions, this article draws on empirical material from an ongoing evaluation of a large quality improvement collaborative for the care sectors in the Netherlands. It addresses how issues like 'effectiveness' and 'client participation' are at present articulated in this collaborative and shows that alternative figurations of these notions dissolve many 'implementation problems' presently experienced. Further it analyzes how such a focus of medical sociology on multiple ontologies engenders new potential for exploring particular spaces for 'acting with' quality improvement agents.

PNRA Process for Utilizing Experience Feedback for Enhancing Nuclear Safety

International Nuclear Information System (INIS)

Shah, Z.H.

2016-01-01

One of the elements essential for any organization to become a learning organization is to learn from its own and others experience. The importance of utilizing experience feedback for enhancing operational safety is highlighted in nuclear industry again and again and this has resulted in establishment of several national and international forums. In addition, IAEA action plan on nuclear safety issued after Fukushima accident further highlighted the importance of experience sharing among nuclear community to enhance global nuclear safety regime. PNRA utilizes operating experience feedback gathered through different sources in order to improve its regulatory processes. During the review of licensing submissions, special emphasis is given to utilize the lessons learnt from experience feedback relating to nuclear industry within and outside the country. This emphasis has gradually resulted in various safety improvements in the facilities and processes. Accordingly, PNRA has developed a systematic process of evaluation of international operating experience feedback with the aim to create safety conscious approach. This process includes collecting information from different international forums such as IAEA, regulatory bodies of other countries and useful feedback of past accidents followed by its screening, evaluation and suggesting recommendations both for PNRA and its licensees. As a result of this process, several improvements concerning regulatory inspection plans of PNRA as well as in regulatory decision making and operational practices of licensees have been highlighted. This paper will present PNRA approach for utilizing experience feedback in its regulatory processes for enhancing / improving nuclear safety. (author)

Assessment of Application Example for a Sodium Fire Extinguishing Facility using Safety Control of Dangerous Substances Act

International Nuclear Information System (INIS)

Jung, Minhwan; Jeong, Ji-Young; Kim, Jongman

2014-01-01

Sodium is under regulation of four kinds of laws including the Safety Control of Dangerous Substances Act and it is under categorized as Class 3(pyrophoric material, water-prohibiting substance). To obtain a license for a sodium experiment facility, the codes and regulations must be satisfied in the Safety Control of Dangerous Substance Act. However, there are some parts that need to be discussed in related regulations in the Safety Control of Dangerous Substance Act because there are differences with the actual features of sodium. To apply for an actual sodium facility, it is necessary to give a supplementary explanation regarding the regulations. The objective of this study is to assess the application example of a sodium experiment facility using the above mentioned laws and to propose the necessity of an amendment for conventional laws in regard to fire extinguishing systems and agents. In this work, an application example of a sodium experiment facility using the Safety Control of Dangerous Substances Act, and the necessity of amending the existing laws in regard to fire extinguishing systems including the agent used, was assessed. The safest standard was applied for cases in which the consideration of a sodium fire is not mentioned in conventional regulations. For the construction of the PGSFR (Prototype Gen-IV Sodium-cooled Fast Reactor), the described regulations in this work should be reviewed and improved carefully by the fire safety regulatory body

Defining safety culture and the nexus between safety goals and safety culture. 4. Enhancing Safety Culture Through the Establishment of Safety Goals

International Nuclear Information System (INIS)

Tateiwa, Kenji; Miyata, Koichi; Yahagi, Kimitoshi

2001-01-01

Safety culture is the perception of each individual and organization of a nuclear power plant that safety is the first priority, and at Tokyo Electric Power Company (TEPCO), we have been practicing it in everyday activities. On the other hand, with the demand for competitiveness of nuclear power becoming even more intense these days, we need to pursue efficient management while maintaining the safety level at the same time. Below, we discuss how to achieve compatibility between safety culture and efficient management as well as enhance safety culture. Discussion at Tepco: safety culture-nurturing activities such as the following are being implemented: 1. informing the employees of the 'Declaration of Safety Promotion' by handing out brochures and posting it on the intranet home page; 2. publishing safety culture reports covering stories on safety culture of other industry sectors, recent movements on safety culture, etc.; 3. conducting periodic questionnaires to employees to grasp how deeply safety culture is being established; 4. carrying out educational programs to learn from past cases inside and outside the nuclear industry; 5. committing to common ownership of information with the public. The current status of safety culture in Japan sometimes seems to be biased to the quest of ultimate safety; rephrasing it, there have been few discussions regarding the sufficiency of the quantitative safety level in conjunction with the safety culture. Safety culture is one of the most crucial foundations guaranteeing the plant's safety, and for example, the plant safety level evaluated by probabilistic safety assessment (PSA) could be said to be valid only on the ground that a sound and sufficient safety culture exists. Although there is no doubt that the safety culture is a fundamental and important attitude of an individual and organization that keeps safety the first priority, the safety culture in itself should not be considered an obstruction to efforts to implement

Assessment of compliance of Employees and Management to Occupational Health & Safety Act in the Department of Public Safety in the North West Province / Neo Patricia Seleka

OpenAIRE

2011-01-01

The study was designed to determine the worker assessment of compliance to OHS act in the department of Public safety. One hundred and two (102) employees were selected randomly using table of random numbers from different directorates such as Human resources, Finance, Road safety, Crime prevention and Traffic management. Data were collected using a structured questionnaire which was made of personal characteristics and sections on level of compliance with OHS act, workers' ...

Tissue-specific RNA expression marks distant-acting developmental enhancers.

Directory of Open Access Journals (Sweden)

Han Wu

2014-09-01

Full Text Available Short non-coding transcripts can be transcribed from distant-acting transcriptional enhancer loci, but the prevalence of such enhancer RNAs (eRNAs within the transcriptome, and the association of eRNA expression with tissue-specific enhancer activity in vivo remain poorly understood. Here, we investigated the expression dynamics of tissue-specific non-coding RNAs in embryonic mouse tissues via deep RNA sequencing. Overall, approximately 80% of validated in vivo enhancers show tissue-specific RNA expression that correlates with tissue-specific enhancer activity. Globally, we identified thousands of tissue-specifically transcribed non-coding regions (TSTRs displaying various genomic hallmarks of bona fide enhancers. In transgenic mouse reporter assays, over half of tested TSTRs functioned as enhancers with reproducible activity in the predicted tissue. Together, our results demonstrate that tissue-specific eRNA expression is a common feature of in vivo enhancers, as well as a major source of extragenic transcription, and that eRNA expression signatures can be used to predict tissue-specific enhancers independent of known epigenomic enhancer marks.

Mochovce NPP safety measures evaluation from point of view of operational safety enhancement

International Nuclear Information System (INIS)

Cillik, I.; Vrtik, L.

2000-01-01

Mochovce NPP consists of four reactor units of WWER 440/V213 type and it is located in the south-middle part of Slovakia. At present first unit operated and the second one under the construction finishing. As these units represent second generation of WWER reactor design, the additional safety measures (SM) were implemented to enhance operational and nuclear safety according to the recommendations of performed international audits and operational experience based on exploitation of other similar units (as Dukovany and J. Bohunice NPPs). These requirements result into a number of SMs grouped according to their purpose to reach recent international requirements on nuclear and operational safety. The paper presents the bases used for safety measures establishing including their grouping into the comprehensive tasks covering different areas of safety goals as well as structural organization of a project management of including participating companies and work performance. More, results are given regarding contribution of selected SMs to the total core damage frequency decreasing. (author)

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

Data.gov (United States)

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

Leadership and Safety Management: Regulatory Initiatives for Enhancing Nuclear Safety in the Republic of Korea

International Nuclear Information System (INIS)

Yun, C.H.; Park, Y.W.; Choi, K.S.

2010-01-01

Since the construction of the first nuclear power plant (NPP) in the Republic of Korea in 1978, a high level of nuclear safety has continued to be maintained. This has been the important basis on which the continuous construction of NPPs has been possible in the country. To date, regulatory initiatives, leaderships and strategies adopting well harmonized regulatory systems and practices of advanced countries have contributed to improving the effectiveness and efficiency of safety regulation and further enhancing nuclear safety. The outcomes have resulted in a high level of safety and performance of Korean NPPs, attributing largely to the safety promotion policy. Recently, with the support of the Korean Ministry of Education, Science and Technology (MEST), the Korea Institute of Nuclear Safety (KINS) established the International Nuclear Safety School and created a Nuclear Safety Master's Degree Programme. Further, it developed multilateral and bilateral cooperation with other agencies to promote global nuclear safety, with the aim of providing knowledge and training to new entrant countries in establishing the safety infrastructure necessary for ensuring an acceptable level of nuclear safety. (author)

The Food Safety Modernization Act: a barrier to trade? Only if the science says so.

Science.gov (United States)

McNeill, Naomi

2012-01-01

The Food Safety Modernization Act improves oversight of America's food safety system. Title III, which regulates imported food, may create extra burdens for importers and therefore act as a barrier to trade. What will be on trial before the World Trade Organization (WTO), however, is not the law's content, but the science supporting it. Under the WTO regime, food safety laws that could restrict the free movement of food commodities must be sufficiently justified by scientific evidence. Member states must engage in risk assessments and regulate food imports in a manner that is "no more restrictive than necessary" to protect against the health risks identified by scientific evidence. This article examines the requirements of the WTO to evaluate the FSMA's legality under WTO rules. It analyzes the case law of the WTO Panel and Appellate Body and compares the FMSA to the EU's General Food Law.

Mentorship for newly appointed physicians: a strategy for enhancing patient safety?

Science.gov (United States)

Harrison, Reema; McClean, Serwaa; Lawton, Rebecca; Wright, John; Kay, Clive

2014-09-01

Mentorship is an increasingly popular innovation from business and industry that is being applied in health-care contexts. This paper explores the concept of mentorship for newly appointed physicians in their first substantive senior post, and specifically its utilization to enhance patient safety. Semi-structured face to face and telephone interviews with Medical Directors (n = 5), Deputy Medical Directors (n = 4), and Clinical Directors (n = 6) from 9 acute NHS Trusts in the Yorkshire and Humber region in the north of England. A focused thematic analysis was used. A number of beneficial outcomes were associated with mentorship for newly appointed physicians including greater personal and professional support, organizational commitment, and general well-being. Providing newly appointed senior physicians with support through mentorship was considered to enhance the safety of patient care. Mentorship may prevent or reduce active failures, be used to identify threats in the local working environment, and in the longer term, address latent threats to safety within the organization by encouraging a healthier safety culture. Offering mentorship to all newly appointed physicians in their first substantive post in health care may be a useful strategy to support the development of their clinical, professional, and personal skills in this transitional period that may also enhance the safety of patient care.

All About OSHA: The Who, What, Where, When, Why and How of the Occupational Safety and Health Act of 1970.

Science.gov (United States)

Occupational Safety and Health Administration, Washington, DC.

The pamphlet summarizes the operations of the Occupational Safety and Health Administration (OSHA) and the provisions of the Occupational Safety and Health Act of 1970. OSHA's mission is to assure safe and healthful working conditions and to preserve human resources. Employers and employees who are covered by the act and employer and employee…

75 FR 74050 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

Science.gov (United States)

2010-11-30

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal...) Communications Security, Reliability, and Interoperability Council (CSRIC) will hold its fourth meeting on...

Safety first!

CERN Multimedia

2016-01-01

Among the many duties I assumed at the beginning of the year was the ultimate responsibility for Safety at CERN: the responsibility for the physical safety of the personnel, the responsibility for the safe operation of the facilities, and the responsibility to ensure that CERN acts in accordance with the highest standards of radiation and environmental protection.   The Safety Policy document drawn up in September 2014 is an excellent basis for the implementation of Safety in all areas of CERN’s work. I am happy to commit during my mandate to help meet its objectives, not least by ensuring the Organization makes available the necessary means to achieve its Safety objectives. One of the main objectives of the HSE (Occupational Health and Safety and Environmental Protection) unit in the coming months is to enhance the measures to minimise CERN’s impact on the environment. I believe CERN should become a role model for an environmentally-aware scientific research laboratory. Risk ...

Engineering Solutions to Enhance Traffic Safety Performance on Two-Lane Highways

Directory of Open Access Journals (Sweden)

Lina Wu

2015-01-01

Full Text Available Improving two-lane highway traffic safety conditions is of practical importance to the traffic system, which has attracted significant research attention within the last decade. Many cost-effective and proactive solutions such as low-cost treatments and roadway safety monitoring programs have been developed to enhance traffic safety performance under prevailing conditions. This study presents research perspectives achieved from the Highway Safety Enhancement Project (HSEP that assessed safety performance on two-lane highways in Beijing, China. Potential causal factors are identified based on proposed evaluation criteria, and primary countermeasures are developed against inferior driving conditions such as sharp curves, heavy gradients, continuous downgrades, poor sight distance, and poor clear zones. Six cost-effective engineering solutions were specifically implemented to improve two-lane highway safety conditions, including (1 traffic sign replacement, (2 repainting pavement markings, (3 roadside barrier installation, (4 intersection channelization, (5 drainage optimization, and (6 sight distance improvement. The effectiveness of these solutions was examined and evaluated based on Empirical Bayes (EB models. The results indicate that the proposed engineering solutions effectively improved traffic safety performance by significantly reducing crash occurrence risks and crash severities.

75 FR 56533 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

Science.gov (United States)

2010-09-16

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal...) Communications Security, Reliability, and Interoperability Council (CSRIC) will hold its third meeting on October...

77 FR 70777 - Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications...

Science.gov (United States)

2012-11-27

... FEDERAL COMMUNICATIONS COMMISSION Public Safety and Homeland Security Bureau; Federal Advisory Committee Act; Communications Security, Reliability, and Interoperability Council AGENCY: Federal... Security, Reliability, and Interoperability Council (CSRIC III) scheduled for December 5, 2012, at Federal...

Organized labor and the origins of the Occupational Safety and Health Act.

Science.gov (United States)

Asher, Robert

2014-11-01

New Solutions is republishing this 1991 article by Robert Asher, which reviews the history of organized labor's efforts in the United States to secure health and safety protections for workers. The 1877 passage of the Massachusetts factory inspection law and the implementation of primitive industrial safety inspection systems in many states paralleled labor action for improved measures to protect workers' health and safety. In the early 1900s labor was focusing on workers' compensation laws. The New Deal expanded the federal government's role in worker protection, supported at least by the Congress of Industrial Organizations (CIO), but challenged by industry and many members of the U.S. Congress. The American Federation of Labor (AFL) and the CIO backed opposing legal and inspection strategies in the late 1940s and through the 1950s. Still, by the late 1960s, several unions were able to help craft the Occupational Safety and Health Act of 1970 and secure new federal protections for U.S. workers.

ChIP-seq Mapping of Distant-Acting Enhancers and Their In Vivo Activities

Energy Technology Data Exchange (ETDEWEB)

Visel, Axel; Pennacchio, Len A.

2011-06-01

The genomic location and function of most distant-acting transcriptional enhancers in the human genome remains unknown We performed ChIP-seq for various transcriptional coactivator proteins (such as p300) directly from different embryonic mouse tissues, identifying thousands of binding sitesTransgenic mouse experiments show that p300 and other co-activator peaks are highly predictive of genomic location AND tissue-specific activity patterns of distant-acting enhancersMost enhancers are active only in one or very few tissues Genomic location of tissue-specific p300 peaks correlates with tissue-specific expression of nearby genes Most binding sites are conserved, but the global degree of conservation varies between tissues

Safety culture in nuclear installations. Guidance for the use in enhancement of safety culture

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-12-01

IAEA Assessment of the Safety Culture in Organizations Team (ASCOT) activities, significant work has been done with respect to indicators to determine the effectiveness of safety culture. IAEA-TECDOC-860, ASCOT Guidelines, issued in 1996, proposed key indicators for the different areas that need to be considered when assessing safety culture. A number of other INSAG reports and Safety Series reports have been published by the IAEA to provide information that will be helpful to organizations that are interested in developing or enhancing their safety culture. Recently the IAEA perspective on safety culture has broadened even further with attention focused on obtaining a deeper understanding of the actual concept of culture and particularly organizational culture. The approach supplements the IAEA previous efforts to promote a better understanding of safety culture, but does not replace them. It can be argued that the IAEA perspective of safety culture has evolved in stages. The first stage was associated with the definition of safety culture; the second stage with how to assess it; the third stage on how to enhance it; and the fourth and current stage on obtaining a deeper understanding of the actual concept of culture. The hope is that the more sophisticated understanding obtained in the fourth stage will lead to improved ways of assessing safety culture, and also increase our ability to detect changes in safety culture at an early point in time. This ability will enable corrective actions to be taken to avoid the consequences of a deteriorating safety culture.

Safety culture in nuclear installations. Guidance for the use in enhancement of safety culture

International Nuclear Information System (INIS)

2002-12-01

IAEA Assessment of the Safety Culture in Organizations Team (ASCOT) activities, significant work has been done with respect to indicators to determine the effectiveness of safety culture. IAEA-TECDOC-860, ASCOT Guidelines, issued in 1996, proposed key indicators for the different areas that need to be considered when assessing safety culture. A number of other INSAG reports and Safety Series reports have been published by the IAEA to provide information that will be helpful to organizations that are interested in developing or enhancing their safety culture. Recently the IAEA perspective on safety culture has broadened even further with attention focused on obtaining a deeper understanding of the actual concept of culture and particularly organizational culture. The approach supplements the IAEA previous efforts to promote a better understanding of safety culture, but does not replace them. It can be argued that the IAEA perspective of safety culture has evolved in stages. The first stage was associated with the definition of safety culture; the second stage with how to assess it; the third stage on how to enhance it; and the fourth and current stage on obtaining a deeper understanding of the actual concept of culture. The hope is that the more sophisticated understanding obtained in the fourth stage will lead to improved ways of assessing safety culture, and also increase our ability to detect changes in safety culture at an early point in time. This ability will enable corrective actions to be taken to avoid the consequences of a deteriorating safety culture

Contractors’ Attitude towards Enhancing Safety Performance: Case Study on Construction Firms in Penang

Directory of Open Access Journals (Sweden)

Ulang N. Md

2014-01-01

Full Text Available A qualitative study was conducted to investigate the contractors’ attitude towards enhancing the safety performance in construction site. Despite the fact that there are many safety initiatives established by the government, the rates of accidents are still in a critically high condition. Thus the purpose of this research is to study the contractors’ attitude towards enhancing the implementation of safety management system in construction site in order to increase the safety awareness of construction practitioners in construction site and improve the safety condition of construction sites. This study is conducted through oral interviews with the construction practitioners, and visual inspection of construction sites. The attitudes of contractors are evaluated from 3 aspects: Contractors’ efforts in implement and enforce the safety rules, Contractors efforts in overcoming the rate of accidents, and Reasons given by the contractors for not implement safety law.

76 FR 13643 - FDA Food Safety Modernization Act: Title III-A New Paradigm for Importers; Public Meeting

Science.gov (United States)

2011-03-14

... Act: Title III--A New Paradigm for Importers; Public Meeting AGENCY: Food and Drug Administration, HHS... announcing a public meeting entitled ``FDA Food Safety Modernization Act: Title III--A New Paradigm for... provided. Request special accommodations due By March 22, 2011.... Patricia M. Kuntze, 301- to disability...

48 CFR 852.222-70 - Contract Work Hours and Safety Standards Act-nursing home care contract supplement.

Science.gov (United States)

2010-10-01

... Safety Standards Act-nursing home care contract supplement. 852.222-70 Section 852.222-70 Federal...—nursing home care contract supplement. As prescribed in 822.305, for nursing home care requirements, insert the following clause: Contract Work Hours and Safety Standards Act—Nursing Home Care Contract...

Enhancing Safety Culture in Complex Nuclear Industry Projects

International Nuclear Information System (INIS)

Gotcheva, N.

2016-01-01

This paper presents an on-going research project “Management principles and safety culture in complex projects” (MAPS), supported by the Finnish Research Programme on Nuclear Power Plant Safety 2015-2018. The project aims at enhancing safety culture and nuclear safety by supporting high quality execution of complex projects in the nuclear industry. Safety-critical industries are facing new challenges, related to increased outsourcing and complexity in technology, work tasks and organizational structures (Milch and Laumann, 2016). In the nuclear industry, new build projects, as well as modernisation projects are temporary undertakings often carried out by networks of companies. Some companies may have little experience in the nuclear industry practices or consideration of specific national regulatory requirements. In large multinational subcontractor networks, the challenge for assuring nuclear safety arises partly from the need to ensure that safety and quality requirements are adequately understood and fulfilled by each partner. Deficient project management practices and unsatisfactory nuclear safety culture in project networks have been recognised as contributing factors to these challenges (INPO, 2010). Prior evidence indicated that many recent major projects have experienced schedule, quality and financial challenges both in the nuclear industry (STUK, 2011) and in the non-nuclear domain (Ahola et al., 2014; Brady and Davies, 2010). Since project delays and quality issues have been perceived mainly as economic problems, project management issues remain largely understudied in safety research. However, safety cannot be separated from other performance aspects if a systemic view is applied. Schedule and quality challenges may reflect deficiencies in coordination, knowledge and competence, distribution of roles and responsibilities or attitudes among the project participants. It is increasingly understood that the performance of the project network in all

On safety enhancements for medical robots

International Nuclear Information System (INIS)

Ng, W.S.; Tan, C.K.

1996-01-01

Both software and hardware methods to enhance safety are discussed for active medical robots applied to, among others, neurosurgery, orthopaedic surgery and prostatectomy. This paper advocates that while it is practically difficult, if not impossible, for software reliability to be 100%, there are positive measures by which a medical robot system can be made adequately or inherently safe. Such measures avoid the problems of software reliability but turn to mathematical logic directly to build a safer system. Examples in a newly developed prototype, known as surgeon assistant robot for selected urological disorders (SARUD), are given to illustrate the concept. Although software measures to promote reliability of a system is less preferred compared to hardware measures, as it can never escape from operating on a hardware platform, it is suggested that a complementary/ hybrid approach can be a good solution for achieving a safe and flexible (by being reprogrammable) system. A totally independent safety monitor is being built. It can arrest a servo runaway and detect out-of-safe-boundary conditions, using encoder pulses as input. This dedicated system can resolve some major safety concerns of a medical robot such as SARUD

Enhancing the Safety Climate and Reducing Violence Against Staff in Closed Hospital Wards.

Science.gov (United States)

Isaak, Valerie; Vashdi, Dana; Bar-Noy, Dor; Kostisky, Hava; Hirschmann, Shmuel; Grinshpoon, Alexander

2017-09-01

This study examined the effectiveness of an intervention program to enhance unit safety climate and minimize employee risk of injury from patient violence. The intervention program, including a 3-day workshop, was offered to personnel on maximum security units of an Israeli psychiatric hospital. Safety climate was examined before and after the implementation of the intervention, and incidents of patient violence were investigated. Six months after the intervention, a significant improvement in employees' perceptions of management's commitment to safety as well as a marginally significant improvement in communication about safety issues were found. This study demonstrated that an intervention program to enhance safety climate was associated with a decrease in the number of aggressive incidents. The researchers concluded that this intervention program is likely to return a sense of safety to workers and reduce workplace violence.

U.S. assistance enhancing safety culture in countries operating Soviet-designed reactors

International Nuclear Information System (INIS)

Guppy, J.G.; Horak, W.C.; Reisman, A.W.

1995-01-01

The United States Department of Energy (USDOE) is managing the International Nuclear Safety Program (INSP), which is aimed at providing assistance to enhance safety at commercial nuclear power plants (NPPS) in Russia and Ukraine, as well as Central European countries (CEC). The funding for this program has been provided by the US Agency for International Development (AID). Brookhaven National Laboratory has been assisting DOE in certain portions of this program. The enhancement of safety culture is one of the most important goals of the joint International Nuclear Safety Program. In terms of the INSP, safety culture is comprised of two major components; (1) an environment that is a function of regulations, management sensitivity and structure; and (2) an individual commitment to safety in the day to day execution of activities in terms of thought and accountability. The long term impact of the INSP activities can only be measured by the effectiveness of strengthening safety culture within our partner counties. The strengthening of this culture will manifest in reduced risk of a nuclear accident long after other evidence of the INSP activities has disappeared. One area within the INSP, which has already led to a number of successful specific projects, is under the plant safety upgrade activities. Here, the US and the partner countries jointly identify specific target areas for the INSP efforts. Each identified area has a major component involving safety culture enhancement. With any direct involvement in the particular assistance activities, areas are identified to include a need for training. As technical experts and management from the partner country are assisted in addressing the identified needs, the training programs are provided which will not only address the specific need at hand, but will also teach skills which can be applied to different, but related needs that may exist or develop

A proposed approach for enhancing design safety assurance of future plants

International Nuclear Information System (INIS)

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

2010-01-01

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

Criticality safety enhancements for SCALE 6.2 and beyond

International Nuclear Information System (INIS)

Rearden, Bradley T.; Bekar, Kursat B.; Celik, Cihangir; Clarno, Kevin T.; Dunn, Michael E.; Hart, Shane W.; Ibrahim, Ahmad M.; Johnson, Seth R.; Langley, Brandon R.; Lefebvre, Jordan P.; Lefebvre, Robert A.; Marshall, William J.; Mertyurek, Ugur; Mueller, Don; Peplow, Douglas E.; Perfetti, Christopher M.; Petrie Jr, Lester M.; Thompson, Adam B.; Wiarda, Dorothea; Wieselquist, William A.; Williams, Mark L.

2015-01-01

SCALE is a widely used suite of tools for nuclear systems modeling and simulation that provides comprehensive, verified and validated, user-friendly capabilities for criticality safety, reactor physics, radiation shielding, and sensitivity and uncertainty analysis. Since 1980, regulators, industry, and research institutions around the world have relied on SCALE for nuclear safety analysis and design. SCALE 6.2 provides several new capabilities and significant improvements in many existing features for criticality safety analysis. Enhancements are realized for nuclear data; multigroup resonance self-shielding; continuous-energy Monte Carlo analysis for sensitivity/uncertainty analysis, radiation shielding, and depletion; and graphical user interfaces. An overview of these capabilities is provided in this paper, and additional details are provided in several companion papers.

Safety parameter display system: an operator support system for enhancement of safety in Indian PHWRs

International Nuclear Information System (INIS)

Subramaniam, K.; Biswas, T.

1994-01-01

Ensuring operational safety in nuclear power plants is important as operator errors are observed to contribute significantly to the occurrence of accidents. Computerized operator support systems, which process and structure information, can help operators during both normal and transient conditions, and thereby enhance safety and aid effective response to emergency conditions. An important operator aid being developed and described in this paper, is the safety parameter display system (SPDS). The SPDS is an event-independent, symptom-based operator aid for safety monitoring. Knowledge-based systems can provide operators with an improved quality of information. An information processing model of a knowledge based operator support system (KBOSS) developed for emergency conditions using an expert system shell is also presented. The paper concludes with a discussion of the design issues involved in the use of a knowledge based systems for real time safety monitoring and fault diagnosis. (author). 8 refs., 4 figs., 1 tab

Software diversity: way to enhance safety?

International Nuclear Information System (INIS)

Dahll, G.; Bishop, P.

1990-01-01

The topic of the paper is the use of diversely produced programs to enhance the safety of computer-based systems applied in safety-critical areas. The paper starts with a survey of scientific investigations on the impact of software redundancy made at various institutions around the world. Main emphasis will, however, be put on the PODS/STEM projects, which have been performed at the OECD Halden Project in cooperation with the Technical Research Center of Finland, the Safety and Reliability Directorate, AEA Technology, UK, and Central Electricity Research Laboratory (now National Power Technology and Environment Centre), UK. In these projects, three program versions were made independently by three different teams, all based on the same specification. The three programs were tested back-to-back with a large amount of test data. The experience and results from this process were carefully logged and used for further analysis. Various strategies for test data selection were compared, with respect to fault finding strategies, as well as to branch and statement coverages of the tested programs. The assumption of independence of failures in diversely produced programs was investigated. A particularly interesting effect, namely failure masking due to program structure, was revealed. Static analysis techniques, software measures, and software reliability estimates were also studied. (author)

76 FR 40648 - Safety Enhancements Part 139, Certification of Airports; Reopening of Comment Period

Science.gov (United States)

2011-07-11

... that was published on February 1, 2011. In that document, the FAA proposed several safety enhancements...-0247; Notice No. 11-01] RIN 2120-AJ70 Safety Enhancements Part 139, Certification of Airports... comment period for the NPRM published on February 1, 2011 (76 FR 5510) and reopened (76 FR 20570) April 13...

New generation main control room of enhanced safety NPP with MKER reactor

International Nuclear Information System (INIS)

Golovanev, V.E.; Gorelov, A.I.; Proshin, V.A.

1994-01-01

Russia is planning to begin the gradual substitution RMBK NPP units, whose resources were worked out itself, to NPP units with a 800 MW multiloop boiling water power reactor (MKER-800) enhanced safety at next ten-year period. Main drawbacks of RBMK Reactor were completely removed in design of MKER-800 reactor. Moreover some special decisions were made to give MKER-800 self-safety properties. The proposed design of the MKER-800 enhanced safety reactor is not only fully free from the drawbacks of the RBMK reactors, but also show a number of advantages of channel-type reactors. This Paper presents some preliminary proposals of MCR Design, that developed Research and Development Institute of Power Energy (RDIPE). 6 refs, 2 figs

Subcritical enhanced safety molten-salt reactor concept

International Nuclear Information System (INIS)

Alekseev, P.N.; Ignatiev, V.V.; Men'shikov, L.I.; Prusakov, V.N.; Ponomarev-Stepnoy, N.N.; Subbotin, S.A.; Krasnykh, A.K.; Rudenko, V.T.; Somov, L.N.

1995-01-01

The nuclear power and its fuel cycle safety requirements can be met in the main by providing nuclear power with subcritical molten salt reactors (SMSR) - 'burner' with an external neutron source. The utilized molten salt fuel is the decisive advantage of the SMSR over other burners. Fissile and fertile nuclides in the burner are solved in a liquid salt in the form of fluorides. This composition acts simultaneously as: a) fuel, b) coolant, c) medium for chemical partitioning and reprocessing. The effective way of reducing the external source power consists in the cascade neutron multiplication in the system of coupled reactors with suppressed feedback between them. (author)

ICT support safety, health and environment management system (e-SHEMS)

International Nuclear Information System (INIS)

Amy Hamijah Ab Hamid; Hasfazilah Hassan; Siti Massari Amran; Norzalina Nasirudin; Azimawati Ahmad; Mohd Suhaimi Kassim; Shaharum Ramli; Musa Ibrahim; Mohd Sidek Othman

2009-01-01

Safety program is compulsory for a nuclear technology related research and development institution like Nuclear Malaysia. It has been implemented in various safety standard systems including Act 514, Act 304, ISO 14000, OSHAS 18001 and IAEA. This paper began with Nuclear Malaysia history in initiating our own safety standard system since 1982. Currently, Nuclear Malaysia's Safety Health and Environment Management System (SHE-MS) was stipulated for similar purpose. Furthermore, it has implemented guidelines by AELB, IAEA, DOSH, Fire Brigade and Police Force. This paper briefly describes the overall structure of SHE-MS, how it functions and being managed, and lessons learned. The findings which are based on the issues and challenges, then it can be analysed to propose a development of SHE-MS ICT-support application for future improvement and enhancement in inculcating and nurturing safety culture among Nuclear Malaysia staff. (Author)

Safety enhancement efforts after Fukushima accident in Korea

Energy Technology Data Exchange (ETDEWEB)

Lee, U.C., E-mail: uclee@nssc.go.kr [Nuclear Safety & Security Commission, Seoul (Korea, Republic of)

2014-07-01

On March 11 of 2011, a massive earthquake and powerful tsunami hit the north-eastern region of Japan and the Fukushima Daiichi Nuclear Power Plant was massively damaged. Korea which is located closest to Japan was not directly affected, however, its people were shocked. They were concerned over the possibility of being exposed to radiation as well as for the safety of domestic nuclear power plants. The Korean government recognized the need to take prompt and immediate actions to alleviate these concerns. The Korean government immediately implemented special safety inspection and derived 50 long and short-term improvement action items to ensure safety of NPPs under extreme hazard conditions. At present, stage 3 of implementation strategy is being implemented, with completion of 22 items including ASTS (Automatic Seismic Trip System) as well as revision of 14 items including suitability review of action measures taken for investigation and research of maximum earthquake at NPP sites. The IAEA Integrated Regulatory Review Service (IRRS) mission was conducted for two weeks during July 10 and 22, 2011, which happened to be the very first review mission to be carried out since the Fukushima disaster. A module on the policy issues related to the actions taken after the Fukushima accident was newly added to the mission. The mission highlighted positive aspects of Korea's safety regulatory program, praising its technical competence and effectiveness. Additionally it concluded that Korea has been responding to the accident in a timely and an effective manner. The follow-up review mission is scheduled in December of this year, expanding the scope to include radiation safety as well. The most noteworthy change in Korea since the Fukushima accident is independence of the regulatory body. Not only to enhance effectiveness and independence of the regulatory body but to secure nuclear safety, the Nuclear Safety and Security Commission (NSSC) was established on October 26

The safety evaluation guide for laboratories and plants a tool for enhancing safety

International Nuclear Information System (INIS)

Lhomme, Veronique; Daubard, Jean-Paul

2013-01-01

The Institute for Radioprotection and Nuclear Safety (IRSN) acts as technical support for the French government Authorities competent in nuclear safety and radiation protection for civil and defence activities. In this frame, the Institute's performs safety assessments of the safety cases submitted by operators to these Authorities for each stage in the life cycle of a nuclear facility, including dismantling operations, which is subjected to a licensing procedure. In the fuel cycle field, this concerns a large variety of facilities. Very often, depending on facilities and on safety cases, safety assessment to be performed is multidisciplinary and involves the supervisor in charge of the facility and several safety experts, particularly to cover the whole set of risks (criticality, exposure to radiation, fire, handling, containment, human and organisational factors...) encountered during facility's operations. Taking these into account, and in order to formalize the assessment process of the fuel cycle facilities, laboratories, irradiators, particle accelerators, under-decommissioning reactors and radioactive waste management, the 'Plants, Laboratories, Transports and Waste Safety' Division of IRSN has developed an internal guide, as a tool: - To present the methodological framework, and possible specificities, for the assessment according to the 'Defence in Depth Concept' (Part 1); - To provide key questions associated to the necessary contradictory technical review of the safety cases (Part 2); - To capitalise on experience on the basis of technical examples (coming from incident reports, previous safety assessments...) demonstrating the questioning (Part 3). The guide is divided in chapters, each dedicated to a type of risk (dissemination of radioactive material, external or internal exposure from ionising radiation, criticality, radiolysis mechanisms, handling operations, earthquake, human or organisational factors...) or to a type

Enhancing Safety of Artificially Ventilated Patients Using Ambient Process Analysis.

Science.gov (United States)

Lins, Christian; Gerka, Alexander; Lüpkes, Christian; Röhrig, Rainer; Hein, Andreas

2018-01-01

In this paper, we present an approach for enhancing the safety of artificially ventilated patients using ambient process analysis. We propose to use an analysis system consisting of low-cost ambient sensors such as power sensor, RGB-D sensor, passage detector, and matrix infrared temperature sensor to reduce risks for artificially ventilated patients in both home and clinical environments. We describe the system concept and our implementation and show how the system can contribute to patient safety.

Sociodrama approach for enhancing nuclear safety

International Nuclear Information System (INIS)

Choi, K. S.; Kim, C. B.; Ha, Y. H.

2004-01-01

A role playing or sociodrama has been experimentally conducted among residents from 4 NPP sites in Korea and KINS employees as a psychological approach for enhancing nuclear safety and improving public communication and public confidence in regulator in Dec. 2004. In this paper, the results were analyzed and presented and future plan and area of further study were suggested. This socio-psychological approach can be used as a new communication method for improving mutual understanding between residents and NPP operators at sites. It can be also used to solve conflicts among stakeholders and interest groups in nuclear industry

78 FR 76391 - Proposed Enhancements to the Motor Carrier Safety Measurement System (SMS) Public Web Site

Science.gov (United States)

2013-12-17

...-0392] Proposed Enhancements to the Motor Carrier Safety Measurement System (SMS) Public Web Site AGENCY... proposed enhancements to the display of information on the Agency's Safety Measurement System (SMS) public Web site. On December 6, 2013, Advocates [[Page 76392

Safety culture enhancement through the implementation of IAEA guidelines

International Nuclear Information System (INIS)

Mengolini, A.; Debarberis, L.

2007-01-01

This paper presents the methodology applied and the results achieved in adapting and implementing the IAEA guidelines on safety culture to a research reactor as a step towards supporting its Life Management Program. The background is presented together with the effort undertaken to develop awareness on safety culture and the enhancement programme hereafter developed. The present study shows how issues of safety culture, management awareness and commitment deserve attention and can be of fundamental relevance also for research reactors. The study presents how guidelines developed specifically for nuclear power installations (NPPs) can be adapted to meet the needs and peculiarities of other nuclear installations. Moreover, the difficulties met during the implementation of the guidelines are discussed and important information and lessons can be learnt for the nuclear industry in general

Review of Post-Marketing Safety Data on Tapentadol, a Centrally Acting Analgesic.

Science.gov (United States)

Stollenwerk, Ariane; Sohns, Melanie; Heisig, Fabian; Elling, Christian; von Zabern, Detlef

2018-01-01

Tapentadol is a centrally acting analgesic that has been available for the management of acute and chronic pain in routine clinical practice since 2009. This is the first integrated descriptive analysis of post-marketing safety data following the use of tapentadol in a broad range of pain conditions relating to the topics overall safety, dose administration above approved dosages, administration during pregnancy, serotonin syndrome, respiratory depression, and convulsion. The data analyzed pertain to spontaneous reports from healthcare and non-healthcare professionals and were put in the context of safety information known from interventional and non-interventional trials. The first years of routine clinical practice experience with tapentadol have confirmed the tolerability profile that emerged from the clinical trials. Moreover, the reporting of expected side effects such as respiratory depression and convulsion was low and no major risks were identified. The evaluation of available post-marketing data did not confirm the theoretical risk of serotonin syndrome nor did it reveal unexpected side effects with administration of higher than recommended doses. More than 8 years after its first introduction, the favorable overall safety profile of tapentadol in the treatment of various pain conditions is maintained in the general population. Grünenthal GmbH.

Range and limits of application of Sec.12, Atomic Energy Act, as a legal basis of the nuclear plant safety ordinance

International Nuclear Information System (INIS)

Schmidt-Preuss, Matthias

2009-01-01

Ensuring plant safety is a key purpose of nuclear law. Sec.7 II No.3, Atomic Energy Act, is considered the basic norm of nuclear legislation. The main requirement this embodies is ensuring 'the provisions against damage arising from construction and operation of a plant as required in accordance with the state of the art'. These normative requirements constitute the strictest yardstick existing in legislation about technology. Putting it into effect has always been the purpose of the set of nuclear rules and regulations constituting the next lower level of legislation, which so far have developed by evolution and are now to be updated comprehensively in the format of so-called modules as provided for in the concept of the Federal Ministry for the Environment, Nature Conservation, and Nuclear Safety (BMU). So far, there has not been a nuclear plant safety ordinance. The Atomic Energy Act has always provided a basis for adopting such an ordinance, especially so in Sec.12 I 1 No.1, Atomic Energy Act. No federal government has so far wanted to make use of it. This makes it all the more remarkable that the BMU took up the subject of a nuclear plant safety ordinance as early as in 2006, starting a dialog with the federal states. This dialog meanwhile has come to a halt. The subject seems to be dormant right now, but certainly has not been shelved. Ensuring plant safety is a key purpose of nuclear law. Sec.7 II No.3, Atomic Energy Act, is considered the basic norm of nuclear legislation. The main requirement this embodies is ensuring 'the provisions against damage arising from construction and operation of a plant as required in accordance with the state of the art'. These normative requirements constitute the strictest yardstick existing in legislation about technology. Putting it into effect has always been the purpose of the set of nuclear rules and regulations constituting the next lower level of legislation, which so far have developed by evolution and are now to be

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

Science.gov (United States)

2012-04-27

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

A Study on Enhancement of Understanding of Radiation and Safety Management

Energy Technology Data Exchange (ETDEWEB)

Yoo, Dong Han; Park, Ji Young; Lee, Jae Uk; Bae, Jun Woo; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

2014-10-15

Concerns for radiation exposure have been increased from small and big radiation works or experiments with radiation generator (RG) or radiation isotopes (RI) at institutions using radiation in Korea. Actually, due to radiation exposure occurred on the process of handling RI, etc., The exposure should be maintained as low as reasonably possible. To do this, above all, suitable training and establishment of safety culture have to be preceded. In this respect, an education institution is a place where people learn first about handling radiations in various specialties with purposes including academic research, and the first learned habits and practices acts as the basis for safety management of radiation when they continue to do radiation work after going into the society. Hereford, it is needed to establish the right safety culture on radiation for its safe managing. In the present study, the direction for the right understandings and safety improvement are suggested through the radiation survey on education institutions and preparation of safety guidances for users. The basic guidance at the radiation experiment was prepared for the right understanding of the radiation to prevent radiation accidents from careless handling by workers based on the surveyed results for education institutions. It is expected to be used as fundamentals for improvement for radiation safety management of workers and researchers and, further, safety policy for national nuclear energy and radiations.

A Study on Enhancement of Understanding of Radiation and Safety Management

International Nuclear Information System (INIS)

Yoo, Dong Han; Park, Ji Young; Lee, Jae Uk; Bae, Jun Woo; Kim, Hee Reyoung

2014-01-01

Concerns for radiation exposure have been increased from small and big radiation works or experiments with radiation generator (RG) or radiation isotopes (RI) at institutions using radiation in Korea. Actually, due to radiation exposure occurred on the process of handling RI, etc., The exposure should be maintained as low as reasonably possible. To do this, above all, suitable training and establishment of safety culture have to be preceded. In this respect, an education institution is a place where people learn first about handling radiations in various specialties with purposes including academic research, and the first learned habits and practices acts as the basis for safety management of radiation when they continue to do radiation work after going into the society. Hereford, it is needed to establish the right safety culture on radiation for its safe managing. In the present study, the direction for the right understandings and safety improvement are suggested through the radiation survey on education institutions and preparation of safety guidances for users. The basic guidance at the radiation experiment was prepared for the right understanding of the radiation to prevent radiation accidents from careless handling by workers based on the surveyed results for education institutions. It is expected to be used as fundamentals for improvement for radiation safety management of workers and researchers and, further, safety policy for national nuclear energy and radiations

IRSN - Annual Report 2013. Financial Report 2013. Enhancing nuclear safety

International Nuclear Information System (INIS)

Schuler, Matthieu; Marchal, Valerie; Albert, Marc-Gerard; Aurelle, Jacques; Bigot, Marie-Pierre; Bruna, Giovanni; Charron, Sylvie; Clavelle, Stephanie; Cousinou, Patrick; Deschamps, Patrice; Delattre, Aleth; Demeillers, Didier; Dumas, Agnes; Franquard, Dominique; Laloi, Patrick; Lorthioir, Stephane; Monti, Pascale; Rollinger, Francois; Rouyer, Veronique; Rutschkovsky, Nathalie; Scott De Martinville, Edouard; Tharaud, Christine; Verpeaux, Jean-Luc; Jaunet, Camille; Hedouin, Jean-Christophe; Pascal-Heuze, Charlotte

2014-03-01

IRSN, a public entity with industrial and commercial activities, is placed under the joint authority of the Ministries of Defense, Environment, Industry, Research, and Health. It is the nation's public service expert in nuclear and radiation risks, and its activities cover all the related scientific and technical issues. Its areas of specialization include the environment and radiological emergency response, human radiation protection in both a medical and professional capacity, and in both normal and post-accident situations, the prevention of major accidents, nuclear reactor safety, as well as safety in nuclear plants and laboratories, transport and waste treatment, and nuclear defense and security expertise. IRSN interacts with all parties concerned by these risks (public authorities, in particular nuclear safety and security authorities, local authorities, companies, research organizations, stakeholders' associations, etc.) to contribute to public policy issues relating to nuclear safety, human and environmental protection against ionizing radiation, and the protection of nuclear materials, facilities, and transport against the risk of malicious acts. This document is the 2013 issue of IRSN's activity report. Content: 1 - Organization, key figures; 2 - Strategy: Progress and main activities in 2013, Transparency and communications policy, Promoting a safety and radiation protection culture; 3 - Activities: Safety (Safety of existing facilities, Studies and researches, About defense, Conducting assessments of future facilities); Nuclear security and non-proliferation (Nuclear security activities, International non-proliferation controls); Radiation protection - environment and human health (Environmental and population exposure, Radiation protection in the workplace, Effects of chronic exposure, Protection in health care); Emergency and post-accident situations efficiency; 4 - Efficiency: Health, safety, environmental, protection and quality, Human resources

Knowledge management and networking for enhancing nuclear safety

International Nuclear Information System (INIS)

Taniguchi, T.; Lederman, L.

2004-01-01

Striving for innovative solutions to enhance efficiency of programme delivery and a wider outreach of its nuclear safety activities, the International Atomic Energy Agency (IAEA) has developed an Integrated Safety Approach as a platform for linking its safety related statutory functions and its many associated activities. The approach recognizes the vital importance of effective management of the knowledge base and builds on the integration between the IAEA's safety standards and all aspects of the provision for their application, including peer reviews and technical meetings to share lessons learned. The IAEA is using knowledge management techniques to develop process flows, map safety knowledge and to promote knowledge sharing. The first practical application was the establishment of a knowledge base related to safety aspects of ageing and long-term operation of nuclear power plants. The IAEA is also promoting and facilitating the establishment of regional nuclear and radiation safety networks to preserve existing knowledge and expertise as well as to strengthen sharing and creation of new knowledge in these fields. Prominent examples are the Asian Nuclear Safety Network established in the frame of the IAEA's Programme on the Safety of Nuclear Installations in South East Asia, Pacific and Far East Countries, and the Ibero-American Radiation Safety Network in the frame of the Ibero-American Forum of Nuclear Regulators. Results to date are most encouraging and suggest that this pioneer work should be extended to other regions and eventually to a global nuclear safety network. Responsive to the need of Member States, the IAEA Secretariat has prepared and made available a large number of up-to-date training packages in nuclear, radiation, transport and waste safety, using IAEA safety standards as a basis. It is also providing instruction to trainers in Member States on the use of these modules. This ensures that the material is properly used and that the IAEA

Handling and safety enhancement of race cars using active aerodynamic systems

Science.gov (United States)

Diba, Fereydoon; Barari, Ahmad; Esmailzadeh, Ebrahim

2014-09-01

A methodology is presented in this work that employs the active inverted wings to enhance the road holding by increasing the downward force on the tyres. In the proposed active system, the angles of attack of the vehicle's wings are adjusted by using a real-time controller to increase the road holding and hence improve the vehicle handling. The handling of the race car and safety of the driver are two important concerns in the design of race cars. The handling of a vehicle depends on the dynamic capabilities of the vehicle and also the pneumatic tyres' limitations. The vehicle side-slip angle, as a measure of the vehicle dynamic safety, should be narrowed into an acceptable range. This paper demonstrates that active inverted wings can provide noteworthy dynamic capabilities and enhance the safety features of race cars. Detailed analytical study and formulations of the race car nonlinear model with the airfoils are presented. Computer simulations are carried out to evaluate the performance of the proposed active aerodynamic system.

National plan to enhance aviation safety through human factors improvements

Science.gov (United States)

Foushee, Clay

1990-01-01

The purpose of this section of the plan is to establish a development and implementation strategy plan for improving safety and efficiency in the Air Traffic Control (ATC) system. These improvements will be achieved through the proper applications of human factors considerations to the present and future systems. The program will have four basic goals: (1) prepare for the future system through proper hiring and training; (2) develop a controller work station team concept (managing human errors); (3) understand and address the human factors implications of negative system results; and (4) define the proper division of responsibilities and interactions between the human and the machine in ATC systems. This plan addresses six program elements which together address the overall purpose. The six program elements are: (1) determine principles of human-centered automation that will enhance aviation safety and the efficiency of the air traffic controller; (2) provide new and/or enhanced methods and techniques to measure, assess, and improve human performance in the ATC environment; (3) determine system needs and methods for information transfer between and within controller teams and between controller teams and the cockpit; (4) determine how new controller work station technology can optimally be applied and integrated to enhance safety and efficiency; (5) assess training needs and develop improved techniques and strategies for selection, training, and evaluation of controllers; and (6) develop standards, methods, and procedures for the certification and validation of human engineering in the design, testing, and implementation of any hardware or software system element which affects information flow to or from the human.

Direct-acting antiviral agent efficacy and safety in renal transplant recipients with chronic hepatitis C virus infection

OpenAIRE

Chen, Keliang; Lu, Pei; Song, Rijin; Zhang, Jiexiu; Tao, Rongzhen; Wang, Zijie; Zhang, Wei; Gu, Min

2017-01-01

Abstract Background: The efficacy and safety of direct-acting antivirals (DAAs) for treating hepatitis C virus (HCV)-infected renal transplant recipients (RTRs) has not been determined. Methods: We searched PubMed, Embase, and the Cochrane Central Register of Controlled Trials and assessed the quality of eligible studies using the Joanna Briggs Institute scale. DAA efficacy and safety were assessed using standard mean difference (SMD) with 95% confidence intervals (95%CIs). Results: Six studi...

76 FR 79192 - Patient Safety Organizations: Voluntary Relinquishment From HSMS Patient Safety Organization

Science.gov (United States)

2011-12-21

... Organizations: Voluntary Relinquishment From HSMS Patient Safety Organization AGENCY: Agency for Healthcare... voluntary relinquishment from the HSMS Patient Safety Organization of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109...

Enhancing Road Safety Behaviour Using a Psychological and Spiritual Approaches

Directory of Open Access Journals (Sweden)

Ghous Mohd Tarmizi

2017-01-01

Full Text Available Main causes of accident is due to driver itself that is influenced by their bad attitude while driving. Human attitude is closely related to the human psychology. Apart from that, spiritual aspect also influence human attitude. Hence, this study carried out to improve driver safety using a new approach through psychology and spiritual factors. Objectives of this study are to identify then analyze factors of psychological and spiritual that contribute towards safety driving. A self-administered questionnaire were distributed among 256 respondents from various type of background. An analysis descriptive statistics show demographic and experience of respondents. Chi-square analysis showed only education level and traffic summon are significant to safety driving. Furthermore, correlation analysis shows psychological factors has strong linear relationship on attitude of drivers towards safety driving while spiritual factor, the perception of the spiritual and practices, both have a strong relationship to safety driving. Regression analysis demonstrates boths psychological and spiritual factors have strong evidence and significant relationship with safety driving. Thus, it can be identified that spiritual psychological factors encourage drivers to drive more safely and reduce road accidents. Therefore, this study propose useful guidelines to related agencies in order to enhance safety among drivers to be able drive safely on the road.

S. 1958: This Act may be cited as the Nuclear Facilities Occupational Safety Improvement Act of 1989. Introduced in the Senate of the United States, One Hundredth First Congress, First Session, November 21, 1989

International Nuclear Information System (INIS)

Anon.

1989-01-01

S. 1958 is a bill to amend the Occupational Safety and Health Act of 1970 to improve and enforce standards for employee health and safety at Department of Energy nuclear facilities, and for other purposes

Engineering and Safety Partnership Enhances Safety of the Space Shuttle Program (SSP)

Science.gov (United States)

Duarte, Alberto

2007-01-01

difference for the safety of the Space Shuttle Vehicle, its crew, and personnel. Because of the MSERP's valuable contribution to the assessment of safety risk for the SSP, this paper also proposes an enhanced Panel concept that takes this successful partnership concept to a higher level of 'true partnership'. The proposed panel is aimed to be responsible for the review and assessment of all risk relative to Safety for new and future aerospace and related programs.

Public safety investigations-A new evolutionary step in safety enhancement?

International Nuclear Information System (INIS)

Stoop, John; Roed-Larsen, Sverre

2009-01-01

A historical overview highlights the evolutionary nature of developments in accident investigations in the transport industry. Based on a series of major events outside transportation, the concept of accident investigations has broadened to other domains and to a widening of the scope of the investigation. Consequently, existing investigation boards are forced to adapt their mandates, missions and methods. With the introduction of social risk perception and application of the concept of safety investigation in the public sector, a change of focus towards the aftermath and non-technical issues of a more generic nature emerges. This expansion has also gained the interest of social sciences and public governance, generating new underlying models and theories on risk and responsibility. The evolutionary development of safety investigations is demonstrated by the various organisational forms which shaped accident investigations in different countries. Underneath these organisational differences, a need for a common methodology and a reflection on fundamental notions is discussed. In particular differences among human operator models, the allocation of responsibilities in design concepts and methodological issue are elaborated. The needs and opportunities for a transition from accident prevention towards systems change are indicated. At present, the situation is ambiguous. An encompassing inventory can only provide a general oversight over emerging trends and lacks analytic rigor on specific topics. The societal dimensions, institutional changes at the level of governance and control and the powers that advocate or challenge investigations are not yet fully described. Therefore, in the conclusions a small number of critical challenges and threats are identified that should be open to scrutiny in order to facilitate a new, evolutionary step in safety enhancement.

Statutory Instrument No. 1439 (C.26) The Health and Safety at Work etc. Act 1974 (Commencement No.1) Order 1974

International Nuclear Information System (INIS)

1974-01-01

This Order brings into operation progressively Parts I, II and IV of the Safety at Work etc. Act of 31 July 1974. Certain provisions entered into force as from 1 October 1974 and the remainder as from 1 April 1974; the provisions respectively relate to the establishment and functions of the Health and Safety Commission, the Health and Safety Executive and the general duties of employers. (NEA) [fr

Nicotine disrupts safety learning by enhancing fear associated with a safety cue via the dorsal hippocampus.

Science.gov (United States)

Connor, David A; Kutlu, Munir G; Gould, Thomas J

2017-07-01

Learned safety, a learning process in which a cue becomes associated with the absence of threat, is disrupted in individuals with post-traumatic stress disorder (PTSD). A bi-directional relationship exists between smoking and PTSD and one potential explanation is that nicotine-associated changes in cognition facilitate PTSD emotional dysregulation by disrupting safety associations. Therefore, we investigated whether nicotine would disrupt learned safety by enhancing fear associated with a safety cue. In the present study, C57BL/6 mice were administered acute or chronic nicotine and trained over three days in a differential backward trace conditioning paradigm consisting of five trials of a forward conditioned stimulus (CS)+ (Light) co-terminating with a footshock unconditioned stimulus followed by a backward CS- (Tone) presented 20 s after cessation of the unconditioned stimulus. Summation testing found that acute nicotine disrupted learned safety, but chronic nicotine had no effect. Another group of animals administered acute nicotine showed fear when presented with the backward CS (Light) alone, indicating the formation of a maladaptive fear association with the backward CS. Finally, we investigated the brain regions involved by administering nicotine directly into the dorsal hippocampus, ventral hippocampus, and prelimbic cortex. Infusion of nicotine into the dorsal hippocampus disrupted safety learning.

The House of Commons of Canada, Bill C-23 : An act to establish the Canadian Nuclear Safety Commission and to make consequential amendments to other acts

International Nuclear Information System (INIS)

1996-01-01

This enactment replaces the Atomic Energy Control Act with a modern statute to provide for more explicit and effective regulation of nuclear energy. While the existing Act encompasses both the regulatory and developmental aspects of nuclear activities, this enactment disconnects the two functions and provides a distinct identity to the regulatory agency. It replaces the Atomic Energy Control Board with the Canadian Nuclear Safety Commission, underlining its separate role from that of Atomic Energy of Canada Ltd., the federal research, development and marketing organization for nuclear energy

Enhancement of safety at nuclear facilities in Pakistan

International Nuclear Information System (INIS)

Ahmad, S.A.; Hayat, T.; Azhar, W.

2006-01-01

Pakistan is benefiting from nuclear technology mostly in health and energy sectors as well as agriculture and industry and has an impeccable safety record. At the national level uses of nuclear technology started in 1955 resulting in the operation of Karachi Radioisotope Center, Karachi, in December 1960. Pakistan Nuclear Safety Committee (PNSC) was formulated in 1964 with subsequent promulgation of Pakistan Atomic Energy Commission (PAEC) Ordinance in 1965 to cope with the anticipated introduction of a research reactor, namely PARR-I, and a nuclear power plant, namely KANUPP. Since then Pakistan's nuclear program has expanded to include numerous nuclear facilities of varied nature. This program has definite economic and social impacts by producing electricity, treating and diagnosing cancer patients, and introducing better crop varieties. Appropriate radiation protection includes a number of measures including database of sealed radiation sources at PAEC operated nuclear facilities, see Table l, updated during periodic physical verification of these sources, strict adherence to the BSS-115, IAEA recommended enforcement of zoning at research reactors and NPPs, etc. Pakistan is party to several international conventions and treaties, such as Convention of Nuclear Safety and Early Notification, to improve and enhance safety at its nuclear facilities. In addition Pakistan generally and PAEC particularly believes in a blend of prudent regulations and good/best practices. This is described in this paper. (Author)

An Evaluation Method for Team Competencies to Enhance Nuclear Safety Culture

International Nuclear Information System (INIS)

Hang, S. M.; Seong, P. H.; Kim, A. R.

2016-01-01

Safety culture has received attention in safety-critical industries, including nuclear power plants (NPPs), due to various prominent accidents such as concealment of a Station Blackout (SBO) of Kori NPP unit 1 in 2012, the Sewol ferry accident in 2014, and the Chernobyl accident in 1986. Analysis reports have pointed out that one of the major contributors to the cause of the accidents is ‘the lack of safety culture’. The term, nuclear safety culture, was firstly defined after the Chernobyl accident by the IAEA in INSAG report no. 4, as follows “Safety culture is that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention warranted their significance.” Afterwards, a wide consensus grew among researchers and nuclear-related organizations, that safety culture should be evaluated and managed in a certain manner. Consequently, each nuclear-related organization defined and developed their own safety culture definitions and assessment methods. However, none of these methods provides a way for an individual or a team to enhance the safety culture of an organization. Especially for a team, which is the smallest working unit in NPPs, team members easily overlook their required practices to improve nuclear safety culture. Therefore in this study, we suggested a method to estimate nuclear safety culture of a team, by approaching with the ‘competency’ point of view. The competency is commonly focused on individuals, and defined as, “underlying characteristics of an individual that are causally related to effective or superior performance in a job.” Similar to safety culture, the definition of competency focuses on characteristics and attitudes of individuals. Thus, we defined ‘safety culture competency’ as “underlying characteristics and outward attitudes of individuals that are causally related to a healthy and strong nuclear safety

The Implementation of the Food Safety Modernization Act and the Strength of the Sustainable Agriculture Movement.

Science.gov (United States)

Wiseman, Samuel R

2015-01-01

In the wake of growing public concerns over salmonella outbreaks and other highly publicized food safety issues, Congress passed the FDA Food Safety Modernization Act in 2011, which placed more stringent standards on food growing and packaging operations. In negotiations preceding the Act's passage, farmers of local, sustainable food argued that these rules would unduly burden local agricultural operations or, at the extreme, drive them out of business by creating overly burdensome rules. These objections culminated in the addition of the Tester-Hagan Amendment to the Food Safety Modernization Act, which created certain exemptions for small farms. Proposed Food and Drug Administration (FDA) rules to implement the Act threatened to weaken this victory for small farm groups, however, prompting a loud response from small farmers and local food proponents. The FDA's second set of proposed rules, issued in September 2014 in response to these and other complaints, were, perhaps surprisingly, responsive to small farmers' concerns. Using comments submitted to the FDA, this article explores the responses of the agriculture industry and public health organizations, as well as small farm groups, consumers of local food, and sustainable agriculture interests (which, for simplicity, I alternately describe as comprising the "sustainable agriculture" or "small farm" movement), to three aspects of the FDA's proposed rules--involving manure application, on-farm packing activities, and exemptions for very small farms--to assess the strength of the sustainable agriculture movement. The rules involving manure application and on-farm packing, it turns out, reveal little about the independent political strength of the local food movement, as large industry groups also objected to these provisions. But for the third issue discussed here--exemptions for very small farms--the interests of sustainable agriculture groups were directly opposed to both industry and public health organizations

Slovak Republic Act No. 124/2006 Coll. of 2 February 2006 on safety and health at work and amending some laws

International Nuclear Information System (INIS)

2006-01-01

This Act establishes the general principles of prevention and basic conditions for ensuring safety and health at work and to eliminate the risk factors and conditioning the occurrence of occupational accidents, occupational diseases and other health damage. This Act came into force on July 1, 2006.

Farm Safety - Time to Act.

Science.gov (United States)

Lower, Tony; Temperley, John

2018-04-18

Agriculture is recognised as a highly dangerous sector worldwide, hence the use of evidence-based solutions to address injury related incidents are critical to prevention. The main of this paper is to determine the potential for prevention by use of existing controls based on deaths data from 2001-2016. This study assesses data from the National Coroner's Information System for the period 2001-2016 in regards to unintentional farm injury deaths in Australia (n = 1,271). The six leading causes of death (tractors, quads (ATVs), water/dams, farm utilities (pickups), motorcycles and horses: n=644), are reviewed against existing evidence-based practice recommendations to ascertain the potential capacity to prevent and/or ameliorate the severity of the fatal incidents. Projections of economic costs associated with these incidents in the past five years (2012-2016) are outlined. Of the cases involving the six leading agents (n=644), 36% (n=235) have the potential to be prevented with the use of designated evidence-based controls. Meanwhile the costs attributed to deaths involving the six leading agents in the 2012-2016 period, exceeded AU$313 million. Farm injury incidents and their related economic costs, can be reduced by enhanced adoption of the existing evidence-based controls. SO WHAT?: Farm safety efforts in Australia require re-invigoration and funding to focus on evidence-based controls supported by enforcement to attain maximum impact. This article is protected by copyright. All rights reserved. This article is protected by copyright. All rights reserved.

IAEA Sees Safety Commitment at Spain’s Almaraz Nuclear Power Plant, Areas for Enhancement

International Nuclear Information System (INIS)

2018-01-01

An International Atomic Energy Agency (IAEA) team of experts said the operator of Spain’s Almaraz Nuclear Power Plant demonstrated a commitment to the long-term safety of the plant and noted several good practices to share with the nuclear industry globally. The team also identified areas for further enhancement. The Operational Safety Review Team (OSART) today concluded an 18-day mission to Almaraz, whose two 1,050-MWe pressurized-water reactors started commercial operation in 1983 and 1984, respectively. Centrales Nucleares Almaraz-Trillo (CNAT) operates the plant, located about 200 km southwest of Madrid. OSART missions aim to improve operational safety by objectively assessing safety performance using the IAEA’s safety standards and proposing recommendations for improvement where appropriate. Nuclear power generates more than 21 per cent of electricity in Spain, whose seven operating power reactors all began operation in the 1980s.The mission made a number of recommendations to improve operational safety, including: • The plant should implement further actions related to management, staff and contractors to enforce standards and expectations related to industrial safety. • The plant should take measures to reinforce and implement standards to enhance the performance of reactivity manipulations in a deliberate and carefully-controlled manner. • The plant should improve the support, training and documented guidance for Severe Accident Management Guideline users in order to mitigate complex severe accident scenarios. The team provided a draft report of the mission to the plant’s management. The plant management and the Nuclear Safety Council (CSN), which is responsible for nuclear safety oversight in Spain, will have the opportunity to make factual comments on the draft. These will be reviewed by the IAEA and the final report will be submitted to the Government of Spain within three months. The plant management said it would address the areas

Occurrence of lead-related symptoms below the current occupational safety and health act allowable blood lead levels.

Science.gov (United States)

Rosenman, Kenneth D; Sims, Amy; Luo, Zhehui; Gardiner, Joseph

2003-05-01

To determine the occurrence of symptoms of lead toxicity at levels below the current allowable Occupational Safety and Health Act blood lead level of 50 micrograms/dL, standardized telephone interviews were conducted of individuals reported to a statewide laboratory-based surveillance system. Four hundred and ninety-seven, or 75%, of the eligible participants were interviewed. Gastrointestinal, musculoskeletal, and nervous system symptoms increased with increasing blood lead levels. Nervous, gastrointestinal, and musculoskeletal symptoms all began to be increased in individuals with blood leads between 30-39 micrograms/dL and possibly at levels as low as 25-30 micrograms/dL for nervous system symptoms. The results of this study of increased symptoms are consistent with and provide added weight to previous results showing subclinical changes in the neurologic and renal systems and sperm counts at blood lead levels currently allowed by the Occupational Safety and Health Act.

1984 Act on nuclear activities (1984:3)

International Nuclear Information System (INIS)

1984-01-01

This 1984 Act on Nuclear Activities (1984:3) replaces the 1956 Atomic Energy Act as well as the 1977 Act on special permits to charge nuclear reactors with nuclear fuel and the 1980 Act on Public Insight into the Safety Work at Nuclear Power Plants. Like the 1956 Act, the 1984 Act in a safety legislation, which is based on a system of licensing conditions and supervision. According to the fundamental provisions of the 1984 Act, nuclear activities should be conducted in such a way as to meet safety requirements and fulfil the obligations that follow from Sweden's international agreements for the purpose of preventing the proliferation of nuclear weapons. (NEA) [fr

Enhanced FAA-hybrid III numerical dummy model in Madymo for aircraft occupant safety assessment

NARCIS (Netherlands)

Boucher, H.; Waagmeester, C.D.

2003-01-01

To improve survivability and to minimize the risk of injury to occupants in helicopter crash events, a complete Cabin Safety System concept including safety features and an enhanced FAA-Hybrid III dummy were developed within the HeliSafe project. A numerical tool was also created and validated to

Use of a web site to enhance criticality safety training

International Nuclear Information System (INIS)

Huang, Song T.; Morman, James A.

2003-01-01

Establishment of the NCSP (Nuclear Criticality Safety Program) website represents one attempt by the NCS (Nuclear Criticality Safety) community to meet the need to enhance communication and disseminate NCS information to a wider audience. With the aging work force in this important technical field, there is a common recognition of the need to capture the corporate knowledge of these people and provide an easily accessible, web-based training opportunity to those people just entering the field of criticality safety. A multimedia-based site can provide a wide range of possibilities for criticality safety training. Training modules could range from simple text-based material, similar to the NCSET (Nuclear Criticality Safety Engineer Training) modules, to interactive web-based training classes, to video lecture series. For example, the Los Alamos National Laboratory video series of interviews with pioneers of criticality safety could easily be incorporated into training modules. Obviously, the development of such a program depends largely upon the need and participation of experts who share the same vision and enthusiasm of training the next generation of criticality safety engineers. The NCSP website is just one example of the potential benefits that web-based training can offer. You are encouraged to browse the NCSP website at http://ncsp.llnl.gov. We solicit your ideas in the training of future NCS engineers and welcome your participation with us in developing future multimedia training modules. (author)

An analysis of the FDA Food Safety Modernization Act: protection for consumers and boon for business.

Science.gov (United States)

Strauss, Debra M

2011-01-01

This article analyzes components of the FDA Food Safety Modernization Act, which was prompted by incidents of food contamination, exploring the history of its passage and explaining its significance, as well as its limitations. As the first time in 70 years that food law has been changed substantially, this new law represents only an initial but significant step in the direction of improving food safety. With bipartisan support from both Congress and the President, this legislation embodies a mandate that food safety is at this moment becoming a priority. As a result, the time is ripe for a reassessment of other areas of food laws--particularly genetically modified foods and the use of milk and meat from cloned animals and their progeny--which are allowed under current U.S. law with no labeling, preapprovals, or post-market monitoring. These areas warrant special regulation consistent with the new proactive policy towards securing the safety of the food supply.

Electronuclear's safety culture assessment and enhancement program

International Nuclear Information System (INIS)

Selvatici, E.; Diaz-Francisco, J.M.; Diniz de Souza, V.

2002-01-01

The present paper describes the Eletronuclear's safety culture assessment and enhancement program. The program was launched by the company's top management one year after the creation of Eletronuclear in 1997, from the merging of two companies with different organizational cultures, the design and engineering company Nuclen and the nuclear directorate of the Utility Furnas, Operator of the Angra1 NPP. The program consisted of an assessment performed internally in 1999 with the support and advice of the IAEA. This assessment, performed with the help of a survey, pooled about 80% of the company's employees. The overall result of the assessment was that a satisfactory level of safety culture existed; however, a number of points with a considerable margin for improvement were also identified. These points were mostly related with behavioural matters such as motivation, stress in the workplace, view of mistakes, handling of conflicts, and last but not least a view by a considerable number of employees that a conflict between safety and production might exist. An Action Plan was established by the company managers to tackle these weak points. This Plan was issued as company guideline by the company's Directorate. The subsequent step was to detail and implement the different actions of the Plan, which is the phase that we are at present. In the detailing of the Action Plan, special care was taken to sum up efforts, avoiding duplication of work or competition with already existing programs. In this process it was identified that the company had a considerable number of initiatives directly related to organizational and safety culture improvement, already operational. These initiatives have been integrated in the detailed Action Plan. A new assessment, for checking the effectiveness of the undertaken actions, is planned for 2003. (author)

The Role of OSHA in Safety and Health. Module SH-02. Safety and Health.

Science.gov (United States)

Center for Occupational Research and Development, Inc., Waco, TX.

This student module on the role of OSHA (Occupational Safety and Health Act) in Safety and Health is one of 50 modules concerned with job safety and health. This module looks at the OSHA Act, its aims, and the rights and responsibilities of employers and workers under the Act. Following the introduction, 16 objectives (each keyed to a page in the…

Food safety security: a new concept for enhancing food safety measures.

Science.gov (United States)

Iyengar, Venkatesh; Elmadfa, Ibrahim

2012-06-01

The food safety security (FSS) concept is perceived as an early warning system for minimizing food safety (FS) breaches, and it functions in conjunction with existing FS measures. Essentially, the function of FS and FSS measures can be visualized in two parts: (i) the FS preventive measures as actions taken at the stem level, and (ii) the FSS interventions as actions taken at the root level, to enhance the impact of the implemented safety steps. In practice, along with FS, FSS also draws its support from (i) legislative directives and regulatory measures for enforcing verifiable, timely, and effective compliance; (ii) measurement systems in place for sustained quality assurance; and (iii) shared responsibility to ensure cohesion among all the stakeholders namely, policy makers, regulators, food producers, processors and distributors, and consumers. However, the functional framework of FSS differs from that of FS by way of: (i) retooling the vulnerable segments of the preventive features of existing FS measures; (ii) fine-tuning response systems to efficiently preempt the FS breaches; (iii) building a long-term nutrient and toxicant surveillance network based on validated measurement systems functioning in real time; (iv) focusing on crisp, clear, and correct communication that resonates among all the stakeholders; and (v) developing inter-disciplinary human resources to meet ever-increasing FS challenges. Important determinants of FSS include: (i) strengthening international dialogue for refining regulatory reforms and addressing emerging risks; (ii) developing innovative and strategic action points for intervention {in addition to Hazard Analysis and Critical Control Points (HACCP) procedures]; and (iii) introducing additional science-based tools such as metrology-based measurement systems.

RAF/9/049: Enhancing and Sustaining the National Regulatory Bodies for safety

International Nuclear Information System (INIS)

Keter, C.J.

2017-01-01

The main objective of this project is to enhance regulatory infrastructure, sustainability and cooperation among national regulatory bodies. This will support strengthening of the existing regulatory framework and capacity building in the region. Self-Assessment using the Self-Assessment Regulatory Infrastructure for Safety (SARIS) was completed on 26th May 2016. Changes made to the legislation is ongoing. The Nuclear Regulatory Bill 2017 is at an advanced stage and about to be tabled to Cabinet. The project objectives shall be addressed under a new project, RAF/9/058 – Improving the Regulatory Framework for the Control of Radiation Sources in Member States. Two major tasks for Kenya to focus include Review of regulations on waste safety, radiation sources and on safety of NPP and advising on drafting of radiation safety guides

Enhanced Maritime Safety through Diagnosis and Fault Tolerant Control

DEFF Research Database (Denmark)

Blanke, Mogens

2001-01-01

Faults in steering, navigation instruments or propulsion machinery are serious on a marine vessel since the consequence could be loss of maneuvering ability, and imply risk of damage to vessel personnel or environment. Early diagnosis and accomodation of faults could enhance safety. Fault...... of properties of a falty system; means to determine remedial actions. The paper illustrates the techniques by two marine examples, sensor fusion for automatic steering and control of the main engine....

Effective corrective actions to enhance operational safety of nuclear installations

International Nuclear Information System (INIS)

2005-07-01

The safe operation of nuclear power plants around the world and the prevention of incidents in these installations remain key concerns for the nuclear community. In this connection the feedback of operating experience plays a major role: every nuclear plant operator needs to have a system in place to identify and feed back the lessons learned from operating experience and to implement effective corrective actions to prevent safety events from reoccurring. An effective operating experience programme also includes a proactive approach that is aimed at preventing the first-time occurrence of safety events. In April 2003, the IAEA issued the PROSPER guidelines for nuclear installations to strengthen and enhance their own operating experience process and for self-assessment on the effectiveness of the feedback process. Subsequently, in the course of the Operational Safety Review Teams missions conducted by the IAEA that focused on the operational safety practices of nuclear power plants, the IAEA enhanced the review of the operating experience in nuclear power plants by implementing a new module that is derived from these guidelines. In order to highlight the effective implementation of the operating experience programme and to provide practical assistance in this area, the IAEA organized workshops and conferences to discuss recent trends in operating experience. The IAEA also performed assistance and review missions at plants and corporate organizations. The IAEA is further developing advice and assistance on operating experience feedback programmes and is reporting on good practices. The present publication is the outcome of two years of coordinated effort involving the participation of experts of nuclear organizations in several Member States. It provides information and good practices for successfully establishing an effective corrective actions programme. This publication forms part of a series that develops the principles set forth in these guidelines

Enhancing the safety of elderly victims after the close of an APS investigation.

Science.gov (United States)

Jackson, Shelly L; Hafemeister, Thomas L

2013-04-01

The purpose of this study was to test whether particular actions on the part of adult protective services (APS), the elderly victim, and/or society's response to abusive individuals, are associated with the continuation of abuse after the close of an APS investigation and thereby compromise victim safety. Interviews were conducted with 71 APS caseworkers, 55 of the elderly victims of substantiated abuse, and 35 third-party persons. A small proportion of elderly victims continue to experience abuse after the close of an APS investigation. Elderly victims were more likely to experience continued abuse when they chose to have ongoing contact with their abusers, vis-à-vis cohabitation or otherwise, and when their abusers experienced no consequences. Although continuation of abuse did not differ by the type of maltreatment involved, reasons for the cessation of abuse, and other safety indicators, did. To enhance victim safety, greater monitoring may be warranted in cases wherein elderly victims continue to have contact with their abuser and when abusive individuals experience no consequences. To further enhance victim safety, abusive individuals must be incorporated into an overall strategic response to elder abuse. A potential avenue for facilitating victim safety while maintaining victim autonomy is to understand their motivations for desiring continued contact with their abuser and developing interventions based upon such knowledge.

Use of a Web Site to Enhance Criticality Safety Training

International Nuclear Information System (INIS)

Huang, S T; Morman, J

2003-01-01

Currently, a website dedicated to enhancing communication and dissemination of criticality safety information is sponsored by the U.S. Department of Energy (DOE) Nuclear Criticality Safety Program (NCSP). This website was developed as part of the DOE response to the Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 97-2, which reflected the need to make criticality safety information available to a wide audience. The website is the focal point for DOE nuclear criticality safety (NCS) activities, resources and references, including hyperlinks to other sites actively involved in the collection and dissemination of criticality safety information. The website is maintained by the Lawrence Livermore National Laboratory (LLNL) under auspices of the NCSP management. One area of the website contains a series of Nuclear Criticality Safety Engineer Training (NCSET) modules. During the past few years, many users worldwide have accessed the NCSET section of the NCSP website and have downloaded the training modules as an aid for their training programs. This trend was remarkable in that it points out a continuing need of the criticality safety community across the globe. It has long been recognized that training of criticality safety professionals is a continuing process involving both knowledge-based training and experience-based operations floor training. As more of the experienced criticality safety professionals reach retirement age, the opportunities for mentoring programs are reduced. It is essential that some method be provided to assist the training of young criticality safety professionals to replenish this limited human expert resource to support on-going and future nuclear operations. The main objective of this paper is to present the features of the NCSP website, including its mission, contents, and most importantly its use for the dissemination of training modules to the criticality safety community. We will discuss lessons learned and several ideas

78 FR 12065 - Patient Safety Organizations: Delisting for Cause for Independent Data Safety Monitoring, Inc.

Science.gov (United States)

2013-02-21

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Safety Monitoring, Inc. due to its failure to correct a deficiency. The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act) authorizes the listing of PSOs, which are entities or component...

Implementation of an Enhanced Measurement Control Program for handling nuclear safety samples at WSRC

International Nuclear Information System (INIS)

Boler-Melton, C.; Holland, M.K.

1991-01-01

In the separation and purification of nuclear material, nuclear criticality safety (NCS) is of primary concern. The primary nuclear criticality safety controls utilized by the Savannah River Site (SRS) Separations Facilities involve administrative and process equipment controls. Additional assurance of NCS is obtained by identifying key process hold points where sampling is used to independently verify the effectiveness of production control. Nuclear safety measurements of samples from these key process locations provide a high degree of assurance that processing conditions are within administrative and procedural nuclear safety controls. An enhanced procedure management system aimed at making improvements in the quality, safety, and conduct of operation was implemented for Nuclear Safety Sample (NSS) receipt, analysis, and reporting. All procedures with nuclear safety implications were reviewed for accuracy and adequate detail to perform the analytical measurements safely, efficiently, and with the utmost quality. Laboratory personnel worked in a ''Deliberate Operating'' mode (a systematic process requiring continuous expert oversight during all phases of training, testing, and implementation) to initiate the upgrades. Thus, the effort to revise and review nuclear safety sample procedures involved a team comprised of a supervisor, chemist, and two technicians for each procedure. Each NSS procedure was upgraded to a ''Use Every Time'' (UET) procedure with sign-off steps to ensure compliance with each step for every nuclear safety sample analyzed. The upgrade program met and exceeded both the long and short term customer needs by improving measurement reliability, providing objective evidence of rigid adherence to program principles and requirements, and enhancing the system for independent verification of representative sampling from designated NCS points

S. 1802: This Act may be referred to as the Department of Energy Nuclear Facilities of Act of 1989. Introduced in the Senate of the United States, One Hundredth First Congress, First Session, October 26, 1989

International Nuclear Information System (INIS)

Anon.

1989-01-01

This bill would enhance nuclear safety at Department of Energy nuclear facilities, apply the provisions of the Occupational, Health, and Safety Act to certain Department of Energy nuclear facilities, encourage independent research on the effects of radiation on human beings, establish a comprehensive program within the Department of Energy of research, development, and demonstration of methods for waste cleanup and remediation, and establish a process for ensuring cleanup of Department of Energy nuclear facilities

Approach to design of future FBRs with enhanced safety and economy

International Nuclear Information System (INIS)

Raghupathy, S.; Balasubramaniyan, V.; Puthiyavinayagam, P.; Selvaraj, P.; Chellapandi, P.; Chetal, S.C.; Raj, Baldev

2009-01-01

After the techno economic demonstration of FBR technology through PFBR, it is essential to achieve high economic competitiveness with enhanced safety on par with other power generation options. Towards this, design studies were made with the objectives of identifying means to achieve enhanced safety, design features for improving economy, conceptualise the plant layout, ways to reduce construction time and to achieve higher capacity factor. This paper describes the outcome of the above studies and the approach to the design of future FBRs with enhanced safety and economy. High economic competitiveness and public acceptance are essential for commercial deployment of fast reactors. India has a well-laid out three phase nuclear power programme with Pressurised Heavy Water Reactors (PHWRs) utilizing natural uranium as fuel in the first phase and fast breeder reactors (FBRs) using plutonium and thorium in the second and third phases. Deploying FBRs on a commercial scale is vital for India in order to utilize the vast thorium reserves and to meet the long term energy needs of the country. As a first step, a 40 MWt, 13.5 MWe Fast Breeder Test Reactor (FBTR) was constructed and has been in operation since 1985. Operation of FBTR has given valuable operating experience with critical systems of FBRs including sodium systems and has given confidence to undertake the design of 500 MWe Prototype Fast Breeder Reactor (PFBR). Construction of PFBR is currently under progress and is expected to be completed by 2010. It is planned to construct four more oxide fuelled FBRs of 500 MWe capacity by 2020 and metal fuelled FBRs of 1000 MWe thereafter. Enhanced safety is proposed to be achieved through improvements in shut down systems, adopting in-vessel primary sodium purification concept, improving the reliability of decay heat removal system, shifting component decontamination activities to a separate building located outside the reactor containment building, providing additional

Outline of the Fukushima Daiichi Accident. Lessons Learned and Safety Enhancements

Directory of Open Access Journals (Sweden)

Hirano Masashi

2017-01-01

This paper briefly presents the outline of the Fukushima Daiichi accident and summarizes the major lessons learned having been drawn and safety enhancements having been done in Japan for the purpose of giving inputs to the discussions to be taken place in the Special Invited Session “Fukushima, 5 years after”.

Facilities management and industrial safety

International Nuclear Information System (INIS)

2003-06-01

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

New developments enhancing MCNP for criticality safety

International Nuclear Information System (INIS)

Hendricks, J.S.; McKinney, G.W.; Forster, R.A.

1993-01-01

Since the early 80's MCNP has had three estimates of k eff : collision, absorption, and track length. MCNP has also had collision and absorption estimators of removal lifetime. These are calculated for every cycle and are averaged over the cycles as simple averages and covariance weighted averages. Correlation coefficients between estimators are also calculated. These criticality estimators are all in addition to the extensive summary information and tally edits used in shielding and other problems. A number of significant new developments have been made to enhance the MCNP Monte Carlo radiation transport code for criticality safety applications. These are available in the newly released MCNP4A version of the code

INPO Perspectives and Activities to Enhance Supplier Human Performance and Safety Culture

International Nuclear Information System (INIS)

Duncan, R. J.

2016-01-01

Within their own organizations, utilities have made significant improvements in human performance and safety culture, supported by a strong community of practice through INPO and WANO. In recent years, utilities have been making increasing use of suppliers for design, construction, inspection and maintenance services in support of their NPPs. Many of these suppliers do not have the benefit of being members of a community of practice when it comes to human performance and safety culture. To help the supplier community make improvements similar to what the utilities have achieved, INPO has recently expanded its Supplier Participant program to address the issue of human performance and safety culture in the supplier community. The intent of this paper will be to share the INPO’s perspectives and activities in helping suppliers of services and products to NPPs enhance their human performance and safety culture. (author)

4th ASEM Seminar on Knowledge Management to Enhance Nuclear Safety

International Nuclear Information System (INIS)

Castello, F.; Reyes, A. de los; Sobari, M. P. Mohd; Istiyanto, J. E.; Faross, P.; Delarosa, A.

2016-01-01

Full text: The 4th Asia-Europe Meeting (ASEM) Seminar on Nuclear Safety was convened in Madrid, Spain on 29th–30th October 2015, hosted by the Spanish Nuclear Safety Council. The seminar’s theme was “Knowledge management to enhance nuclear safety”, which aimed to continue discussing on nuclear safety to foster Asia-Europe capacity-building and cooperation in nuclear safety. The seminar was attended by representatives from national governments, nuclear regulators, energy companies, radiation protection and nuclear safety authorities, research institutes and universities. According to such model, proposed by the IAEA, the national capacity building requires an integrated approach based on four pillars: human resources development, education and training, knowledge management and knowledge networking. In this context, Nuclear Knowledge Management (KM) has become a high priority in many countries and international organizations and it has been taken into account to develop and implement specific strategies in ensuring safe and sustainable operation of nuclear facilities. At national level, a sustainable approach should include the necessary Nuclear Knowledge Management actions to ensure that every actor having a significant role in the national nuclear programmes infrastructure acquires, preserves and improves its corporate and individual knowledge. (author

The HIV1 protein Vpr acts to enhance constitutive DCAF1-dependent UNG2 turnover.

Directory of Open Access Journals (Sweden)

Xiaoyun Wen

Full Text Available The HIV1 protein Vpr assembles with and acts through an ubiquitin ligase complex that includes DDB1 and cullin 4 (CRL4 to cause G2 cell cycle arrest and to promote degradation of both uracil DNA glycosylase 2 (UNG2 and single-strand selective mono-functional uracil DNA glycosylase 1 (SMUG1. DCAF1, an adaptor protein, is required for Vpr-mediated G2 arrest through the ubiquitin ligase complex. In work described here, we used UNG2 as a model substrate to study how Vpr acts through the ubiquitin ligase complex. We examined whether DCAF1 is essential for Vpr-mediated degradation of UNG2 and SMUG1. We further investigated whether Vpr is required for recruiting substrates to the ubiquitin ligase or acts to enhance its function and whether this parallels Vpr-mediated G2 arrest.We found that DCAF1 plays an important role in Vpr-independent UNG2 and SMUG1 depletion. UNG2 assembled with the ubiquitin ligase complex in the absence of Vpr, but Vpr enhanced this interaction. Further, Vpr-mediated enhancement of UNG2 degradation correlated with low Vpr expression levels. Vpr concentrations exceeding a threshold blocked UNG2 depletion and enhanced its accumulation in the cell nucleus. A similar dose-dependent trend was seen for Vpr-mediated cell cycle arrest.This work identifies UNG2 and SMUG1 as novel targets for CRL4(DCAF1-mediated degradation. It further shows that Vpr enhances rather than enables the interaction between UNG2 and the ubiquitin ligase. Vpr augments CRL4(DCAF1-mediated UNG2 degradation at low concentrations but antagonizes it at high concentrations, allowing nuclear accumulation of UNG2. Further, the protein that is targeted to cause G2 arrest behaves much like UNG2. Our findings provide the basis for determining whether the CRL4(DCAF1 complex is alone responsible for cell cycle-dependent UNG2 turnover and will also aid in establishing conditions necessary for the identification of additional targets of Vpr-enhanced degradation.

78 FR 17212 - Patient Safety Organizations: Voluntary Relinquishment From Universal Safety Solution PSO

Science.gov (United States)

2013-03-20

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Research and Quality (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21--b-26, provides for the...

78 FR 52941 - Cooperative Research and Development Agreement: Next Generation Arctic Navigational Safety...

Science.gov (United States)

2013-08-27

... advantages, disadvantages, required technology enhancements, performance, costs, and other issues associated... technology approach to the ``Next Generation Arctic Maritime Navigational Safety Information System,'' which... Federal Technology Transfer Act of 1986 (Pub. L. 99-502, codified at 15 U.S.C. 3710(a)). A CRADA [[Page...

Enhancement of pressurizer safety valve operability by seating design improvement

International Nuclear Information System (INIS)

Moisidis, N.T.; Ratiu, M.D.

1994-01-01

Operating conditions specific to Pressurizer Safety Valves (PSVs) have led to numerous problems and have caused industry and NRC concerns regarding the adequacy of spring loaded self-actuated safety valves for Reactor Coolant System (RCS) overpressure protection. Specific concerns are: setpoint drift, spurious actuations and leakage. Based on testing and valve construction analysis of a Crosby model 6M6 PSV, it was established that the primary contributor to the valve problems is a susceptibility to weak seating. To eliminate spring instability, a new spring washer was designed, which guides the spring and precludes its rotation from the reference installed position. Results of tests performed on a prototype PSV equipped with the modified upper spring washer has shown significant improvements in valve operability and a consistent setpoint reproducibility to less than ±1% of the PSV setpoint (testing of baseline, unmodified valve, resulted in a setpoint drift of ±2%). Enhanced valve operability will result in a significant decrease in operating and maintenance costs associated with valve maintenance and testing. In addition, the enhanced setpoint reproducibility will allow the development of a nitrogen to steam correlation for future in-house PSV testing which will result in further reductions in costs associated with valve testing

Nuclear Safety through International Cooperation

International Nuclear Information System (INIS)

Flory, Denis

2013-01-01

The Fukushima Daiichi nuclear accident was the worst at a nuclear facility since the Chernobyl accident in 1986. It caused deep public anxiety and damaged confidence in nuclear power. Following this accident, strengthening nuclear safety standards and emergency response has become an imperative at the global level. The IAEA is leading in developing a global approach, and the IAEA Action Plan on Nuclear Safety is providing a comprehensive framework and acting as a significant driving force to identify lessons learned and to implement safety improvements. Strengthening nuclear safety is addressed through a number of measures proposed in the Action Plan including 12 main actions focusing on safety assessments in the light of the accident. Significant progress has been made in assessing safety vulnerabilities of nuclear power plants, strengthening the IAEA's peer review services, improvements in emergency preparedness and response capabilities, strengthening and maintaining capacity building, as well as widening the scope and enhancing communication and information sharing with Member States, international organizations and the public. Progress has also been made in reviewing the IAEA's safety standards, which continue to be widely applied by regulators, operators and the nuclear industry in general, with increased attention and focus on accident prevention, in particular severe accidents, and emergency preparedness and response.

Safety of NPP with WWER-440 and WWER-1000 reactors

Energy Technology Data Exchange (ETDEWEB)

Balabanov, E [Energoproekt, Sofia (Bulgaria); Gledachev, J; Angelov, D [Kombinat Atomna Energetika, Kozloduj (Bulgaria)

1996-12-31

The WWER-440 and WWER-1000 reactors used at the Kozloduy NPP have been analyzed in terms of safety. There are currently 4 reactors WWER-440/230 and 2 reactors WWER-1000/320. The former do not comply completely with the modern safety requirements due to the regulations acted in the sixties when they have been designed. The main features of these reactors are: low power density in the core; three levels of reactor control and protection; six primary loops; horizontal steam generators; two turbines; large number of cross-unit connections. The low thermal density in the core, the low specific thermal loading in the rods and the large coolant inventory enhance the safety, while the major deficiencies are identified as follows: insufficient capabilities for emergency core cooling; low diversification and physical separation of the safety systems; old fashioned control systems; inadequate fire protection; lack of full containment. It is pointed out that several design and operation actions have been completed in the Kozloduy NPP in order to enhance their safety. The WWER-1000 units are 320 model and feature a high safety level, complying completely with OPB-82 regulations and with all current international safety standards. 3 refs., 7 figs., 1 tab.

Safety of NPP with WWER-440 and WWER-1000 reactors

International Nuclear Information System (INIS)

Balabanov, E.; Gledachev, J.; Angelov, D.

1995-01-01

The WWER-440 and WWER-1000 reactors used at the Kozloduy NPP have been analyzed in terms of safety. There are currently 4 reactors WWER-440/230 and 2 reactors WWER-1000/320. The former do not comply completely with the modern safety requirements due to the regulations acted in the sixties when they have been designed. The main features of these reactors are: low power density in the core; three levels of reactor control and protection; six primary loops; horizontal steam generators; two turbines; large number of cross-unit connections. The low thermal density in the core, the low specific thermal loading in the rods and the large coolant inventory enhance the safety, while the major deficiencies are identified as follows: insufficient capabilities for emergency core cooling; low diversification and physical separation of the safety systems; old fashioned control systems; inadequate fire protection; lack of full containment. It is pointed out that several design and operation actions have been completed in the Kozloduy NPP in order to enhance their safety. The WWER-1000 units are 320 model and feature a high safety level, complying completely with OPB-82 regulations and with all current international safety standards. 3 refs., 7 figs., 1 tab

Efforts toward enhancing seismic safety at Kashiwazaki Kariwa Nuclear Power Station

International Nuclear Information System (INIS)

Yamashita, Kazuhiko

2009-01-01

It has been two years since the Niigata-ken Chuetsu-oki Earthquake (NCOE) occurred in 2007. The earthquake brought a major disaster for Kashiwazaki, Kariwa, and the neighboring areas. First of all, we would like to give condolences to people in the devastated area and to pray for the immediate recovery. Our Kashiwazaki Kariwa Nuclear Power Station located in the same area was naturally caught up in the earthquake. The station was hit by a big tremor more than its intensity assumed to be valid at the station design stage. In spite of unexpected tremor, preventive functions for the station safety worked as expected as it designed. Critical facilities designed as high seismic class were not damaged, though considerable damages were seen in outside-facilities designed as low seismic class. We currently make efforts to inspect and recover damages. While we carefully carry out inspection and assessment to make sure the station integrity, we are also going forward restoration as well as construction for seismic safety enhancement in turn. This report introduces details of the following accounts, these are an outline of guidelines for seismic design evaluation that was revised in 2006, a situation at Kashiwazaki Kariwa Nuclear Power Station in the aftermath of the earthquake, and efforts toward enhancing seismic safety that the Tokyo Electric Power Company (TEPCO) has made since the seismic disaster, and our approach to evaluation of facility integrity. (author)

A Safety and Health Guide for Vocational Educators. Incorporating Requirements of the Occupational Safety and Health Act of 1970, Relevant Pennsylvania Requirements with Particular Emphasis for Those Concerned with Cooperative Education and Work Study Programs. Volume 15. Number 1.

Science.gov (United States)

Wahl, Ray

Intended as a guide for vocational educators to incorporate the requirements of the Occupational Safety and Health Act (1970) and the requirements of various Pennsylvania safety and health regulations with their cooperative vocational programs, the first chapter of this document presents the legal implications of these safety and health…

Enhancement of Nuclear Safety in Korea: A Regulatory Perspective

International Nuclear Information System (INIS)

Chung, K.Y.

2016-01-01

In the aftermath of Fukushima Daiichi accident in 2011 Korean regulatory body immediately performed special inspections on nuclear power plants (NPPs) and a research reactor in Korea, and issued an enforcement order for the licensees to implement fifty Fukushima action items to address the safety issues identified by the inspections. Subsequently, the licensees have established the implementation plans for resolution of the action items. By the implementation of the action items, the possibility of severe accident due to the extreme hazards has been greatly reduced and the capabilities to mitigate the severe accident, should it occur, have been upgraded. To improve the consistency and predictability of the regulation on severe accidents, Nuclear Safety and Security Commission (NSSC) the regulatory body in Korea, is revising the regulatory framework for severe accidents. The new framework will require the licensee to enhance the capabilities for prevention and mitigation of severe accidents in view of the defence in depth principle, to assess the radiological effects from the severe accidents, and to improve current accident management procedures and guidelines necessary for the prevention and mitigation of severe accidents. This rulemaking also considers the safety principles provided by the IAEA Vienna Declaration in 2015, which require new NPPs to prevent large radioactive releases. (author)

75 FR 1749 - Notice of Meeting; Federal Lands Recreation Enhancement Act (Title VIII, Pub. L. 108-447)

Science.gov (United States)

2010-01-13

... DEPARTMENT OF AGRICULTURE Forest Service Notice of Meeting; Federal Lands Recreation Enhancement... Management in Oregon and Washington, under the Federal Lands Recreation Enhancement Act of 2004. DATES: The conference call will be held on February 2, 2010 from 12:30 p.m. to 4:30 p.m. A public input session will be...

Short-term initiatives for enhancing cyber-safety within South African schools

Directory of Open Access Journals (Sweden)

Elmarie Kritzinger

2016-07-01

Full Text Available The rate of technological development across the globe is dramatic. The decreasing cost and increasing availability of ICT devices means that its users are no longer exclusively industry or government employees – they are now also home users. Home users integrate ICT in their daily lives for education, socialising and information gathering. However, using ICT is associated with risks and threats, such as identity theft and phishing scams. Most home users of ICT do not have the necessary information technology and Internet skills to protect themselves and their information. School learners, in particular, are not sufficiently educated on how to use technological devices safely, especially in developing countries such as South Africa. The national school curriculum in South Africa currently does not make provision for cyber-safety education, and the availability of supporting material and training for ICT teachers in South Africa is limited, resulting in a lack of knowledge and skills regarding cyber-safety. The research in hand focuses on the situation concerning cyber-safety awareness in schools and has adopted a short-term approach towards cyber-safety among teachers and school learners in South Africa until a formal long-term national approach has been implemented. This study takes a quantitative approach to investigating the current options of teachers to enhance cyber-safety among learners in their schools. The research proposes that short-term initiatives (i.e. posters can increase learners’ awareness of cyber-safety until formal cyber-safety awareness methods have been introduced.

Bill C-5, an act to amend the radiation emitting devices act

International Nuclear Information System (INIS)

1984-01-01

This Act, entitled Bill C-5, allows for a series of amendments to the Radiation Emitting Devices Act. The amendments relate to regulations concerned with the sale, lease or import, labelling, advertising, packaging, safety standards and inspection of radiation emitting devices

Effectiveness evaluation methodology for safety processes to enhance organisational culture in hazardous installations

International Nuclear Information System (INIS)

Mengolini, A.; Debarberis, L.

2008-01-01

Safety performance indicators are widely collected and used in hazardous installations. The IAEA, OECD and other international organisations have developed approaches that strongly promote deployment of safety performance indicators. These indicators focus mainly on operational performance, but some of them also address organisational and safety culture aspects. However, operators of hazardous installations, in particular those with limited resources and time constraints, often find it difficult to collect the large number of different safety performance indicators. Moreover, they also have difficulties with giving a meaning to the numbers and trends recorded, especially to those that should reflect a positive safety culture. In this light, the aim of this article is to address the need to monitor and assess progress on implementation of a programme to enhance safety and organisational culture. It proposes a specific process-view approach to effectiveness evaluation of organisational and safety culture indicators by means of a multi-level system in which safety processes and staff involvement in defining improvement activities are central. In this way safety becomes fully embedded in staff activities. Key members of personnel become directly involved in identifying and supplying leading indicators relating to their own daily activity and become responsible and accountable for keeping the measurement system alive. Besides use of lagging indicators, particular emphasis is placed on the importance of identifying and selecting leading indicators which can be used to drive safety performance for organisational and safety culture aspects as well

Effectiveness evaluation methodology for safety processes to enhance organisational culture in hazardous installations.

Science.gov (United States)

Mengolini, A; Debarberis, L

2008-06-30

Safety performance indicators are widely collected and used in hazardous installations. The IAEA, OECD and other international organisations have developed approaches that strongly promote deployment of safety performance indicators. These indicators focus mainly on operational performance, but some of them also address organisational and safety culture aspects. However, operators of hazardous installations, in particular those with limited resources and time constraints, often find it difficult to collect the large number of different safety performance indicators. Moreover, they also have difficulties with giving a meaning to the numbers and trends recorded, especially to those that should reflect a positive safety culture. In this light, the aim of this article is to address the need to monitor and assess progress on implementation of a programme to enhance safety and organisational culture. It proposes a specific process-view approach to effectiveness evaluation of organisational and safety culture indicators by means of a multi-level system in which safety processes and staff involvement in defining improvement activities are central. In this way safety becomes fully embedded in staff activities. Key members of personnel become directly involved in identifying and supplying leading indicators relating to their own daily activity and become responsible and accountable for keeping the measurement system alive. Besides use of lagging indicators, particular emphasis is placed on the importance of identifying and selecting leading indicators which can be used to drive safety performance for organisational and safety culture aspects as well.

Challenges in ensuring radiological safety and nuclear forensic for malicious acts involving nuclear and other radioactive material

International Nuclear Information System (INIS)

Sharma, Ranjit; Chatterjee, M.K.; Singh, Rajvir; Pradeepkumar, K.S.

2010-01-01

Nuclear and other radioactive materials may get smuggled into the country aimed at malicious acts. Radioactive material detected accidentally or during inspection at the entry points/national borders may indicate illicit trafficking for the purpose of nuclear/radiological terrorism. As country requires prevention and preparedness for response to these malicious acts, nuclear forensic techniques are to be developed incorporating radiological safety aspects. Nuclear forensics helps in determining the origin, intended use, legal owner and the smuggled route etc. by using fingerprinting as well as comparison with reference data. The suggested sequence of methods for analysis of radioactive material/samples will be radiological assessment, physical characterization, traditional forensic analysis, isotope analysis along with elemental/chemical analysis

NASA Engineering and Safety Center (NESC) Enhanced Melamine (ML) Foam Acoustic Test (NEMFAT)

Science.gov (United States)

McNelis, Anne M.; Hughes, William O.; McNelis, Mark E.

2014-01-01

The NASA Engineering and Safety Center (NESC) funded a proposal to achieve initial basic acoustic characterization of ML (melamine) foam, which could serve as a starting point for a future, more comprehensive acoustic test program for ML foam. A project plan was developed and implemented to obtain acoustic test data for both normal and enhanced ML foam. This project became known as the NESC Enhanced Melamine Foam Acoustic Test (NEMFAT). This document contains the outcome of the NEMFAT project.

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

International Nuclear Information System (INIS)

Anon.

1991-01-01

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

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

International Nuclear Information System (INIS)

Anon.

1989-01-01

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

Safety: Preventive Medicine.

Science.gov (United States)

Kotula, John R.; Digenakis, Anthony

1985-01-01

Underscores the need for community colleges to practice safety within the institutions and to instruct students in workplace safety procedures and requirements. Reviews Occupational Safety and Health Act (OSHA) regulations and their impact on industry and education. Looks at the legal responsibilities of colleges for safety. (DMM)

Enhancement of pressurizer safety valve operability by seating design improvement

International Nuclear Information System (INIS)

Moisidis, N.T.; Ratiu, M.D.

1995-01-01

Operating conditions specific to pressurizer safety valves (PSVs) have led to numerous problems and have caused industry and NRC concerns regarding the adequacy of spring-loaded self-actuated safety valves for reactor coolant system (RCS) overpressure protection. Specific concerns are: setpoint drift, spurious actuations, and pressure protection. Specific concerns are: setpoint drift, spurious actuations, and leakage. Based on testing and valve construction analysis of a Crosby model 6M6 PSV (Moisidis and Ratiu, 1992), it was established that the primary contributor to the valve problems is a susceptibility to weak seating. To eliminate spring instability, a new spring washer was designed, which guides the spring and precludes its rotation from the reference installed position. Results of tests performed on a prototype PSV equipped with the modified upper spring washer has shown significant improvements in valve operability and a consistent setpoint reproducibility to less than ±1% of the PSV setpoint (testing of baseline, unmodified valve, resulted in a setpoint drift of ± 2%). Enhanced valve operability will result in a significant decrease in operating and maintenance costs associated with valve maintenance and testing. In addition, the enhanced setpoint reproducibility will allow the development of a nitrogen to steam correlation for future in-house PSV testing which will result in further reductions in costs associated with valve testing

Conception of transport cask with advanced safety, aimed at transportation and storage of spent nuclear fuel of power reactors, which meets the requirements of IAEA in terms of safety and increased stability during beyond-design-basis accidents and acts of terrorism

International Nuclear Information System (INIS)

Il'kaev, R.I.; Matveev, V.Z.; Morenko, A.I.; Shapovalov, V.I.; Semenov, A.G.; Sergeyev, V.M.; Orlov, V.K.; Shatalov, V.V.; Gotovchikov, V.T.; Seredenko, V.A.; Haire, Jonathan M.; Forsberg, C.W.

2004-01-01

The report is devoted to the problem of creation of a new generation of multi-purpose universal transport cask with advanced safety, aimed at transportation and storage of spent nuclear fuel (SNF) of power reactors, which meets all requirements of IAEA in terms of safety and increased stability during beyond-design-basis accidents and acts of terrorism. Meeting all IAEA requirements in terms of safety both in normal operation conditions and accidents, as well as increased stability of transport cask (TC) with SNF under the conditions of beyond-design-basis accidents and acts of terrorism has been achieved in the design of multi-purpose universal TC due to the use of DU (depleted uranium) in it. At that, it is suggested to use DU in TC, which acts as effective gamma shield and constructional material in the form of both metallic depleted uranium and metal-ceramic mixture (cermet), based on stainless or carbon steel and DU dioxide. The metal in the cermet is chosen to optimize cask performance. The use of DU in the design of multi-purpose universal TC enables getting maximum load of the container for spent nuclear fuel when meeting IAEA requirements in terms of safety and providing increased stability of the container with SNF under conditions of beyond-design-basis accident and acts of terrorism

Conception of transport cask with advanced safety, aimed at transportation and storage of spent nuclear fuel of power reactors, which meets the requirements of IAEA in terms of safety and increased stability during beyond-design-basis accidents and acts of terrorism

Energy Technology Data Exchange (ETDEWEB)

Il' kaev, R.I.; Matveev, V.Z.; Morenko, A.I.; Shapovalov, V.I. [Russian Federal Nuclear Center - All-Russian Research Inst. of Experimental Physics, Sarov (Russian Federation); Semenov, A.G.; Sergeyev, V.M.; Orlov, V.K. [All-Russian Research Inst. of Inorganic Materials, Moscow (Russian Federation); Shatalov, V.V.; Gotovchikov, V.T.; Seredenko, V.A. [All-Russian Research Inst. of Applied Chemistry, Moscow (Russian Federation); Haire, Jonathan M.; Forsberg, C.W. [Oak Ridge National Lab., Oak Ridge (United States)

2004-07-01

The report is devoted to the problem of creation of a new generation of multi-purpose universal transport cask with advanced safety, aimed at transportation and storage of spent nuclear fuel (SNF) of power reactors, which meets all requirements of IAEA in terms of safety and increased stability during beyond-design-basis accidents and acts of terrorism. Meeting all IAEA requirements in terms of safety both in normal operation conditions and accidents, as well as increased stability of transport cask (TC) with SNF under the conditions of beyond-design-basis accidents and acts of terrorism has been achieved in the design of multi-purpose universal TC due to the use of DU (depleted uranium) in it. At that, it is suggested to use DU in TC, which acts as effective gamma shield and constructional material in the form of both metallic depleted uranium and metal-ceramic mixture (cermet), based on stainless or carbon steel and DU dioxide. The metal in the cermet is chosen to optimize cask performance. The use of DU in the design of multi-purpose universal TC enables getting maximum load of the container for spent nuclear fuel when meeting IAEA requirements in terms of safety and providing increased stability of the container with SNF under conditions of beyond-design-basis accident and acts of terrorism.

Enhancement of nuclear safety culture

International Nuclear Information System (INIS)

Anderson, Stanley J.

1996-01-01

Throughout the 40-year history of the commercial nuclear power industry, improvements have continually been made in the design of nuclear power plants and the equipment in them. In one sense, we have reached an enviable point -- in most plants, equipment failures have become relatively rare. Yet events continue to occur. Regardless of how much the plants are improved, that equipment is operated by people -- highly motivated, well-trained people -- but people nonetheless. And people occasionally make mistakes. By setting the right climate and by setting high standards, good plant management can reduce the number of mistakes made ? and also reduce their potential consequences. Another way to say this is that the proper safety culture must be established and continually improved upon in our nuclear plants. Safety culture is defined by the International Atomic Energy Agency as 'that assembly of characteristics and attitudes in organizations and individuals which establishes that, as an overriding priority, nuclear plant safety issues receive the attention that, as an overriding priority, nuclear plant safety issues receive the attention warranted by their significance.' In short, we must make safety our top priority

47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key topic / Enhanced safety and operation excellence

Energy Technology Data Exchange (ETDEWEB)

Traichel, Anke [NUKEM Technologies Engineering Services GmbH, Alzenau (Germany). Dept. of Safety Engineering and Assessment / Proposals Engineering

2017-04-15

Summary report on the Key Topic ''Enhanced Safety and Operation Excellence'' Technical Session ''Safety, IT, Hazards and PSA'' of the 47th Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016.

Survey on the implementation of the Occupational Health and Safety Act at an academic hospital in Johannesburg.

Science.gov (United States)

Foromo, Muraga R; Chabeli, Mary; Satekge, Mpho M

2016-09-28

Despite the available research findings, recommendations and the South African Occupational Health and Safety Act (OHSA) (Act 85 of 1993), there are still challenges with regard to the implementation of selected sections and regulations of the OHSA. This is evidenced by the occupational injuries and illness claims registered with the compensation fund (South Africa, Department of Labour 1993). To determine the extent to which the OHSA was implemented at an academic hospital in Johannesburg, from the senior professional nurses and nursing managers' perspective, and to describe recommendations in order to facilitate the implementation of the Act. A contextual, quantitative, exploratory and descriptive survey was conducted. A purposive sampling method was used to select the participants that met the inclusion criteria. A structured Likert-scale questionnaire was used to collect data (Brink 2011). Stata version 12 was used to analyse the data. Cronbach's alpha, with a cut-off point of 0.7 was used to test for internal consistency. Ethical considerations were strictly adhered to. Results are presented in the form of graphs, frequency distributions and tables. The study revealed that overall there is 93.3% non-implementation of the selected sections and regulations of the OHSA. These results have serious implications on the health and safety of employees in the workplace. The study recommends that the replication of the study should be conducted in order to determine the extent of implementation of the selected sections and regulations of the OHSA in other government institutions.

An Approach to Enhancement of the Safety Culture of Nuclear Power Plants

Energy Technology Data Exchange (ETDEWEB)

Lee, Yong Hee [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2014-05-15

The culture of an organization is very complex to study and evaluate, but it is possible to examine the specific norms that figure out the culture for the safety of a system. This paper describes an initiation plan to study the safety culture issue in Korean NPPs. Recently there happened successively events that turned out to be socially prominent in Korea. Many issues on the safety culture aspect of NPPs have been raised including the types of errors such as violations, an intended concealment of safety-related information, counterfeit items, forgery process in procurement, and so on. Those were investigated in detail for the root causes of these issues as human and organizational errors and for the countermeasures to prevent those events. They are integrated into a correspondent long-term plan including the establishment of a fundamental infrastructure of safety culture management for operating NPPs in Korea. A monitoring system with analysis functions utilizing system dynamics simulation and data mining is proposed to be incorporated into a safety culture management system. Additionally, a set of training and support programs are to be developed for the enhancement of some selected competence of the operating personnel in Korean NPPs. The safe operation of NPPs requires the typical safety culture characteristics of the high reliability organization (HRO). The culture of an organization is very complex to study and evaluate, but it is possible to examine the specific norms that figure out the culture for the safety of a system. This paper describes an integrated systems approach as an initiating plan to study the safety culture issue in Korean NPPs.

An Approach to Enhancement of the Safety Culture of Nuclear Power Plants

International Nuclear Information System (INIS)

Lee, Yong Hee

2014-01-01

The culture of an organization is very complex to study and evaluate, but it is possible to examine the specific norms that figure out the culture for the safety of a system. This paper describes an initiation plan to study the safety culture issue in Korean NPPs. Recently there happened successively events that turned out to be socially prominent in Korea. Many issues on the safety culture aspect of NPPs have been raised including the types of errors such as violations, an intended concealment of safety-related information, counterfeit items, forgery process in procurement, and so on. Those were investigated in detail for the root causes of these issues as human and organizational errors and for the countermeasures to prevent those events. They are integrated into a correspondent long-term plan including the establishment of a fundamental infrastructure of safety culture management for operating NPPs in Korea. A monitoring system with analysis functions utilizing system dynamics simulation and data mining is proposed to be incorporated into a safety culture management system. Additionally, a set of training and support programs are to be developed for the enhancement of some selected competence of the operating personnel in Korean NPPs. The safe operation of NPPs requires the typical safety culture characteristics of the high reliability organization (HRO). The culture of an organization is very complex to study and evaluate, but it is possible to examine the specific norms that figure out the culture for the safety of a system. This paper describes an integrated systems approach as an initiating plan to study the safety culture issue in Korean NPPs

Practicing industrial safety - issues involved

International Nuclear Information System (INIS)

Gunasekaran, P.

2016-01-01

Industrial safety is all about measures or techniques implemented to reduce the risk of injury, loss to persons, property or the environment in any industrial facility. The issue of industrial safety evolved concurrently with industrial development as a shift from compensation to prevention as well. Today, industrial safety is widely regarded as one of the most important factors that any business, large or small, must consider in its operations, as prevention of loss is also a part of profit. Factories Act of Central government and Rules made under it by the state deals with the provisions on industrial safety legislation. There are many other acts related to safety of personnel, property and environment. Occupational health and safety is also of primary concern. The aim is to regulate health and safety conditions for all employers. It includes safety standards and health standards. These acts encourage employers and employees to reduce workplace hazards and to implement new or improve existing safety and health standards; and develop innovative ways to achieve them. Maintain a reporting and record keeping system to monitor job-related injuries and illnesses; establish training programs to increase the number and competence of occupational safety and health personnel

Computer-assisted navigational surgery enhances safety in dental implantology.

Science.gov (United States)

Ng, F C; Ho, K H; Wexler, A

2005-06-01

Dental implants are increasingly used to restore missing dentition. These titanium implants are surgically installed in the edentulous alveolar ridge and allowed to osteointegrate with the bone during the healing phase. After osseo-integration, the implant is loaded with a prosthesis to replace the missing tooth. Conventional implant treatment planning uses study models, wax-ups and panoramic x-rays to prefabricate surgical stent to guide the preparation of the implant site. The drilling into the alveolar ridge is invariably a "blind" procedure as the part of the drill in bone is not visible. Stereotactic systems were first introduced into neurosurgery in 1986. Since then, computer-assisted navigational technology has brought major advances to neuro-, midface and orthopaedic surgeries, and more recently, to implant placement. This paper illustrates the use of real-time computer-guided navigational technology in enhancing safety in implant surgical procedures. Real-time computer-guided navigational technology enhances accuracy and precision of the surgical procedure, minimises complications and facilitates surgery in challenging anatomical locations.

Report of a consultants meeting on backfittings and safety enhancement measures in NPPs with WWER 440/213 reactors. Extrabudgetary programme on the safety of WWER NPPS

International Nuclear Information System (INIS)

1994-01-01

The purpose of this Consultants' Meeting held by the IAEA in Vienna from 11-15 April 1994 within the framework of the Extrabudgetary Programme on WWER Safety was to review and analyze safety issues revealed during operation and through analyses of NPPs with WWER 440/213 reactors. The initial list of safety issues based on the available reports from various studies had been prepared by the IAEA secretariat before the meeting, together with indications of safety enhancement measures proposed in various NPP units. During the meeting, the underlying safety concerns and actual technical status of the plants were discussed and the ranking of the safety issues was considered. 58 refs, 1 tab

76 FR 71345 - Patient Safety Organizations: Voluntary Relinquishment From Child Health Patient Safety...

Science.gov (United States)

2011-11-17

... Organizations: Voluntary Relinquishment From Child Health Patient Safety Organization, Inc. AGENCY: Agency for... notification of voluntary relinquishment from Child Health Patient Safety Organization, Inc. of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety...

Suitable footwear for enhanced safety

CERN Document Server

2004-01-01

Safety shoes are the theme of a new safety campaign. Always remember that accidents can happen - even to your feet! When entering hazardous areas such as underground halls, work sites, experiment assembly sites, workshops etc., sandals, ordinary shoes or similar light footwear should not be worn. Whatever the risks to which you may be exposed, always think safety and wear suitable footwear, i.e. safety shoes, which have non-slip soles and steel reinforcements to protect your feet from being crushed, fractured or pierced. Is it serious, Doctor? "Some traumas resulting from foot-related accidents - open fractures for instance - can be quite serious," explains CERN Works Doctor Véronique Fassnacht. "But the most common injuries are sprained ankles sustained during simple falls caused by differences in floor-levels (e.g. false floors). Fractures, bruising, surface wounds or deep wounds caused by objects falling onto the top of the foot are also quite common." ...

Annual report on the administration of the Radiation Control for Health and Safety Act of 1968, Public Law 90-602, (1988), April 1, 1989. Annual report

International Nuclear Information System (INIS)

1989-01-01

The Secretary of Health and Human Services is required by Subpart 3, Part F of Title III of the Public Health Service Act; 42 USC 263b et seq. (Public Law 90-602) to submit an annual report to the President for transmittal to the Congress on or before April 1 on the administration of the Radiation Control for Health and Safety Act. The detailed information required in the report is outlined in Section 360D of the Public Health Service Act. The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1988. In reviewing the operations of the Center for Devices and Radiological Health as reported in the document, it should be kept in mind that the day-to-day administration of the Act is only part of the Center's function. Other responsibilities include the administration and enforcement of the 1976 Medical Device Amendments to the Federal Food, Drug, and Cosmetic Act (not covered in the report)

No 592 - Radiation Act

International Nuclear Information System (INIS)

1991-01-01

This Act will enter into force on 1 January 1992. The scope of the Act is extensive as, in addition to ionizing radiation, it will also apply to activities involving exposure to natural radiation and non-ionizing radiation. Its purpose is to prevent and restrict harmful effects to health resulting from radiation. The basic principles of the Act are that the practice involving radiation should be justified; radiation protection should be optimized; and radiation doses should be as low as reasonably achievable. Licensed organisations using radiation will be responsible for the safety of the activity involving exposure to radiation and for having available the appropriate expertise to this effect. The required so-called safety licence provides the regulatory control to ensure that radiation is used sensibly, that the equipment and shields are technically acceptable and the operating personnel is competent, and that the radioactive waste is dealt with appropriately. The Radiation Act will also apply to nuclear activities within the scope of the 1987 Nuclear Energy Act [fr

Occupational Health and Safety ACT NO. 6331 and Status Assessment in this Perspective, the Role of ÇASGEM at Education and Research

OpenAIRE

Karaman, Esra

2015-01-01

In this study, basic knowledge of Occupational Health and Safety Act No. 6331 and in this regard legal rights and obligations of employers and employees was given. It was informed with this study health and safety problems originated from work, often experienced occupational accidents and occupational diseases and provided information about their causes. It was referred Labour and Social Security Training and Research Centre ( ÇASGEM ) 's missions and conducted education and research on ...

Enhanced safety in the storage of fissile materials

International Nuclear Information System (INIS)

Williams, G.E.; Alvares, N.J.

1978-01-01

An inexpensive boron-loaded liner of epoxy resin for fissile-material storage containers was developed that can be easily fabricated of readily available, low-cost materials. Computer calculations indicate reactivity will be reduced substantially if this neutron-absorbing liner is added to containers in a typical storage array. These calculations compare favorably with neutron-attenuation experiments with thermal and fission neutron spectra, and tests at the Fire Test Facility indicate the epoxy resin will survive extreme environmental and accident conditions. The fire-resistant and insulating properties of the epoxy-resin liner further augment its ability to protect fissile materials. Boron-loaded epoxy resin is adaptable to many tasks but is particularly useful for providing enhanced criticality safety in the packaging and storage of fissile materials

ENSI’s synopsis concerning the enhancement of safety margins; Zusammenfassung des ENSI zur Erhöhung der Sicherheitsmargen

Energy Technology Data Exchange (ETDEWEB)

NONE

2015-06-15

This press release issued by the Swiss Federal Nuclear Safety Inspectorate ENSI discusses the results of its probabilistic safety analysis on the safety margins for Swiss nuclear power stations that was made after the Fukushima nuclear accident. External incidents such as earthquakes and flooding and their impact on the power stations are analysed by the ERSIM project concerning the enhancement of safety margins. Three shut-down scenarios are discussed. The safety margins with respect to earthquakes and flooding for all four nuclear power station sites are discussed in detail.

Healing Arts Radiation Protection Act

International Nuclear Information System (INIS)

1984-07-01

The Healing Arts Radiation Protection Act is concerned with regulating the registration, installation, operation, inspection and safety of X-ray machines. The Act provides for the establishment of the Healing Arts Radiation Protection Commission which is responsible for reporting on all the above matters to the Ontario Minister of Health. In addition the board is responsible for the continuing development of an X-ray safety code and for the submission of an annual report of their activities to the minister

Chronic beryllium disease prevention program; worker safety and health program. Final rule.

Science.gov (United States)

2006-02-09

The Department of Energy (DOE) is today publishing a final rule to implement the statutory mandate of section 3173 of the Bob Stump National Defense Authorization Act (NDAA) for Fiscal Year 2003 to establish worker safety and health regulations to govern contractor activities at DOE sites. This program codifies and enhances the worker protection program in operation when the NDAA was enacted.

Enhancing Safety through Generic Competencies

Directory of Open Access Journals (Sweden)

S. Mockel

2014-03-01

Full Text Available This article provides insights into proactive safety management and mitigation. An analysis of accident reports reveals categories of supervening causes of accidents which can be directly linked to the concept of generic competencies (information management, communication and coordination, problem solving, and effect control. These findings strongly suggest adding the human element as another safety-constituting pillar to the concept of ship safety next to technology and regulation. We argue that the human element has unique abilities in dealing with critical and highly dynamic situations which can contribute to the system's recovery from non-routine or critical situations. By educating seafarers in generic competencies we claim to enable the people onboard to successfully deal with critical situations.

21 CFR 1000.15 - Examples of electronic products subject to the Radiation Control for Health and Safety Act of 1968.

Science.gov (United States)

2010-04-01

... 21 Food and Drugs 8 2010-04-01 2010-04-01 false Examples of electronic products subject to the Radiation Control for Health and Safety Act of 1968. 1000.15 Section 1000.15 Food and Drugs FOOD AND DRUG... electromagnetic radiation include: Ultraviolet: Biochemical and medical analyzers. Tanning and therapeutic lamps...

Identification of protective actions to reduce the vulnerability of safety-critical systems to malevolent acts: A sensitivity-based decision-making approach

International Nuclear Information System (INIS)

Wang, Tai-Ran; Pedroni, Nicola; Zio, Enrico

2016-01-01

A classification model based on the Majority Rule Sorting method has been previously proposed by the authors to evaluate the vulnerability of safety-critical systems (e.g., nuclear power plants) with respect to malevolent intentional acts. In this paper, we consider a classification model previously proposed by the authors based on the Majority Rule Sorting method to evaluate the vulnerability of safety-critical systems (e.g., nuclear power plants) with respect to malevolent intentional acts. The model is here used as the basis for solving an inverse classification problem aimed at determining a set of protective actions to reduce the level of vulnerability of the safety-critical system under consideration. To guide the choice of the set of protective actions, sensitivity indicators are originally introduced as measures of the variation in the vulnerability class that a safety-critical system is expected to undergo after the application of a given set of protective actions. These indicators form the basis of an algorithm to rank different combinations of actions according to their effectiveness in reducing the safety-critical systems vulnerability. Results obtained using these indicators are presented with regard to the application of: (i) one identified action at a time, (ii) all identified actions at the same time or (iii) a random combination of identified actions. The results are presented with reference to a fictitious example considering nuclear power plants as the safety-critical systems object of the analysis. - Highlights: • We use a hierarchical framework to represent the vulnerability. • We use an empirical classification model to evaluate vulnerability. • Sensitivity indicators are introduced to rank protective actions. • Constraints (e.g., budget limitations) are accounted for. • Method is applied to fictitious Nuclear Power Plants.

The Health and Safety Executive's regulatory framework for control of nuclear criticality safety

International Nuclear Information System (INIS)

Smith, K.; Simister, D.N.

1991-01-01

In the United Kingdom the Health and Safety at Work Act, 1974 is the main legal instrument under which risks to people from work activities are controlled. Certain sections of the Nuclear Installations Act, 1965 which deal with the licensing of nuclear sites and the regulatory control of risks arising from them, including the risk from accidental criticality, are relevant statutory provisions of the Health and Safety at Work Act. The responsibility for safety rests with the operator who has to make and implement arrangements to prevent accidental criticality. The adequacy of these arrangements must be demonstrated in a safety case to the regulatory authorities. Operators are encouraged to treat each plant on its own merits and develop the safety case accordingly. The Nuclear Installations Inspectorate (NII), for its part, assesses the adequacy of the operator's safety case against the industry's own standards and criteria, but more particularly against the NII's safety assessment principles and guides, and international standards. Risks should be made as low as reasonably practicable. Generally, the NII seeks improvements in safety using an enforcement policy which operates at a number of levels, ranging from persuasion through discussion to the ultimate deterrent of withdrawal of a site licence. This paper describes the role of the NII, which includes a specialist criticality expertise, within the Health and Safety Executive, in regulating the nuclear sites from the criticality safety viewpoint. (Author)

48 CFR 52.250-5 - SAFETY Act-Equitable Adjustment.

Science.gov (United States)

2010-10-01

... Act—Equitable Adjustment (FEB 2009) (a) Definitions. As used in this clause— Act of terrorism means... the DHS has determined to be a Qualified Anti-Terrorism Technology (QATT). Qualified Anti-Terrorism... preventing, detecting, identifying, or deterring acts of terrorism or limiting the harm such acts might...

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

Science.gov (United States)

2010-10-18

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

A new design concept for offshore nuclear power plants with enhanced safety features

International Nuclear Information System (INIS)

Lee, Kihwan; Lee, Kang-Heon; Lee, Jeong Ik; Jeong, Yong Hoon; Lee, Phill-Seung

2013-01-01

Highlights: ► A new design concept for offshore nuclear power plants is proposed. ► The total general arrangement for the concept is suggested. ► A new emergency passive containment cooling system (EPCCS) is proposed. ► A new emergency passive reactor-vessel cooling system (EPRVCS) is proposed. ► Safety features against earthquakes, tsunamis, and storms are discussed. - Abstract: In this paper, we present a new concept for offshore nuclear power plants (ONPP) with enhanced safety features. The design concept of a nuclear power plant (NPP) mounted on gravity-based structures (GBSs), which are widely used offshore structures, is proposed first. To demonstrate the feasibility of the concept, a large-scale land-based nuclear power plant model APR1400, which is the most recent NPP model in the Republic of Korea, is mounted on a GBS while minimizing modification to the original features of APR1400. A new total general arrangement (GA) and basic design principles are proposed and can be directly applied to any existing land based large scale NPPs. The proposed concept will enhance the safety of a NPP due to several aspects. A new emergency passive containment cooling system (EPCCS) and emergency passive reactor-vessel cooling system (EPRVCS) are proposed; their features of using seawater as coolant and safety features against earthquakes, Tsunamis, storms, and marine collisions are also described. We believe that the proposed offshore nuclear power plant is more robust than conventional land-based nuclear power plants and it has strong potential to provide great opportunities in nuclear power industries by decoupling the site of construction and that of installation.

16 CFR 1117.9 - Prohibited acts and sanctions.

Science.gov (United States)

2010-01-01

... 16 Commercial Practices 2 2010-01-01 2010-01-01 false Prohibited acts and sanctions. 1117.9 Section 1117.9 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT....C. 1001. (b) A failure to report to the Commission in a timely fashion as required by this part is a...

Britain's Nuclear Electric pursues a major programme to enhance safety

International Nuclear Information System (INIS)

Anon.

1991-01-01

The UK state-owned nuclear utility, Nuclear Electric, is actively pursuing a major initiative inherited from its predecessor the Central Electricity Generating Board, known as the Station Enhancement Programme. The Enhancement Programme is a multi-million pound project and covers all Nuclear Electric's stations (including relevant aspects of the de-commissioning site at Berkeley). Its fundamental objective is to enhance the arrangements, practices and attitudes on the power stations to create an overall environment likely to promote ever safer and more reliable operation, and to take full account of the best international practices. The four year programme started in the spring of 1989, and is expected to be completed in 1993. Key elements of the programme include quality assurance based management systems; improvements to site and plant material conditions; a more formal approach to training; additional resources and controls to aid the management of maintenance defects; higher profile for the feedback of operational experience; management targets; a station evaluation programme; and formal feedback of lessons learned from the IAEA operational and safety review team visit to the Oldbury-on-Severn station in 1989. (author)

Occupational Safety and Health Management System (OSHMS)

International Nuclear Information System (INIS)

Shyen, A.K.S.; Mohd Khairul Hakimin; Manisah Saedon

2011-01-01

Safe work environment has always been one of the major concerns at workplace. For this, Occupational Safety and Health Act 1994 has been promulgated for all workplaces to ensure the Safety, Health and Welfare of its employees and any person at workplaces. Malaysian Nuclear Agency therefore has started the initiative to review and improve the current Occupational Safety and Health Management System (OSHMS) by going for OHSAS 18001:2007 and MS 1722 standards certification. This would also help in our preparation to bid as the TSO (Technical Support Organization) for the NPP (Nuclear Power Plant) when it is established. With a developed and well maintained OSHMS, it helps to create a safe working condition and thus enhancing the productivity, quality and good morale. Ultimately, this will lead to a greater organization profit. However, successful OSHMS requires full commitment and support from all level of the organization to work hand in hand in implementing the safety and health policy. Therefore it is essential for all to acknowledge the progress of the implementation and be part of it. (author)

Enhancement of safety for reprocessing facilities

International Nuclear Information System (INIS)

2012-06-01

The adequacy of the safety measures for utility loss accidents in nuclear fuel reprocessing facilities which have been formulated by the nuclear enterprises is investigated in JNES which organizes an advanced committee to specifically study this problem. The results are reviewed in the present report including the case of such severe accidents as in Fukushima Daiichi Nuclear Power Plant. The report also represents a tentative proposal for examination standards of such unimaginable severe accidents as 'station blackout,' urgent safety measures necessary for reoperation of nuclear power plants and requested by nuclear and industrial safety agency, and pointing out and clarification of the potential weakness from the safety point of view, and collective and composite evaluation of safety of the relevant facilities. Furthermore, the definition of accident management is given as of controlled condition and the authorized way of thinking for the cases of plural events happening at the same time and the cases when risks exist radioactivity emits with explosion. (S. Ohno)

77 FR 11120 - Patient Safety Organizations: Voluntary Relinquishment From UAB Health System Patient Safety...

Science.gov (United States)

2012-02-24

... Organizations: Voluntary Relinquishment From UAB Health System Patient Safety Organization AGENCY: Agency for... notification of voluntary relinquishment from the UAB Health System Patient Safety Organization of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005...

Radiation emitting devices act

International Nuclear Information System (INIS)

1970-01-01

This Act, entitled the Radiation Emitting Devices Act, is concerned with the sale and importation of radiation emitting devices. Laws relating to the sale, lease or import, labelling, advertising, packaging, safety standards and inspection of these devices are listed as well as penalties for any person who is convicted of breaking these laws

14 CFR 1274.934 - Safety.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Safety. 1274.934 Section 1274.934... FIRMS Other Provisions and Special Conditions § 1274.934 Safety. Safety July 2002 NASA's safety priority... shall act responsibly in matters of safety and shall take all reasonable safety measures in performing...

77 FR 19414 - Pipeline Safety: Public Comment on Leak and Valve Studies Mandated by the Pipeline Safety...

Science.gov (United States)

2012-03-30

... Safety, Regulatory Certainty, and Job Creation Act of 2011 AGENCY: Pipeline and Hazardous Materials.... Background: The recent passage of the Pipeline Safety, Regulatory Certainty, and Job Creation Act of 2011 has... consider upstream and downstream controls, automation, supervisory control and data acquisition systems...

The Ex Hoc Infrastructure - Enhancing Traffic Safety through LIfe WArning Systems

DEFF Research Database (Denmark)

Hansen, Klaus Marius; Kristensen, Lars Michael; Eskildsen, Toke

2004-01-01

New pervasive computing technologies for sensing and communication open up novel possibilities for enhancing traffic safety. We are currently designing and implementing the Ex Hoc infrastructure framework for communication among mobile and stationary units including vehicles. The infrastructure...... will connect sensing devices on vehicles with sensing devices on other vehicles and with stationary communication units placed alongside roads. The current application of Ex Hoc is to enable the collection and dissemination of information on road condition through LIfe Warning Systems (LIWAS) units....

The Creating Hope Act: what is old is new again

Directory of Open Access Journals (Sweden)

Tolbert JA

2014-06-01

Full Text Available Jaszianne A Tolbert,1,2 Jennifer L Goldman,2-4 Ralph E Kauffman,2,4 Susan M Abdel-Rahman2,41Division of Hematology/Oncology, 2Division of Clinical Pharmacology and Therapeutic Innovation, 3Division of Infectious Diseases, Children's Mercy Hospital, Kansas City, MO, USA; 4Department of Pediatrics, University of Missouri-Kansas City, School of Medicine, Kansas City, MO, USAAbstract: The Creating Hope Act, passed as part of the Food and Drug Administration Safety and Innovation Act of 2012, is among the newest laws intended to foster drug development for rare and neglected diseases in children. The act expands the priority review voucher incentive that first appeared in the Food and Drug Administration Amendments Act of 2007 and was intended to stimulate the development of products for the prevention and treatment of tropical diseases. Notably, legislative and regulatory initiatives aimed at enhancing drug development both for use in children and for rare diseases have intermittently emerged over the past 3 decades. This manuscript provides an overview of related legislation that has preceded the Creating Hope Act and examines the potential impact of the new act in the context of the outcomes that have been observed with the earlier initiatives.Keywords: orphan drug, rare disease, pediatric, drug development, priority review voucher

Regulatory Safety Requirements for Operating Nuclear Installations

International Nuclear Information System (INIS)

Gubela, W.

2017-01-01

The National Nuclear Regulator (NNR) is established in terms of the National Nuclear Regulator Act (Act No 47 of 1999) and its mandate and authority are conferred through sections 5 and 7 of this Act, setting out the NNR's objectives and functions, which include exercising regulatory control over siting, design, construction etc of nuclear installations through the granting of nuclear authorisations. The NNR's responsibilities embrace all those actions aimed at providing the public with confidence and assurance that the risks arising from the production of nuclear energy remain within acceptable safety limits -> Therefore: Set fundamental safety standards, conducting pro-active safety assessments, determining licence conditions and obtaining assurance of compliance. The promotional aspects of nuclear activities in South Africa are legislated by the Nuclear Energy Act (Act No 46 of 1999). The NNR approach to regulations of nuclear safety and security take into consideration, amongst others, the potential hazards associated with the facility or activity, safety related programmes, the importance of the authorisation holder's safety related processes as well as the need to exercise regulatory control over the technical aspects such as of the design and operation of a nuclear facility in ensuring nuclear safety and security. South Africa does not have national nuclear industry codes and standards. The NNR is therefore non-prescriptive as it comes to the use of industry codes and standards. Regulatory framework (current) provide for the protection of persons, property, and environment against nuclear damage, through Licensing Process: Safety standards; Safety assessment; Authorisation and conditions of authorisation; Public participation process; Compliance assurance; Enforcement

Safety and effectiveness of rapid-acting intramuscular olanzapine for agitation associated with schizophrenia – Japan postmarketing surveillance study

Directory of Open Access Journals (Sweden)

Katagiri H

2018-01-01

Full Text Available Hideaki Katagiri,1 Masanori Taketsuna,2 Shinpei Kondo,3 Kenta Kajimoto,4 Etsuko Aoi,5 Yuka Tanji1 1Bio Medicine, 2Statistical Sciences, 3Post Marketing Study Management, 4Scientific Communications, Medicines Development Unit Japan, 5Global Patient Safety Japan, Quality and Patient Safety, Eli Lilly Japan K.K., Kobe, Japan Objective: The objective of this study was to evaluate the safety and effectiveness of rapid-acting intramuscular (IM olanzapine in the treatment of acute agitation associated with schizophrenia in real-world clinical settings in Japan.Methods: In this multicenter, postmarketing surveillance (PMS study, patients with acute agitation associated with schizophrenia were treated with IM olanzapine daily in a daily clinical setting. The observational period ranged from 1 to 7 days, including the day of initial administration. Safety was assessed by reporting treatment-emergent adverse events (TEAEs and adverse drug reactions (ADRs. The Positive and Negative Syndrome Scale – Excited Component (PANSS-EC score was used to evaluate effectiveness at baseline and at 2 hours (after each administration, 2 days, and 3 days (end of the observational period from the last administration of the IM olanzapine injection.Results: The safety analysis set included 999 patients, and the initial dose of 10 mg was administered to 955 patients. TEAEs were reported in 28 patients (36 events, the most common of which were dyslalia (5 patients, akathisia and somno­lence (4 patients each, hepatic function abnormal (3 patients, and constipation and dehydration (2 patients each. One serious adverse event of akathisia occurred during the observation period. The PANSS-EC score (mean ± standard deviation was 23.3±6.4 (n=625 at baseline, 16.9±7.0 (n=522 at 2 hours after initial injection, and 14.9±6.5 (n=650 at the last observation carried forward.Conclusion: The results of this Japanese PMS study demonstrated that IM olanzapine is safe and has a

Using Total Lightning Observations to Enhance Lightning Safety

Science.gov (United States)

Stano, Geoffrey T.

2012-01-01

Lightning is often the underrated threat faced by the public when it comes to dangerous weather phenomena. Typically, larger scale events such as floods, hurricanes, and tornadoes receive the vast majority of attention by both the general population and the media. This comes from the fact that these phenomena are large, longer lasting, can impact a large swath of society at one time, and are dangerous events. The threat of lightning is far more isolated on a case by case basis, although millions of cloud-to-ground lightning strikes hit this United States each year. While attention is given to larger meteorological events, lightning is the second leading cause of weather related deaths in the United States. This information raises the question of what steps can be taken to improve lightning safety. Already, the meteorological community s understanding of lightning has increased over the last 20 years. Lightning safety is now better addressed with the National Weather Service s access to the National Lightning Detection Network data and enhanced wording in their severe weather warnings. Also, local groups and organizations are working to improve public awareness of lightning safety with easy phrases to remember, such as "When Thunder Roars, Go Indoors." The impacts can be seen in the greater array of contingency plans, from airports to sports stadiums, addressing the threat of lightning. Improvements can still be made and newer technologies may offer new tools as we look towards the future. One of these tools is a network of sensors called a lightning mapping array (LMA). Several of these networks exist across the United States. NASA s Short-term Prediction Research and Transition Center (SPoRT), part of the Marshall Spaceflight Center, has access to three of these networks from Huntsville, Alabama, the Kennedy Space Center, and Washington D.C. The SPoRT program s mission is to help transition unique products and observations into the operational forecast environment

Nuclear Protections and Safety Act of 1987. Report of the Committee on Governmental Affairs, United States Senate together with Additional Views to Accompany S. 1085, One Hundredth Congress, First Session

International Nuclear Information System (INIS)

Anon.

1987-01-01

The Senate report on S. 1085 suggests several amendments to the recommended bill which would make oversight of nuclear facility safety an independent board. The legislation responds to concerns that there is no justification for DOE facilities to be exempt from this kind of oversight, and that health and safety standards are as important at nuclear weapons and materials facilities as elsewhere. The report traces the emergence of the nuclear age and the different treatment of government and commercial facilities. There is evidence of a lack of concern for employee health and safety at some government installations. The report summarizes the four titles of the bill, reviews the four days of public hearings, and analyzes the bill by section. It notes changes that will result in the Energy Reorganization Act of 1974, the Atomic Energy Act of 1954, and the Department of Energy Organization Act

29 CFR 1977.10 - Proceedings under or related to the Act.

Science.gov (United States)

2010-07-01

... OCCUPATIONAL SAFETY AND HEALTH ACT OF 1970 Specific Protections § 1977.10 Proceedings under or related to the... standard under section 6(f) of the Act and employee appeal of an Occupational Safety and Health Review... 1977.10 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH ADMINISTRATION...

76 FR 7854 - Patient Safety Organizations: Voluntary Delisting From Lumetra PSO

Science.gov (United States)

2011-02-11

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act... delivery. The Patient Safety and Quality Improvement Final Rule (Patient Safety Rule), 42 CFR part 3...

Stakeholder Transportation Scorecard: Reviewing Nevada's Recommendations for Enhancing the Safety and Security of Nuclear Waste Shipments - 13518

International Nuclear Information System (INIS)

Dilger, Fred C.; Ballard, James D.; Halstead, Robert J.

2013-01-01

As a primary stakeholder in the Yucca Mountain program, the state of Nevada has spent three decades examining and considering national policy regarding spent nuclear fuel and high-level radioactive waste transportation. During this time, Nevada has identified 10 issues it believes are critical to ensuring the safety and security of any spent nuclear fuel transportation program, and achieving public acceptance. These recommendations are: 1) Ship the oldest fuel first; 2) Ship mostly by rail; 3) Use dual-purpose (transportable storage) casks; 4) Use dedicated trains for rail shipments; 5) Implement a full-scale cask testing program; 6) Utilize a National Environmental Policy Act (NEPA) process for the selection of a new rail spur to the proposed repository site; 7) Implement the Western Interstate Energy Board (WIEB) 'straw man' process for route selection; 8) Implement Section 180C assistance to affected States, Tribes and localities through rulemaking; 9) Adopt safety and security regulatory enhancements proposed states; and 10) Address stakeholder concerns about terrorism and sabotage. This paper describes Nevada's proposals in detail and examines their current status. The paper describes the various forums and methods by which Nevada has presented its arguments and sought to influence national policy. As of 2012, most of Nevada's recommendations have been adopted in one form or another, although not yet implemented. If implemented in a future nuclear waste program, the State of Nevada believes these recommendations would form the basis for a successful national transportation plan for shipments to a geologic repository and/or centralized interim storage facility. (authors)

Strengthening leadership as a catalyst for enhanced patient safety culture: a repeated cross-sectional experimental study.

Science.gov (United States)

Kristensen, Solvejg; Christensen, Karl Bang; Jaquet, Annette; Møller Beck, Carsten; Sabroe, Svend; Bartels, Paul; Mainz, Jan

2016-05-13

Current literature emphasises that clinical leaders are in a position to enable a culture of safety, and that the safety culture is a performance mediator with the potential to influence patient outcomes. This paper aims to investigate staff's perceptions of patient safety culture in a Danish psychiatric department before and after a leadership intervention. A repeated cross-sectional experimental study by design was applied. In 2 surveys, healthcare staff were asked about their perceptions of the patient safety culture using the 7 patient safety culture dimensions in the Safety Attitudes Questionnaire. To broaden knowledge and strengthen leadership skills, a multicomponent programme consisting of academic input, exercises, reflections and discussions, networking, and action learning was implemented among the clinical area level leaders. In total, 358 and 325 staff members participated before and after the intervention, respectively. 19 of the staff members were clinical area level leaders. In both surveys, the response rate was >75%. The proportion of frontline staff with positive attitudes improved by ≥5% for 5 of the 7 patient safety culture dimensions over time. 6 patient safety culture dimensions became more positive (increase in mean) (pculture are remarkable, and imply that strengthening the leadership can act as a significant catalyst for patient safety culture improvement. Further studies using a longitudinal study design are recommended to investigate the mechanism behind leadership's influence on patient safety culture, sustainability of improvements over time, and the association of change in the patient safety culture measures with change in psychiatric patient safety outcomes. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

Efficacy and Safety of Rapid-Acting Insulin Analogs in Special Populations with Type 1 Diabetes or Gestational Diabetes

DEFF Research Database (Denmark)

Nørgaard, Kirsten; Sukumar, Nithya; Rafnsson, Snorri B

2018-01-01

Med, EMBASE and Cochrane Reviews were searched electronically, and their bibliographies examined to identify suitable studies for review and inclusion in a meta-analysis. Eligible studies were randomized controlled trials that reported data on relevant clinical outcomes. A different reviewer abstracted data...... concerns. Meta-analysis indicated severe hypoglycemic events were comparable for rapid-acting insulin analogs versus RHI (risk difference: 0.00 [95% confidence interval - 0.01; 0.01]). In the pregnancy group, insulin lispro and insulin aspart were safe and effective for both mother and fetus, with glycemic......INTRODUCTION: To assess the efficacy and safety of three available rapid-acting insulin analogs (insulins lispro, aspart and glulisine, respectively) in pregnant women, children/adolescents and people using continuous subcutaneous insulin infusion (CSII) with type 1 diabetes. METHODS: Pub...

14 CFR 1260.37 - Safety.

Science.gov (United States)

2010-01-01

... 14 Aeronautics and Space 5 2010-01-01 2010-01-01 false Safety. 1260.37 Section 1260.37 Aeronautics... Provisions § 1260.37 Safety. Safety October 2000 (a) The Recipient shall act responsibly in matters of safety and shall take all reasonable safety measures in performing under this grant or cooperative agreement...

An AP-2 element acts synergistically with the cyclic AMP- and Phorbol ester-inducible enhancer of the human proenkephalin gene

Energy Technology Data Exchange (ETDEWEB)

Hyman, S.E.; Comb, M.; Pearlberg, J.; Goodman, H.M.

1989-01-01

An enhancer with two DNA elements, one containing the sequence CGTCA, is required for cyclic AMP-and phorbol ester-inducible transcription of the human proenkephalin gene. The authors report that an AP-2 element located adjacent to the enhancer acts synergistically with it to confer maximal response to cyclic AMP and phorbol esters.

77 FR 66639 - Advisory Committee on Construction Safety and Health (ACCSH)

Science.gov (United States)

2012-11-06

... Contract Work Hours and Safety Standards Act (Construction Safety Act) (40 U.S.C. 3701 et seq.) and the.../Women in Construction: 2:15 to 4:15 p.m. The following ACCSH Work Groups will meet November 28, 2012... Occupational Safety and Health Act of 1970 (29 U.S.C. 656), Section 107 of the Contract Work Hours and Safety...

Comparing the Affordable Care Act's Financial Impact on Safety-Net Hospitals in States That Expanded Medicaid and Those That Did Not.

Science.gov (United States)

Dobson, Allen; DaVanzo, Joan E; Haught, Randy; Phap-Hoa, Luu

2017-11-01

Safety-net hospitals play a vital role in delivering health care to Medicaid enrollees, the uninsured, and other vulnerable patients. By reducing the number of uninsured Americans, the Affordable Care Act (ACA) was also expected to lower these hospitals’ significant uncompensated care costs and shore up their financial stability. To examine how the ACA’s Medicaid expansion affected the financial status of safety-net hospitals in states that expanded Medicaid and in states that did not. Using Medicare hospital cost reports for federal fiscal years 2012 and 2015, the authors compared changes in Medicaid inpatient days as a percentage of total inpatient days, Medicaid revenues as a percentage of total net patient revenues, uncompensated care costs as a percentage of total operating costs, and hospital operating margins. Medicaid expansion had a significant, favorable financial impact on safety-net hospitals. From 2012 to 2015, safety-net hospitals in expansion states, compared to those in nonexpansion states, experienced larger increases in Medicaid inpatient days and Medicaid revenues as well as reduced uncompensated care costs. These changes improved operating margins for safety-net hospitals in expansion states. Margins for safety-net hospitals in nonexpansion states, meanwhile, declined.

75 FR 28757 - Security Zone; Potomac River, Washington Channel, Washington, DC

Science.gov (United States)

2010-05-24

... potential terrorist acts, and enhance public and maritime safety and security. The Coast Guard was unable to...-ranking government officials, mitigating potential terrorist acts and enhancing public and maritime safety... terrorist acts and enhancing public and maritime safety and security. Basis and Purpose The Coast Guard will...

Safety Systems

Science.gov (United States)

Halligan, Tom

2009-01-01

Colleges across the country are rising to the task by implementing safety programs, response strategies, and technologies intended to create a secure environment for teachers and students. Whether it is preparing and responding to a natural disaster, health emergency, or act of violence, more schools are making campus safety a top priority. At…

Ex Ante Liability Rules in New Zealand's Health and Safety in Employment Act: A Law and Economics Analysis

OpenAIRE

Paul Gordon; Alan E. Woodfield

2006-01-01

In addition to penalties imposed for breaches of statutory duties in the event of workplace accidents involving physical harms, New Zealand's Health and Safety in Employment Act 1992 also provides for penalties where accidents have not occurred. Ordinary negligence rules are ex post in that both an accident and harm must occur before liability accrues, whereas ex ante liability rules create liability for deficient care per se. This paper examines whether liability for breaches of duty that do...

Ongoing enhancements in the German nuclear regulatory framework with respect to fire safety

Energy Technology Data Exchange (ETDEWEB)

Elsche, Bjoern [e.on Kernkraft, Hannover (Germany); Roewekamp, Marina [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Koeln (Germany); Neugebauer, Wilfried [AREVA NP, Erlangen (Germany); Gersinska, Rainer [Bundesamt fuer Strahlenschutz (BfS), Salzgitter (Germany). KTA-Geschaeftsstelle

2015-12-15

In the recent past, the regulatory framework for nuclear power plants (NPP) in Germany has been updated and enhanced comprising on the one hand comprehensive high level regulatory documents such as the 'Safety Requirements for Nuclear Power Plants' and, on the other hand, revised state-of-the-art nuclear safety standards and rules being incorporated in a corresponding legal structure. A major enhancement concerns the nuclear fire and explosion protection standards being already available as so-called green print for final comments which are expected to be officially published end of 2015. The update became necessary after approx. ten years for better addressing some lessons learnt form the operating experience, the consideration of post- Fukushima insights, such as more systematically addressing event combinations with fires and taking into account deviations from non-nuclear standards for escape and rescue routes. Moreover, fire protections remains an important issue for nuclear power plants in Germany during the longer term post-commercial safe shutdown period before decommissioning during which the spent fuel elements remain either in the containment or in the spent fuel pool for further years requiring suitable fire protection means being in place.

Educating future leaders in patient safety

Science.gov (United States)

Leotsakos, Agnès; Ardolino, Antonella; Cheung, Ronny; Zheng, Hao; Barraclough, Bruce; Walton, Merrilyn

2014-01-01

Education of health care professionals has given little attention to patient safety, resulting in limited understanding of the nature of risk in health care and the importance of strengthening systems. The World Health Organization developed the Patient Safety Curriculum Guide: Multiprofessional Edition to accelerate the incorporation of patient safety teaching into higher educational curricula. The World Health Organization Curriculum Guide uses a health system-focused, team-dependent approach, which impacts all health care professionals and students learning in an integrated way about how to operate within a culture of safety. The guide is pertinent in the context of global educational reforms and growing recognition of the need to introduce patient safety into health care professionals’ curricula. The guide helps to advance patient safety education worldwide in five ways. First, it addresses the variety of opportunities and contexts in which health care educators teach, and provides practical recommendations to learning. Second, it recommends shared learning by students of different professions, thus enhancing student capacity to work together effectively in multidisciplinary teams. Third, it provides guidance on a range of teaching methods and pedagogical activities to ensure that students understand that patient safety is a practical science teaching them to act in evidence-based ways to reduce patient risk. Fourth, it encourages supportive teaching and learning, emphasizing the need to establishing teaching environments in which students feel comfortable to learn and practice patient safety. Finally, it helps educators incorporate patient safety topics across all areas of clinical practice. PMID:25285012

Strengthening the Global Nuclear Safety Regime. INSAG-21. A report by the International Nuclear Safety Group

International Nuclear Information System (INIS)

2014-01-01

The Global Nuclear Safety Regime is the framework for achieving the worldwide implementation of a high level of safety at nuclear installations. Its core is the activities undertaken by each country to ensure the safety and security of the nuclear installations within its jurisdiction. But national efforts are and should be augmented by the activities of a variety of international enterprises that facilitate nuclear safety - intergovernmental organizations, multinational networks among operators, multinational networks among regulators, the international nuclear industry, multinational networks among scientists, international standards setting organizations and other stakeholders such as the public, news media and non-governmental organizations (NGOs) that are engaged in nuclear safety. All of these efforts should be harnessed to enhance the achievement of safety. The existing Global Nuclear Safety Regime is functioning at an effective level today. But its impact on improving safety could be enhanced by pursuing some measured change. This report recommends action in the following areas: - Enhanced use of the review meetings of the Convention on Nuclear Safety as a vehicle for open and critical peer review and a source for learning about the best safety practices of others; - Enhanced utilization of IAEA Safety Standards for the harmonization of national safety regulations, to the extent feasible; - Enhanced exchange of operating experience for improving operating and regulatory practices; and - Multinational cooperation in the safety review of new nuclear power plant designs. These actions, which are described more fully in this report, should serve to enhance the effectiveness of the Global Nuclear Safety Regime

48{sup th} Annual meeting on nuclear technology (AMNT 2017). Key topic / Enhanced safety and operation excellence. Technical session: Operation and safety of nuclear installations, fuel

Energy Technology Data Exchange (ETDEWEB)

Hollands, Thorsten [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH, Garching (Germany). Bereich Reaktorsicherheitsforschung

2017-12-15

The sessions Fuel and Materials and Containment and SFP, as part of the Technical Sessions Operation and Safety of Nuclear Installations, Fuel implemented in the Key Topic Enhanced Safety and Operation Excellence were chaired by Dr. Thorsten Hollands (Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) gGmbH) and Dr. Erwin Fischer (PreussenElektra GmbH) who was the keynote coordinator for the Technical Sessions. Both sessions consist of a keynote lecture followed by technical presentations.

EC6 safety enhancement - including impact of Fukushima lessons learned

Energy Technology Data Exchange (ETDEWEB)

Yu, S.; Zemdegs, R.; Boyle, S.; Soulard, M., E-mail: stephen.yu@candu.com [Candu Energy Inc., Mississauga, Ontario (Canada)

2012-09-15

The Enhanced CANDU 6 (EC6) is the new Generation III CANDU reactor design that meets the most up to date regulatory requirements and customer expectations. EC6 builds on the proven high performance design inch as the Qinshan CANDU 6 units and has made improvements to safety and operational performance, and has incorporated extensive operational feedback including Fukushima. The Fukushima Dai-ichi March 11, 2011 event has demonstrated the importance of defence-in-depth considerations for beyond-design basis events, including severe accidents. The EC6 design is based on the defence-in-depth principles and provides further design features that address the lessons learned from Fukushima. (author)

A trans-acting enhancer modulates estrogen-mediated transcription of reporter genes in osteoblasts.

Science.gov (United States)

Sasaki-Iwaoka, H; Maruyama, K; Endoh, H; Komori, T; Kato, S; Kawashima, H

1999-02-01

The presence of bone-specific estrogen agonists and discovery of the osteoblast-specific transcription factor (TF), Cbfa1, together with the discovery of synergism between a TF Pit-1 and estrogen receptor alpha (ERalpha) on rat prolactin gene, led to investigation of Cbfa1 in the modulation of osteoblast-specific actions of estrogen. Reverse transcribed-polymerase chain reaction demonstrated expression of Cbfa1 in the osteoblastic cell lines, MG63, ROS17/2.8, and MC3T3E1, but not in nonosteoblastic cell lines, MCF7, C3H10T1/2, and HeLa. An ER expression vector and a series of luciferase (Luc) reporter plasmids harboring the Cbfa1 binding site OSE2 (the osteoblast-specific cis element in the osteocalcin promoter) and palindromic estrogen response elements (EREs) were cotransfected into both osteoblastic and nonosteoblastic cells. OSE2 worked as a cis- acting element in osteoblastic cells but not nonosteoblastic cells, whereas EREs were cis- acting in all cell lines. Synergistic transactivation was observed in osteoblastic cells only when both ERE and OSE2 were placed in juxtaposition to the promoter. Forced expression of Cbfa1 in C3H10T1/2 cells also induced synergism. Tamoxifen, a partial agonist/antagonist of estrogen, acted as an osteoblast-specific agonist in cells transfected with a promoter containing ERE and acted synergistically with a promoter containing the ERE-OSE2 enhancer combination. These results support the idea that bone-specific TFs modulate the actions of estrogen in a tissue-specific manner.

7 CFR 1170.2 - Act.

Science.gov (United States)

2010-01-01

... 7 Agriculture 9 2010-01-01 2009-01-01 true Act. 1170.2 Section 1170.2 Agriculture Regulations of... Orders; Milk), DEPARTMENT OF AGRICULTURE DAIRY PRODUCT MANDATORY REPORTING § 1170.2 Act. Act means the Agricultural Marketing Act of 1946, 7 U.S.C. 1621 et seq., as amended by the Dairy Market Enhancement Act of...

77 FR 2450 - Security Zone; Potomac and Anacostia Rivers, Washington, DC

Science.gov (United States)

2012-01-18

... terrorist acts, and enhance public and maritime safety and security. The Coast Guard was unable to publish a... terrorist acts and enhancing public and maritime safety security. Under 5 U.S.C. 553(d)(3), the Coast Guard...-ranking government officials, mitigating potential terrorist acts and enhancing public and maritime safety...

Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident

Directory of Open Access Journals (Sweden)

Sang Ho Kim

2015-01-01

Full Text Available The role of nuclear energy is to supply electric power on a stable basis to meet increasing demands, reduce carbon dioxide emissions, and maintain stable electric power costs while ensuring safety. The Fukushima accident taught us many lessons for creating safer nuclear power plants. Considering the design of systems, the areas of weakness at the Fukushima nuclear power plants can be divided into three categories: plant protection, electricity supply, and cooling of the nuclear fuel. In this paper, focusing on these three areas, the lessons learned are proposed and applied for pressurized heavy water reactors. Firstly, hard protection against external risks ensures the integrity of components and systems such that they can perform their original functions. Secondly, additional emergency power supply systems for electrical redundancy and diversity can improve the response capabilities for an accident by increasing the availability of active components. Thirdly, cooling for removing decay heat can be augmented by adopting diverse safety systems derived from other types of reactors. This study is expected to contribute to the safety enhancement of pressurized heavy water reactors by applying design changes based on the lessons learned from the Fukushima accident.

The NSW Radiation Control Act and regulation

International Nuclear Information System (INIS)

Towson, J.

1994-01-01

The legal control of radiation safety in New South Wales has undergone substantial change in recent years. The long-awaited Regulation to the 1990 Radiation Control Act came into effect on 1 September 1993 (of necessity, as the Regulation to the previous 1957 Radioactive Substances Act expired on that date). It has not met with unanimous acclaim. The Regulation addresses three broad areas, namely - (a) legal controls - licensing, registration, radiation 'experts'; (b) safety matters - workplace management, monitoring, research exposures, transport/disposal, accidents; and (c) miscellaneous -radiation safety officers, committees, penalties, records, This article offers a personal view of the implications for nuclear medicine practice in New South Wales

Exploiting Science: Enhancing the Safety Training of Pilots to Reduce the Risk of Bird Strikes

Science.gov (United States)

Mendonca, Flavio A. C.

Analysis of bird strikes to aviation in the U.S. from 1990 to 2015 indicate that the successful mitigation efforts at airports, which must be sustained, have reduced incidents with damage and a negative effect-on-flight since 2000. However, such efforts have done little to reduce strikes outside the airport jurisdiction, such as occurred with US Airways Flight 1549 in 2009. There are basically three strategies to mitigate the risk of bird strikes: standards set by aviation authorities, technology, and actions by crewmembers. Pilots play an important role as stakeholders in the prevention of bird strikes, especially outside the airport environment. Thus, safety efforts require enhanced risk management and aeronautical decision-making training for flight crews. The purpose of this study was to determine if a safety training protocol could effectively enhance CFR Part 141 general aviation pilots' knowledge and skills to reduce the risk of bird strikes to aviation. Participants were recruited from the Purdue University professional flight program and from Purdue Aviation. The researcher of this study used a pretest posttest experimental design. Additionally, qualitative data were collected through open-ended questions in the pretest, posttest, and a follow-up survey questionnaire. The participants' pretest and posttest scores were analyzed using parametric and nonparametric tests. Results indicated a significant increase in the posttest scores of the experimental group. An investigation of qualitative data showed that the topic "safety management of bird hazards by pilots" is barely covered during the ground and flight training of pilots. Furthermore, qualitative data suggest a misperception of the safety culture tenets and a poor familiarity with the safety risk management process regarding bird hazards. Finally, the researcher presented recommendations for practice and future research.

Applications of nuclear safety probabilistic risk assessment to nuclear security for optimized risk mitigation

Energy Technology Data Exchange (ETDEWEB)

Donnelly, S.K.; Harvey, S.B. [Amec Foster Wheeler, Toronto, Ontario (Canada)

2016-06-15

Critical infrastructure assets such as nuclear power generating stations are potential targets for malevolent acts. Probabilistic methodologies can be applied to evaluate the real-time security risk based upon intelligence and threat levels. By employing this approach, the application of security forces and other protective measures can be optimized. Existing probabilistic safety analysis (PSA) methodologies and tools employed. in the nuclear industry can be adapted to security applications for this purpose. Existing PSA models can also be adapted and enhanced to consider total plant risk, due to nuclear safety risks as well as security risks. By creating a Probabilistic Security Model (PSM), safety and security practitioners can maximize the safety and security of the plant while minimizing the significant costs associated with security upgrades and security forces. (author)

Strengthening the culture of safety and performance in nuclear installations

International Nuclear Information System (INIS)

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

1997-01-01

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

Oxidized Metal Powders for Mechanical Shock and Crush Safety Enhancers; TOPICAL

International Nuclear Information System (INIS)

GARINO, TERRY J.

2002-01-01

The use of oxidized metal powders in mechanical shock or crush safety enhancers in nuclear weapons has been investigated. The functioning of these devices is based on the remarkable electrical behavior of compacts of certain oxidized metal powders when subjected to compressive stress. For example, the low voltage resistivity of a compact of oxidized tantalum powder was found to decrease by over six orders of magnitude during compaction between 1 MPa, where the thin, insulating oxide coatings on the particles are intact, to 10 MPa, where the oxide coatings have broken down along a chain of particles spanning the electrodes. In this work, the behavior of tantalum and aluminum powders was investigated. The low voltage resistivity during compaction of powders oxidized under various conditions was measured and compared. In addition, the resistivity at higher voltages and the dielectric breakdown strength during compaction were also measured. A key finding was that significant changes in the electrical properties persist after the removal of the stress so that a mechanical shock enhancer is feasible. This was verified by preliminary shock experiments. Finally, conceptual designs for both types of enhancers are presented

Distributed fiber optic sensing enhances pipeline safety and security

Energy Technology Data Exchange (ETDEWEB)

Frings, Jochen; Walk, Tobias [ILF Consulting Engineers, Munich (Germany)

2011-09-15

Pipelines are efficient, highly reliable and safe means of transportation. However, despite intensive right of way surveillance by foot, car and out of the air, pipeline leaks and illegal tappings are a reality - sometimes with catastrophic results. These events show a gap in real-time monitoring caused by the highly distributed nature of pipelines. Parts of this gap now can be closed with distributed fiber optic sensing technology. Using various physical effects this technology is apt to detect temperature, strain, vibrations and sound with very good localization over spans up to 50 km with a single sensor cable. Various field tested applications like leakage detection, third party activity monitoring and intrusion detection or ground movement detection as well as integrity monitoring proof that distributed fiber optic sensing can enhance pipeline safety and security. (orig.)

Human Factors and Safety Culture in Maritime Safety (revised

Directory of Open Access Journals (Sweden)

Heinz Peter Berg

2013-09-01

Full Text Available As in every industry at risk, the human and organizational factors constitute the main stakes for maritime safety. Furthermore, several events at sea have been used to develop appropriate risk models. The investigation on maritime accidents is, nowadays, a very important tool to identify the problems related to human factor and can support accident prevention and the improvement of maritime safety. Part of this investigation should in future also be near misses. Operation of ships is full of regulations, instructions and guidelines also addressing human factors and safety culture to enhance safety. However, even though the roots of a safety culture have been established, there are still serious barriers to the breakthrough of the safety management. One of the most common deficiencies in the case of maritime transport is the respective monitoring and documentation usually lacking of adequacy and excellence. Nonetheless, the maritime area can be exemplified from other industries where activities are ongoing to foster and enhance safety culture.

Evaluation of research projects and studies on nuclear safety in the context of implementation of the German Atomic Energy Act (AtG). Vol. 9

International Nuclear Information System (INIS)

Casper, H.

2000-01-01

The content of this report is a collection of research projects and investigations in the field of nuclear safety evaluated in 1999 and 2000 with regard to the application of the Atomic Energy Act (Atomgesetz). In addition the report gives an overview on objectives and procedures used for the evaluation. The purpose of this project, being executed for the Federal Ministry for Environment, Nature Conservation and Nuclear Safety (BMU) of the Federal Republic of Germany is to inform all parties involved in the licensing procedure as well as the consulting councils on the latest nuclear safety research results and the status of their verification in a precise short manner. In addition experts' opinions are given with regard to the relevance of these research results to nuclear rules and guidelines as well as to the execution of the Atomic Energy Act. The information consists of precise and short evaluations of final research reports or technical reports. These evaluations are prepared by specialists who are acquainted with the technical aspects of the licensing procedure of nuclear plants in the Federal Republic of Germany. This volume is the ninth report of this series. (orig.) [de

77 FR 25179 - Patient Safety Organizations: Expired Listing for Medkinetics, LLC

Science.gov (United States)

2012-04-27

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Medkinetics, LLC of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act) authorizes the listing of PSOs, which are entities or component...

A study on method to identify actual causes and conditions of safety rule deviations through analyzing events due to unsafe acts of workers

International Nuclear Information System (INIS)

Hirotsu, Yuko; Takeda, Daisuke

2010-01-01

The purpose of this study is to establish a method to understand actual causes and condition of intentional deviation from safety rules (including norm and written rules that has developed to anticipate, prevent, detect and recover human errors) in an organization by analyzing events due to unsafe acts of workers (human factor events) and to propose effective measures. Firstly, by reviewing literature regarding safety violations, the following two advantages of investigating actual condition of safety rule deviation through human factor event analysis were extracted, such as (a) being able to clarify relationships between deviations, human errors, and events, and (b) being able to identify specific causal factors that influenced the decision to deviate, including acts of people concerned, problems with rules, task demands, environment and management. Next, through the analysis of human factor event data in accordance with existing human error analysis method on the basis of advantages above, the following three requirements for analyzing event data were extracted, such as (a) gathering information such as rules concerning to the work activities related to the human factor events, and whether there are intentional deviations of the rules, (b) gathering information and identify interrelations among causal factors of the intentional deviations, and (c) gathering information on general condition of deviations and the causal factors. (author)

ENHANCED PROACTIVE PLANNING APPROACH: A CRUCIAL TO AN IMPROVED WORKERS’ SAFETY IN WESTERN NIGERIA SMALL SCALE INDUSTRY

Directory of Open Access Journals (Sweden)

H.O. ADEYEMI

2016-12-01

Full Text Available This study evaluated managements’ proactive planning approach (PPA to enhance safety among workers in South-western Nigeria small scale industry (SSI. The main objective was to rate the managements’ efforts at eliminating risk among their employees. By worker participatory and psychological survey approach, three tools were used; workplace observation (visual, management safety culture (questionnaire and managers interviews (oral. The survey included 200 workers, 120 supervisors and 80 managers, in 82 SSI. Four steps to a safety proactive action plans (PAP, (looking for clues, prioritization of identified potential hazard, making improvements to eliminate the risk and follow up, were rated by employees on a scale from 0 to 5. Paired t-test was used to appraise the significant difference between the managers’ mean scores rated by the supervisors and other workers. 77.1% of workers and 64.2% supervisors rated their managers as either “not done at all” or “poorly done”. Workers’ scores for managers PPA had statistically significantly lower ratings (mean=1.09, SEM = 0.22 compared to that of the supervisors rating (mean= 1.55, SEM = 0.32, with t (14 = -1.185, p = 0.784. There is a closed poor performance perception gaps, of managers’ PPA, of the two groups of employees. It can be concluded that safety is not emphasized, by managers of SSI, as overriding priority and this may have contributed to high reported injuries among their workforce. Courses to enhance managements’ understanding for inclusion of safety among the leading priorities becomes necessary. This will reduce work-related risks and promotes occupational safety and health among the group of workers.

The Alternative Design Features for Safety Enhancement in Shutdown Operation

International Nuclear Information System (INIS)

Oh, Hae Cheol; Kim, Myung Ki; Chung, Bag Soon; Seo, Mi Ro

2009-01-01

PSA can be used to confirm that the new plant design is complied with the applicable safety goals, and to select among the alternate design options. A shutdown PSA provides insight for outage planning schedule, outage management practices, and design modifications. Considering the results of both LPSD PSA studies and operating experiences for low power and shutdown, the improvements can be proposed to reduce the high risk contribution. The improvements/enhancements during shutdown operation may be divided into categories such as hardware, administrative management, and operational procedure. This paper presents on an example how the risk related to an accidental situation can be reduced, focusing the hardware design changes for the newly designed NPPs

Regional aviation safety organisations : enhancing air transport safety through regional cooperation

NARCIS (Netherlands)

Ratajczyk, Mikołaj Andrzej

2014-01-01

Aviation safety is of global concern. Yet 43% of countries worldwide lack the expertise and administrative capacity to ensure effective safety oversight of the aviation activities for which they are responsible under international law. With air traffic predicted to double in the next 15 years and

A Secure ECC-based RFID Mutual Authentication Protocol to Enhance Patient Medication Safety.

Science.gov (United States)

Jin, Chunhua; Xu, Chunxiang; Zhang, Xiaojun; Li, Fagen

2016-01-01

Patient medication safety is an important issue in patient medication systems. In order to prevent medication errors, integrating Radio Frequency Identification (RFID) technology into automated patient medication systems is required in hospitals. Based on RFID technology, such systems can provide medical evidence for patients' prescriptions and medicine doses, etc. Due to the mutual authentication between the medication server and the tag, RFID authentication scheme is the best choice for automated patient medication systems. In this paper, we present a RFID mutual authentication scheme based on elliptic curve cryptography (ECC) to enhance patient medication safety. Our scheme can achieve security requirements and overcome various attacks existing in other schemes. In addition, our scheme has better performance in terms of computational cost and communication overhead. Therefore, the proposed scheme is well suitable for patient medication systems.

On-site Consultation Hearings, Occupational Safety and Health Act. Hearings before the Subcommittee on Manpower, Compensation, and Health and Safety of the Committee on Education and Labor, House of Representatives, Ninety-fourth Congress.

Science.gov (United States)

Congress of the U.S., Washington, DC. House Committee on Education and Labor.

The hearings consider a bill, H.R. 8618, to amend the Occupational Safety and Health Act of 1970 (OSHA) which would provide on-site consultative services to employers desiring to comply with OSHA standards. H.R. 8616 was introduced to strengthen OSHA by providing an additional program that would encourage employers to voluntarily comply with…

Enhanced CANDU 6 design assist probabilistic safety assessment results and insights

International Nuclear Information System (INIS)

Torabi, T.; Bettig, R.; Iliescu, P.; Robinson, J.; Santamaura, P.; Skorupska, B.; Tyagi, A.K.; Vencel, I.

2013-01-01

The Enhanced CANDU 6(EC6) is a 700 MWe reactor, which has evolved from the well-established CANDU line of reactors, which are heavy-water moderated, and heavy-water cooled horizontal pressure tube reactors, using natural uranium fuel. The EC6 design retains the generic CANDU design features, while incorporating innovations and state-of-the-art technologies to ensure competitiveness with other design with respect to operation, performance and economics. A design assist probabilistic safety assessment (PSA) was conducted during the design change phase of the project. The purpose of the assessment was to assess internal events during at-power operation and identify the design improvements and additional features needed to comply with the latest regulatory requirements in Canada and compete with other reactor designs, internationally. The PSA results show that the EC6 plant response to the postulated initiating events is well balanced, and the design meets its safety objectives. This paper summarizes the results and insights gained during the development of the PSA models for at-power internal events. (author)

The Influence of Laboratory Safety on Capital Planning.

Science.gov (United States)

Francis, Robert A.

1980-01-01

Discusses state and federal legislation concerning the handling of dangerous materials and its impact on the design of college and university buildings. Lists federal legislation affecting laboratory safety, the objectives of each act, and the influence of each act on laboratory safety. (IRT)

Slovak Republic Act of 1 April 1998 on the peaceful use of nuclear energy and on alterations and amendments to Act No. 174/1968 Zb. on State supervision of work safety as amended by Act of the National Council of the Slovak Republic No. 256/1994 Z.z

International Nuclear Information System (INIS)

1998-01-01

This Act is a part of Report and contains: Part I. Chapter (Ch.) one: Basic provisions; Paragraph (P) 1: Subject of act; P2: Definition of certain terms; P3: Principles of peaceful use of nuclear energy; P4: Conditions for use of nuclear energy; P5: Conditions for issue of authorization; P6: Application for the issue of an authorization; P7: Issue of authorization; P8: Termination and limitation of authorization; P8: Termination and limitation of authorization. Ch.2: Nuclear materials; P9: Nuclear materials, special materials and equipment; P10: Procurement and use of nuclear materials (NM); P11: Transportation of NM; P12: Accounting and control of NM; Ch.3: Nuclear installations, management of radioactive waste and spent nuclear fuel; P13: Nuclear installation (NI); P14: Construction of nuclear installations (NI); P15. Commissioning and operation of NI; P16. Extension of operational lifetime of NI; P17: Radioactive waste management; P18: Management of spent nuclear fuel; P19: Decommissioning of NIs; Ch.4. Nuclear safety and quality assurance; P20: Nuclear safety; P21: Professional qualification; P22: Quality assurance; P23: Physical protection of NIs and NMs; P24. Events at nuclear installations and accidents during transportation of NMs; P25: Emergency planning; Ch.5. P26: Nuclear damage and compensation for such damage; P27: Liability for nuclear damage; P28: Limitation of liability; P29: Meeting of claims for compensation for nuclear damage; P30: Financial cover for nuclear damage liability. Ch.6: NRA SR. P31: Competence of the Authority; P32: The Authority performs the State supervision; P33: The obligations of the authorized persons towards the authority and apprising by the authority of the national organs; P34: Nuclear safety inspectors; P35: Discontinuation of the operating of a NI or its construction. P36: Penalties. Ch.7. Common, temporary and concluding provisions. P37. Relation to administrative procedure; P38: Temporary provisions; P39: Abrogation

Incident factor as a learning aspect to enhance safety culture in the experimental fuel element installation of PTBN - BATAN

International Nuclear Information System (INIS)

Heri Hardiyanti; Agus Sartono; Bambang Herutomo; AS Latief

2013-01-01

The safety of a nuclear facility depends not only on the fulfillment of all technical requirements, but also on the role of non-technical aspects. The primary causation of incidents or accidents in a nuclear facility is human error which is non-technical. Therefore, in order to enhance safety, efforts from the technical aspects are as important as efforts to deal with the human factor which can be done through the application of safety culture in the facility. Incidents that took place in the Experimental Fuel Element Installation (EFEI) of PTBN - BATAN from 2011 to 2012 were caused by aging instruments and human error. In order to prevent accidents and to enhance safety, non-technical efforts that were done in the EFEI were, interalia, the obligations on all personnel to attend the pre-lab briefing, to prepare a work proposal, to compose a HIRADC (hazard identification, risk assessment, and determining control) document, to utilize self protection devices, to perform a routine maintenance, and to practice safe behavior. All personnel were involved in all those efforts. Safety is the first priority and can always be improved in the facility. A strong commitment of and cooperation between the top management and the staff are needed. (author)

The Study of Implement of HCS Program at Hazardous Chemicals Knowledge and Safety performance in Tehran refinery, s laboratory unit

Directory of Open Access Journals (Sweden)

N. Hassanzadeh-Rangi

2008-10-01

Full Text Available Background and aims   The HCS standard includes listing of chemicals, labeling of chemical  containers, preparation of material safety data sheets, writing plan and employee training  programs. The aim of this study was to determine the influence of implemented program to enhance the knowledge and safety performance level of employees.   Methods   The knowledge level and unsafe act ratio were measured using both questionnaire  and behavior checklist (with safety sampling method before and after enforcing this interface.   Results   In this study, the mean and standard deviation of the knowledge level of employees  related to chemical safety before enforcing the interface was 46% and 14%. However, after  enforcing the interface, mean and standard deviation was 88% and 12%. The paired-t-test result   in this parameter was significant (p-value <0.0001. The mean and standard deviation of  knowledge level of employees related to warning labels before to enforcing the interface was 29%  and 22%. After enforcing the interface, mean and standard deviation was 80% and 16%. The paired-t-test result in this parameter was significant (p-value <0.0001. The mean and standard  deviation of the knowledge level of employees related to hazard communication methods before enforcing the interface was 25% and 11%. After enforcing the interface, mean and standard deviation was 79% and 16%. The paired-t-test result in this parameter was significant (p-value   <0.001.   Conclusion   The obtained result revealed that enhancement of the knowledge related to chemical safety, hazard communication methods and warning labels was significant. Statistical paired-t-test and control chart methods was used to comparison between unsafe act ratio before  and after enforcing the interface. The mean and standard deviation of unsafe act ratio before implementation of HCS program was 23.6% and 5.49%. However, mean and standard deviation of unsafe act ratio

76 FR 60495 - Patient Safety Organizations: Voluntary Relinquishment From Illinois PSO

Science.gov (United States)

2011-09-29

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... voluntary relinquishment from the Illinois PSO of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b...

75 FR 57048 - Patient Safety Organizations: Voluntary Delisting

Science.gov (United States)

2010-09-17

... Organizations: Voluntary Delisting AGENCY: Agency for Healthcare Research and Quality (AHRQ), HHS. ACTION... Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109... the listing of PSOs, which are entities or component organizations whose mission and primary activity...

20 CFR 638.803 - Safety.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 3 2010-04-01 2010-04-01 false Safety. 638.803 Section 638.803 Employees... THE JOB TRAINING PARTNERSHIP ACT Administrative Provisions § 638.803 Safety. (a) The Job Corps... shall be assigned to such jobs or training in accordance with appropriate health and safety practices...

Quality and safety of products containing Ephedra Herba on the Dutch market

OpenAIRE

Lake OA; Slijkhuis C; Maas WF; Vliet MEA van; Kaste D de; Verdonk-Kleinjan W; Keuringsdienst van Waren, regio Zuid; LGO

2001-01-01

We performed analytical studies on dietary supplements and smart products containing Ephedra herba on the Dutch market. Such products are labelled 'from natural, herbal sources' and do not fall under Dutch Medicines Act. Most of the samples tested from 1993 to 1999 contained unacceptably large amounts of ephedrine (EP) alkaloids (the active substances of Ephedra herba) in relation to the safety criteria in the literature. Some samples also contained an effect-enhancing substance (e.g. coffein...

Priority ranking of safety-related systems for structural enhancement assessment at Savannah River Site

International Nuclear Information System (INIS)

Kao, G.C.; Daugherty, W.L.; Barnes, D.M.

1992-09-01

In order to extend the service life of safety related structures and systems in a logical manner, a Structural Enhancement Program was initiated to evaluate the structural integrity of eight (8) systems, namely: Cooling Water System, Emergency Cooling System, Moderator Recovery System supplementary Safety System, Water Removal System, Service Raw Water System, Service Clarified Water System, and River Water System. Since the level of importance of each system to reactor operations varies from one system to another, the scope of structural integrity evaluation for each system should be prioritized accordingly. This paper presents the assessment of system priority for structural evaluation based on a ranking methodology and specifies the level of structural evaluation consistent with the established priority. The effort was undertaken by a five-member panel representing four (4) major disciplines, including. structures, reactor engineering/operations, risk management and materials. The above systems were divided into a total of thirty-five (35) subsystem. These subsystems were then ranked with six (6) attributes, namely: Safety Classification, Degradation Mechanisms, Difficulty of Replacement, Failure Mode, Radiation Dose to Workers and Consequence of Failure. Each attribute was assigned a set of consequences or events with corresponding weighting scores. The results of the ranking process yielded two groups of subsystems, categorized as Priority I and II subsystems. The level of structural assessment was then formulated accordingly. The prioritized approach will allow more efficient allocation of resources, so that the Structural Enhancement Program can be implemented in a cost-effective and efficient manner

Stakeholder Transportation Scorecard: Reviewing Nevada's Recommendations for Enhancing the Safety and Security of Nuclear Waste Shipments - 13518

Energy Technology Data Exchange (ETDEWEB)

Dilger, Fred C. [Black Mountain Research, Henderson, NV 81012 (United States); Ballard, James D. [Department of Sociology, California State University, Northridge, CA 91330 (United States); Halstead, Robert J. [State of Nevada Agency for Nuclear Projects, Carson City, NV 80906 (United States)

2013-07-01

As a primary stakeholder in the Yucca Mountain program, the state of Nevada has spent three decades examining and considering national policy regarding spent nuclear fuel and high-level radioactive waste transportation. During this time, Nevada has identified 10 issues it believes are critical to ensuring the safety and security of any spent nuclear fuel transportation program, and achieving public acceptance. These recommendations are: 1) Ship the oldest fuel first; 2) Ship mostly by rail; 3) Use dual-purpose (transportable storage) casks; 4) Use dedicated trains for rail shipments; 5) Implement a full-scale cask testing program; 6) Utilize a National Environmental Policy Act (NEPA) process for the selection of a new rail spur to the proposed repository site; 7) Implement the Western Interstate Energy Board (WIEB) 'straw man' process for route selection; 8) Implement Section 180C assistance to affected States, Tribes and localities through rulemaking; 9) Adopt safety and security regulatory enhancements proposed states; and 10) Address stakeholder concerns about terrorism and sabotage. This paper describes Nevada's proposals in detail and examines their current status. The paper describes the various forums and methods by which Nevada has presented its arguments and sought to influence national policy. As of 2012, most of Nevada's recommendations have been adopted in one form or another, although not yet implemented. If implemented in a future nuclear waste program, the State of Nevada believes these recommendations would form the basis for a successful national transportation plan for shipments to a geologic repository and/or centralized interim storage facility. (authors)

Radiation Act, promulgated on May 8,1997

International Nuclear Information System (INIS)

1997-01-01

The Radiation Act was passed by the Estonian Parliament on 23 Apr 1997 and promulgated by the President on 8 May 1997. It is the principal legal instrument in the field of radiation protection for workers, the public and the environment. The Act is based on the concepts, principles, terminology and dose limits stipulated in the Basic Safety Standards (IAEA Safety Series No. 115-1) and the EC Directive 96/29/EURATOM. The Radiation Act defines the institutional framework for, and establishes the rules applicable to, the use of ionising radiation, the detention of radiation sources, the transport of radioactive materials, radioactive waste disposal and other activities which cause or may cause harm to health or to the environment. It also contains some general provisions on radioactive waste management, import and export of such wastes and the prohibition against importing radioactive waste for disposal purposes. The Act deals solely with radiation protection; all other nuclear activities are to be covered by other specific laws. The Estonian Radiation Protection Centre is empowered under the Act to inspect sources of radiation exposure and to register dose and source data. It is generally responsible for enforcing the provisions of the Act, although the details of the medical checks for radiation workers are governed by rules established by the Minister for Social Affairs. Chapter 3 of the Radiation Act contains detailed provisions on dose limits for the following categories of exposure to ionising radiation. The Act provides that Government and nominated Ministers be empowered to enact implementing regulations on exemption levels, requirements to ensure observance of the stipulated dose limits, qualification procedures for radiation workers, medical checks of radiation workers, medical applications of ionising radiation, packaging and safety procedures for radiation sources and rules for handling radioactive waste

The Safety of Using High Frequency, Low Intensity Ultrasound to Enhance Thrombolysis

International Nuclear Information System (INIS)

Soltani, Azita

2006-01-01

The EKOS Ultrasound Infusion Systems (EKOS Corporation, Bothell, WA) use high frequency, low intensity ultrasound to accelerate thrombolysis by enhancing clot permeability and lytic drug penetration into thrombus. These systems are designed to provide efficacious catheter-directed treatment for the management of stroke, peripheral arterial occlusion and deep vein thrombosis. The in vitro and in vivo results of investigating the stability of therapeutic and diagnostic compounds used in combination with EKOS devices, the potential for adverse biological effects and the clot fragmentation confirmed the safety of EKOS ultrasound infusion systems in thrombolysis treatment

Development and implementation of a hospital-based patient safety program

International Nuclear Information System (INIS)

Frush, Karen S.; Alton, Michael; Frush, Donald P.

2006-01-01

Evidence from numerous studies indicates that large numbers of patients are harmed by medical errors while receiving health-care services in the United States today. The 1999 Institute of Medicine report on medical errors recommended that hospitals and health-care agencies ''establish safety programs to act as a catalyst for the development of a culture of safety'' [1]. In this article, we describe one approach to successful implementation of a hospital-based patient safety program. Although our experience at Duke University Health System will be used as an example, the needs, principles, and solutions can apply to a variety of other health-care practices. Key components include the development of safety teams, provision of tools that teams can use to support an environment of safety, and ongoing program modification to meet patient and staff needs and respond to changing priorities. By moving patient safety to the forefront of all that we do as health-care providers, we can continue to improve our delivery of health care to children and adults alike. This improvement is fostered when we enhance the culture of safety, develop a constant awareness of the possibility of human and system errors in the delivery of care, and establish additional safeguards to intercept medical errors in order to prevent harm to patients. (orig.)

Perceived safety management practices in the logistics sector.

Science.gov (United States)

Auyong, Hui-Nee; Zailani, Suhaiza; Surienty, Lilis

2016-03-09

Malaysia's progress on logistics has been slowed to keep pace with its growth in trade. The Government has been pressing companies to improve the safety of their activities in order to reduce society's loss due to occupational accidents and illnesses. Occupational safety and health is a crucial part of a workplace because every worker has to take care of his/her own safety and health. The main occupational safety and health (OSH) national policy in Malaysia is the enactment of the Occupational Safety and Health Act (OSHA) 1994. Only those companies which have excellent health and safety care have good quality and productive employees. This study investigated safety management practices in the logistics sector. The present study is concerned with the human factors to safety in the logistics industry. The authors examined the perceived safety management practices of workers in the logistics sector. The purpose was to identify the perception of safety management practices of Malaysian logistics personnel. Survey questionnaires were distributed to assess logistics personnel about management commitment. The quantitative method using the availability sampling method was applied. The data gathered from the survey were analysed using SPSS software. The responses to the survey were rated according to the Likert scale type, with '1' indicating strongly disagree and '5' indicating strongly agree. One hundred and three employees of logistics functions completed the survey. The highest mean scores were found for fire apparatus, prioritisation of safety, and safety policy. The results from this study also emphasise the importance of the management's commitment in enhancing workplace safety. Specifically, companies should maintain good relations between the employer and the employee to help reduce workplace injuries.

No nuclear safety without security

International Nuclear Information System (INIS)

Anon.

2016-01-01

ead of Health and Safety - Nuclear Safety and Corporate Security at ENGIE Benelux, Pierre Doumont has the delicate job of defining and implementing measures, including cybersecurity, to prevent the risk of malevolent acts against tangible and intangible assets. He gives some hints on the contribution of nuclear security to safety.

Food Safety and Sanitary Practices of Selected Hotels in Batangas Province, Philippines: Basis of Proposed Enhancement Measures

Directory of Open Access Journals (Sweden)

April M. Perez

2017-02-01

Full Text Available This study assessed the extent of food safety and sanitary practices of selected hotels in Batangas province as basis of proposed enhancement measures. The study utilized descriptive method to describe food safety and sanitary practices of selected hotels in Batangas province with a total of 8 hotels (256 respondents. Purposive sampling was used in the study. The questionnaires were designed using the provision of the Sanitation Code of the Philippines, validated and finalized to come up with legitimate results. The study showed that there were eight (8 hotel respondents classified as two, three, four star with considerable years of experience and adequate number of employees. The hotels demonstrated the food safety and sanitary practices always in the areas of restaurant, bar service, catering and banquet and room service. The significant pair-wise comparison for restaurant, bar service, catering and banquet and room service shows that 2 star hotels greatly differs. The researcher recommends that the management should maintain high standard of food safety and sanitary practices among its staff, upgrade the food safety and sanitary practices for food safety accreditation, continuous training of the hotel managers/employees on food safety and sanitary practices.

Enhancing the Safety, Security and Resilience of ICT and Scada Systems Using Action Research

Science.gov (United States)

Johnsen, Stig; Skramstad, Torbjorn; Hagen, Janne

This paper discusses the results of a questionnaire-based survey used to assess the safety, security and resilience of information and communications technology (ICT) and supervisory control and data acquisition (SCADA) systems used in the Norwegian oil and gas industry. The survey identifies several challenges, including the involvement of professionals with different backgrounds and expertise, lack of common risk perceptions, inadequate testing and integration of ICT and SCADA systems, poor information sharing related to undesirable incidents and lack of resilience in the design of technical systems. Action research is proposed as a process for addressing these challenges in a systematic manner and helping enhance the safety, security and resilience of ICT and SCADA systems used in oil and gas operations.

78 FR 30937 - National Advisory Committee on Occupational Safety and Health (NACOSH)

Science.gov (United States)

2013-05-23

... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2013-0015] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... meeting is open to the public. Section 7(a) of the Occupational Safety and Health Act of 1970 (OSH Act...

Strengthening the culture of safety and performance in nuclear installations

Energy Technology Data Exchange (ETDEWEB)

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

1997-07-01

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

Australian radiation protection and nuclear safety (consequential amendments) Bill 1998. Explanatory memorandum

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-31

The purpose of this Bill is to make consequential changes to the Australian Nuclear Science and Technology Organisation Act 1987 (the ANSTO Act) and to provide for transitional arrangements to cover the operation of controlled facilities and the handling of radiation sources while applications for licences to cover these facilities and activities are being made under the proposed Australian Radiation Protection and Nuclear Safety Act 1998 (the ARPANS Act) For this purpose, the Bill: (a) repeals Parts VI and VII A of the ANSTO Act under which, respectively, the Safety Review Committee and the Nuclear Safety Bureau are established, as the functions of the Committee and Bureau will be transferred to the CEO of the Australian Radiation Protection and Nuclear Safety Agency, established under the ARPANS Act; (b) makes transitional arrangements for the transfer of the assets and liabilities of the Nuclear Safety Bureau to the Commonwealth, and confers on the CEO of ARPANSA the powers of the Director of the Nuclear Safety Bureau in relation to the Australian Nuclear Science and Technology Organisation during the transitional period before the offenses provisions commence to operate under the ARPANS Act; (c) repeals the Environment Protection (Nuclear Codes) Act 1978. That Act provides for the development and endorsement of Codes of Practice which will be undertaken under the auspices of ARPANSA; (d) provides that Commonwealth entities have a transition period of 6 months after the ARPANS Act commences to apply for a licence to authorize specified activities under that Act

Australian radiation protection and nuclear safety (consequential amendments) Bill 1998. Explanatory memorandum

International Nuclear Information System (INIS)

1998-01-01

The purpose of this Bill is to make consequential changes to the Australian Nuclear Science and Technology Organisation Act 1987 (the ANSTO Act) and to provide for transitional arrangements to cover the operation of controlled facilities and the handling of radiation sources while applications for licences to cover these facilities and activities are being made under the proposed Australian Radiation Protection and Nuclear Safety Act 1998 (the ARPANS Act) For this purpose, the Bill: (a) repeals Parts VI and VII A of the ANSTO Act under which, respectively, the Safety Review Committee and the Nuclear Safety Bureau are established, as the functions of the Committee and Bureau will be transferred to the CEO of the Australian Radiation Protection and Nuclear Safety Agency, established under the ARPANS Act; (b) makes transitional arrangements for the transfer of the assets and liabilities of the Nuclear Safety Bureau to the Commonwealth, and confers on the CEO of ARPANSA the powers of the Director of the Nuclear Safety Bureau in relation to the Australian Nuclear Science and Technology Organisation during the transitional period before the offenses provisions commence to operate under the ARPANS Act; (c) repeals the Environment Protection (Nuclear Codes) Act 1978. That Act provides for the development and endorsement of Codes of Practice which will be undertaken under the auspices of ARPANSA; (d) provides that Commonwealth entities have a transition period of 6 months after the ARPANS Act commences to apply for a licence to authorize specified activities under that Act

Food Safety and Raw Milk

Science.gov (United States)

... and Food Safety Food Safety Modernization Act Raw Milk Recommend on Facebook Tweet Share Compartir RAW MILK ... Decide? Questions & Answers Outbreak Studies Resources & Publications Raw Milk Infographic [PDF – 1 page] More Resources 5 Raw ...

76 FR 51255 - Security Zone; Potomac River, Georgetown Channel, Washington, DC

Science.gov (United States)

2011-08-18

... officials, mitigate potential terrorist acts, and enhance public and maritime safety and security. The Coast... officials, mitigating potential terrorist acts and enhancing public and maritime safety security. Under 5 U... and enhancing public and maritime safety and security. Background and Purpose The President of the...

Evaluation of the relationship between unsafe acts and occupational accidents in a vehicle manufacturing

Directory of Open Access Journals (Sweden)

F. Fatemi

2008-10-01

Full Text Available Background and aims   Vehicle manufacturing industries are as critical sites from points of safety. Unsafe acts and unsafe conditions have been recognized as effective factors in increasing the risk of occupational accidents. In order to promote of safety conditions, it's necessary to evaluate unsafe acts of workers as the main reason of accidents. The main goal of research is evaluation of relationship between unsafe Acts with occupational accidents.   Methods   Safety behavior sampling (SBS technique was employed to conduct this study. After doing a pilot study, the number of samples and views were determined 195 and 3456  respectively. The information was then analyzed using Excel, SPSS and statistic tests.   Results   The results of the study showed that the rate of unsafe acts of studying workers was  35.4% .The study of the relationship between unsafe acts and occupational accidents via Regression Logistic test showed that if one percent increases on unsafe acts, the rate of accidents  multiply three.   Conclusion   Therefore in view of this significant correlation between unsafe acts and  occupational accidents and kind of unsafe acts, reducing or eliminating requires the investment and implementation of a program. It should be associated with behavioral safety principles and emphasis should be placed on implementing safety culture fundamentals at all organizational levels.

77 FR 26280 - Patient Safety Organizations: Voluntary Relinquishment From CareRise LLC

Science.gov (United States)

2012-05-03

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... relinquishment from CareRise LLC of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act) authorizes the listing of PSOs, which are entities or...

77 FR 62536 - National Advisory Committee on Occupational Safety and Health (NACOSH)

Science.gov (United States)

2012-10-15

... DEPARTMENT OF LABOR Occupational Safety and Health Administration [Docket No. OSHA-2012-0019] National Advisory Committee on Occupational Safety and Health (NACOSH) AGENCY: Occupational Safety and... Section 7(a) of the Occupational Safety and Health Act of 1970 (OSH Act) (29 U.S.C. 651, 656) to advise...

Administration of the Radiation Control for Health and Safety Act of 1968, Public Law 90-602, April 1, 1975. Annual report, Jan--Dec 1974

International Nuclear Information System (INIS)

1974-01-01

The Secretary of Health, Education, and Welfare is required, Subpart 3, Section 2, Part F of Title III of the Public Health Service Act; 42 USC et seq. (Public Law 90-602), to submit an annual report to the President for transmittal to the Congress on or before April 1 on the adminstration of the Radiation Control for Health and Safety Act. The detailed information required to be included in the report is outlined in Section 360D of Public Law 90-602. The Food and Drug Administration, through its Bureau of Radiological Health, has been delegated the authority for the day-to-day administration of the Act. This report covers the detailed operation of the Agency in carrying out that responsibility for calendar year 1974

Safety enhancement concept for NPP of new generation with VVER reactors

International Nuclear Information System (INIS)

Bezlepkin, V.; Kukhtevich, I.; Semashko, S.; Svetlov, S.; Solodovnikov, A.

2004-01-01

With the present day conditions, in order to successfully promote new NPP designs in the electric power markets, it is necessary to ensure enhanced technical/economic performances provided that international safety requirements are properly adhered to. When compared with high-powered nuclear power plants, NPP VVER-640 design (medium powered) possesses a number of advantages for the regions with undeveloped energy systems. Reduced specific energy intensity of the core adopted in this type of reactor allows to ensure the emergency cooldown of the reactor plant by passive means and to minimize the 'human factor' risk and external effects and provide sound substantiations as to how to retain corium inside RPV in case of severe accidents. At the same time, high-powered NPPs seem to be promising for regions with developed energy systems. Among such designs, NPP VVER-1000 and VVER-1500 designs are the most desirable. Configuration of new generation NPP with VVER-1500 is to be selected based on the gained experience in designing NPPs of previous generations considering the latest safety requirements and situation in the domestic and global energy markets for the time being and in the short run. Recent IAEA publications and latest EUR requirements insist that the following key safety indices should be established for new NPP designs: - aggregated frequency of core melting is 10 -6 (1/year); - frequency of maximum accident release is 10 -7 (1/year). To meet the aforementioned criteria, it is necessary to implement some safety assurance principles recommended by IAEA (in-depth defence, single failure, redundancy, diversity, etc.), application of deterministic and probabilistic methods for selection of safety assurance activities and means and use of reasonable combination of active and passive systems. Application of VVER-640 concept to high-powered NPPs seems to be a formidable task due to a number of reasons, namely, it is quite difficult to carry out cooldown process

Integration of the advanced transparency framework to advanced nuclear systems : enhancing Safety, Operations, Security and Safeguards (SOSS)

International Nuclear Information System (INIS)

Mendez, Carmen Margarita; Rochau, Gary Eugene; Cleary, Virginia D.

2008-01-01

The advent of the nuclear renaissance gives rise to a concern for the effective design of nuclear fuel cycle systems that are safe, secure, nonproliferating and cost-effective. We propose to integrate the monitoring of the four major factors of nuclear facilities by focusing on the interactions between Safeguards, Operations, Security, and Safety (SOSS). We proposed to develop a framework that monitors process information continuously and can demonstrate the ability to enhance safety, operations, security, and safeguards by measuring and reducing relevant SOSS risks, thus ensuring the safe and legitimate use of the nuclear fuel cycle facility. A real-time comparison between expected and observed operations provides the foundation for the calculation of SOSS risk. The automation of new nuclear facilities requiring minimal manual operation provides an opportunity to utilize the abundance of process information for monitoring SOSS risk. A framework that monitors process information continuously can lead to greater transparency of nuclear fuel cycle activities and can demonstrate the ability to enhance the safety, operations, security and safeguards associated with the functioning of the nuclear fuel cycle facility. Sandia National Laboratories (SNL) has developed a risk algorithm for safeguards and is in the process of demonstrating the ability to monitor operational signals in real-time though a cooperative research project with the Japan Atomic Energy Agency (JAEA). The risk algorithms for safety, operations and security are under development. The next stage of this work will be to integrate the four algorithms into a single framework

Safety culture: modern slogan or effective contribution to safety?

International Nuclear Information System (INIS)

Salm, M.

1994-01-01

Safety culture is defined and its impact on nuclear power plants is documented using the words of the INSAG of IAEA. Two examples from the field of aviation and space flight testify, that the upper management, by its sheer image, may considerably influence actions of the lower levels of the hierarchy. Management therefore can do a lot more for safety than is commonly assumed. Two examples, although separated by 57 years, show that the mentioned influence remains unchanged inspire of progress in management- and organisation-methods as well as in safety-engineering. Safety culture is an overriding element of safety, acting at all levels of a hierarchy. Its action is most important on those levels, for which precise reglementation is hardly possible. The chain of technical and organisational measures guarantees safety only under the condition, that it is embedded in 'safety culture'. Safety culture therefore merits our full attention. (author) 1 fig

76 FR 74788 - Patient Safety Organizations: Voluntary Relinquishment From HealthWatch, Inc.

Science.gov (United States)

2011-12-01

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... relinquishment from HealthWatch, Inc. of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21--b-26...

76 FR 7853 - Patient Safety Organizations: Voluntary Delisting From HealthDataPSO

Science.gov (United States)

2011-02-11

... Medical Error Management, LLC, of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21--b-26... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety...

Safety Teams: An Approach to Engage Students in Laboratory Safety

Science.gov (United States)

Alaimo, Peter J.; Langenhan, Joseph M.; Tanner, Martha J.; Ferrenberg, Scott M.

2010-01-01

We developed and implemented a yearlong safety program into our organic chemistry lab courses that aims to enhance student attitudes toward safety and to ensure students learn to recognize, demonstrate, and assess safe laboratory practices. This active, collaborative program involves the use of student "safety teams" and includes…

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

International Nuclear Information System (INIS)

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

2014-04-01

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

Thermal safety of ultrasound-enhanced ocular drug delivery: A modeling study

Energy Technology Data Exchange (ETDEWEB)

Nabili, Marjan, E-mail: mnabili@gwmail.gwu.edu [Department of Electrical and Computer Engineering, The George Washington University, 800 22nd Street NW, Room 5000, Washington, DC 20052 (United States); Geist, Craig, E-mail: cgeist@mfa.gwu.edu, E-mail: zderic@gwu.edu [Department of Ophthalmology, The George Washington University, 2150 Pennsylvania Avenue NW, Floor 2A, Washington, DC 20037 (United States); Zderic, Vesna, E-mail: cgeist@mfa.gwu.edu, E-mail: zderic@gwu.edu [Department of Biomedical Engineering, The George Washington University, 800 22nd Street NW, Room 6670, Washington, DC 20052 (United States)

2015-10-15

Purpose: Delivery of sufficient amounts of therapeutic drugs into the eye for treatment of various ocular diseases is often a challenging task. Ultrasound was shown to be effective in enhancing ocular drug delivery in the authors’ previous in vitro and in vivo studies. Methods: The study reported here was designed to investigate the safety of ultrasound application and its potential thermal effects in the eye using PZFlex modeling software. The safety limit in this study was set as a temperature increase of no more than 1.5 °C based on regulatory recommendations and previous experimental safety studies. Acoustic and thermal specifications of different human eye tissues were obtained from the published literature. The tissues of particular interest in this modeling safety study were cornea, lens, and the location of optic nerve in the posterior eye. Ultrasound application was modeled at frequencies of 400 kHz–1 MHz, intensities of 0.3–1 W/cm{sup 2}, and exposure duration of 5 min, which were the parameters used in the authors’ previous drug delivery experiments. The baseline eye temperature was 37 °C. Results: The authors’ results showed that the maximal tissue temperatures after 5 min of ultrasound application were 38, 39, 39.5, and 40 °C in the cornea, 39.5, 40, 42, and 43 °C in the center of the lens, and 37.5, 38.5, and 39 °C in the back of the eye (at the optic nerve location) at frequencies of 400, 600, 800 kHz, and 1 MHz, respectively. Conclusions: The ocular temperatures reached at higher frequencies were considered unsafe based on current recommendations. At a frequency of 400 kHz and intensity of 0.8 W/cm{sup 2} (parameters shown in the authors’ previous in vivo studies to be optimal for ocular drug delivery), the temperature increase was small enough to be considered safe inside different ocular tissues. However, the impact of orbital bone and tissue perfusion should be included in future modeling efforts to determine the safety

Thermal safety of ultrasound-enhanced ocular drug delivery: A modeling study

International Nuclear Information System (INIS)

Nabili, Marjan; Geist, Craig; Zderic, Vesna

2015-01-01

Purpose: Delivery of sufficient amounts of therapeutic drugs into the eye for treatment of various ocular diseases is often a challenging task. Ultrasound was shown to be effective in enhancing ocular drug delivery in the authors’ previous in vitro and in vivo studies. Methods: The study reported here was designed to investigate the safety of ultrasound application and its potential thermal effects in the eye using PZFlex modeling software. The safety limit in this study was set as a temperature increase of no more than 1.5 °C based on regulatory recommendations and previous experimental safety studies. Acoustic and thermal specifications of different human eye tissues were obtained from the published literature. The tissues of particular interest in this modeling safety study were cornea, lens, and the location of optic nerve in the posterior eye. Ultrasound application was modeled at frequencies of 400 kHz–1 MHz, intensities of 0.3–1 W/cm 2 , and exposure duration of 5 min, which were the parameters used in the authors’ previous drug delivery experiments. The baseline eye temperature was 37 °C. Results: The authors’ results showed that the maximal tissue temperatures after 5 min of ultrasound application were 38, 39, 39.5, and 40 °C in the cornea, 39.5, 40, 42, and 43 °C in the center of the lens, and 37.5, 38.5, and 39 °C in the back of the eye (at the optic nerve location) at frequencies of 400, 600, 800 kHz, and 1 MHz, respectively. Conclusions: The ocular temperatures reached at higher frequencies were considered unsafe based on current recommendations. At a frequency of 400 kHz and intensity of 0.8 W/cm 2 (parameters shown in the authors’ previous in vivo studies to be optimal for ocular drug delivery), the temperature increase was small enough to be considered safe inside different ocular tissues. However, the impact of orbital bone and tissue perfusion should be included in future modeling efforts to determine the safety of this

Nuclear Reactor RA Safety Report, Vol. 14, Safety protection measures

International Nuclear Information System (INIS)

1986-11-01

Nuclear reactor accidents can be caused by three type of errors: failure of reactor components including (1) control and measuring instrumentation, (2) errors in operation procedure, (3) natural disasters. Safety during reactor operation are secured during its design and construction and later during operation. Both construction and administrative procedures are applied to attain safe operation. Technical safety features include fission product barriers, fuel elements cladding, primary reactor components (reactor vessel, primary cooling pipes, heat exchanger in the pump), reactor building. Safety system is the system for safe reactor shutdown and auxiliary safety system. RA reactor operating regulations and instructions are administrative acts applied to avoid possible human error caused accidents [sr

78 FR 17212 - Patient Safety Organizations: Voluntary Relinquishment From QAISys, Inc.

Science.gov (United States)

2013-03-20

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21-- b-26, provides for the formation of...

78 FR 70560 - Patient Safety Organizations: Voluntary Relinquishment From GE-PSO

Science.gov (United States)

2013-11-26

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety...), HHS. ACTION: Notice of delisting. SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21-b-26, provides for the formation of Patient...

Aviation safety and ICAO

NARCIS (Netherlands)

Huang, Jiefang

2009-01-01

The thesis addresses the issue of aviation safety under the rule of law. Aviation safety is a global concern. While air transport is considered a safe mode of travel, it is susceptible to inherent risks of flight, the use of force, and terrorist acts. Consequently, within the framework of the

TPE upgrade for enhancing operational safety and improving in-vessel tritium inventory assessment in fusion nuclear environment

Energy Technology Data Exchange (ETDEWEB)

Shimada, M., E-mail: Masashi.Shimada@inl.gov [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Taylor, C.N.; Moore-McAteer, L.; Pawelko, R.J. [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID 83415 (United States); Kolasinski, R.D.; Buchenauer, D.A. [Sandia National Laboratories, Hydrogen and Materials Science Department, Livermore, CA 94550 (United States); Cadwallader, L.C.; Merrill, B.J. [Fusion Safety Program, Idaho National Laboratory, Idaho Falls, ID 83415 (United States)

2016-11-01

The Tritium Plasma Experiment (TPE) is a unique high-flux linear plasma device that can handle beryllium, tritium, and neutron-irradiated plasma facing materials, and is the only existing device dedicated to evaluate in-vessel tritium inventory in the nuclear environment for fusion safety. The electrical upgrade were recently carried out to enhance operational safety and to improve plasma performance. New DC power supplies and a new control center enable remote plasma operations from outside of the contamination area for tritium, minimizing the possible exposure risk with tritium and beryllium and eliminating heat stress issue. In November 2015, the TPE successfully achieved first deuterium plasma via remote operation after a significant three-year upgrade. Simple linear scaling estimate showed that the TPE is expected to achieve Γ{sub i}{sup max} of >1.0 × 10{sup 23} m{sup −2} s{sup −1} and q{sub heat} of >1 MW m{sup −2} with new power supplies. This upgrade not only improves operational safety of the worker, but also enhances plasma performance to better simulate extreme plasma-material conditions expected in ITER, FNSF, and DEMO for improving in-vessel tritium inventory assessment in fusion nuclear environment.

Outline of the Fukushima Daiichi Accident. Lessons Learned and Safety Enhancements

Science.gov (United States)

Hirano, Masashi

2017-09-01

Abstract. On March 11, 2011, an earthquake and subsequent tsunamis off the Pacific coastline of Japan's Tohoku region caused widespread devastation in Japan. As of June 10, 2016, it is reported that a total of 15,894 people lost their lives and 2,558 people are still unaccounted for. In Fukushima Prefecture, approximately 100,000 people are still obliged to live away from their homes due to the earthquake and tsunami as well as the Fukushima Daiichi accident. On the day, the earthquake and tsunami caused severe damages to the Tokyo Electric Power Company (TEPCO)'s Fukushima Daiichi Nuclear Power Station (NPS). All the units in operation, namely Units 1 to 3, were automatically shut down on seismic reactor protection system trips but the earthquake led to the loss of all off-site electrical power supplies to that site. The subsequent tsunami inundated the site up to 4 to 5 m above its ground level and caused, in the end, the loss of core cooling function in Units 1 to 3, resulting in severe core damages and containment vessel failures in these three units. Hydrogen was released from the containment vessels, leading to explosions in the reactor buildings of Units 1, 3 and 4. Radioactive materials were released to the atmosphere and were deposited on the land and in the ocean. One of the most important lessons learned is an importance to prevent such large scale common cause failures due to extreme natural events. This leads to a conclusion that application of the defense-in-depth philosophy be enhanced because the defense-in-depth philosophy has been and continues to be an effective way to account for uncertainties associated with risks. From the human and organizational viewpoints, the final report from the Investigation Committee of the Government pointed out so-called "safety myth" that existed among nuclear operators including TEPCO as well as the government, that serious severe accidents could never occur in nuclear power plants in Japan. After the accident, the

Pre- and post-exposure safety and efficacy of attenuated rabies virus vaccines are enhanced by their expression of IFNγ

Energy Technology Data Exchange (ETDEWEB)

Barkhouse, Darryll A. [Department of Cancer Biology, 1020 Locust St., Jefferson Alumni Hall, Room 454, Philadelphia, PA 19107 (United States); Center for Neurovirology 1020 Locust St., Jefferson Alumni Hall, Room 454, Philadelphia, PA 19107 (United States); Faber, Milosz [Center for Neurovirology 1020 Locust St., Jefferson Alumni Hall, Room 454, Philadelphia, PA 19107 (United States); Department of Microbiology and Immunology 1020 Locust St., Jefferson Alumni Hall, Room 465, Philadelphia, PA 19107 (United States); Hooper, D. Craig, E-mail: douglas.hooper@jefferson.edu [Department of Cancer Biology, 1020 Locust St., Jefferson Alumni Hall, Room 454, Philadelphia, PA 19107 (United States); Department of Neurological Surgery, 1020 Locust St., Jefferson Alumni Hall, Room 454, Philadelphia, PA 19107 (United States); Center for Neurovirology 1020 Locust St., Jefferson Alumni Hall, Room 454, Philadelphia, PA 19107 (United States)

2015-01-01

Consistent with evidence of a strong correlation between interferon gamma (IFNγ) production and rabies virus (RABV) clearance from the CNS, we recently demonstrated that engineering a pathogenic RABV to express IFNγ highly attenuates the virus. Reasoning that IFNγ expression by RABV vaccines would enhance their safety and efficacy, we reverse-engineered two proven vaccine vectors, GAS and GASGAS, to express murine IFNγ. Mortality and morbidity were monitored during suckling mice infection, immunize/challenge experiments and mixed intracranial infections. We demonstrate that GASγ and GASγGAS are significantly attenuated in suckling mice compared to the GASGAS vaccine. GASγ better protects mice from lethal DRV4 RABV infection in both pre- and post-exposure experiments compared to GASGAS. Finally, GASγGAS reduces post-infection neurological sequelae, compared to control, during mixed intracranial infection with DRV4. These data show IFNγ expression by a vaccine vector can enhance its safety while increasing its efficacy as pre- and post-exposure treatment. - Highlights: • IFNγ expression improves attenuated rabies virus safety and immunogenicity. • IFNγ expression is safer and more immunogenic than doubling glycoprotein expression. • Co-infection with IFNγ-expressing RABV prevents wild-type rabies virus lethality. • Vaccine safety and efficacy is additive for IFNγ and double glycoprotein expression.

Pre- and post-exposure safety and efficacy of attenuated rabies virus vaccines are enhanced by their expression of IFNγ

International Nuclear Information System (INIS)

Barkhouse, Darryll A.; Faber, Milosz; Hooper, D. Craig

2015-01-01

Consistent with evidence of a strong correlation between interferon gamma (IFNγ) production and rabies virus (RABV) clearance from the CNS, we recently demonstrated that engineering a pathogenic RABV to express IFNγ highly attenuates the virus. Reasoning that IFNγ expression by RABV vaccines would enhance their safety and efficacy, we reverse-engineered two proven vaccine vectors, GAS and GASGAS, to express murine IFNγ. Mortality and morbidity were monitored during suckling mice infection, immunize/challenge experiments and mixed intracranial infections. We demonstrate that GASγ and GASγGAS are significantly attenuated in suckling mice compared to the GASGAS vaccine. GASγ better protects mice from lethal DRV4 RABV infection in both pre- and post-exposure experiments compared to GASGAS. Finally, GASγGAS reduces post-infection neurological sequelae, compared to control, during mixed intracranial infection with DRV4. These data show IFNγ expression by a vaccine vector can enhance its safety while increasing its efficacy as pre- and post-exposure treatment. - Highlights: • IFNγ expression improves attenuated rabies virus safety and immunogenicity. • IFNγ expression is safer and more immunogenic than doubling glycoprotein expression. • Co-infection with IFNγ-expressing RABV prevents wild-type rabies virus lethality. • Vaccine safety and efficacy is additive for IFNγ and double glycoprotein expression

Enhancing NPP Safety Through an Effective Dependability Management

Energy Technology Data Exchange (ETDEWEB)

Vieru, G., E-mail: g_vieru@yahoo.com [AREN, Bucharest (Romania)

2014-10-15

Taking into account the importance of the continuous improvement of the performance and reliability of a NPP and practical measures to strengthen nuclear safety and security, it is to be noted that a good management for a nuclear power reactor involves a ''good dependability management'' of the activities, such as: Reliability, Availability, Maintainability (RAM) and maintenance support. In order to evaluate certain safety assessment criteria intended to be applied at the level of the nuclear reactor unit management, equipment dependability indicators and their impact over the availability and reactor safety have to be evaluated. Reactor equipment dependability indicators provide a quantitative indication of equipment RAM performances (Reliability, Availability and Maintenance). One of the important benefits of maintenance and failure data gathering is that it can be used as a support of probabilistic safety assessment (PSA). Also, a good dependability management implementation may be used to complement reactor level unit performance indicators in the field of safe operation, maintenance and improving operating parameters, as well as for Strengthening Safety and Improving Reliability of a NPP. This paper underlines the importance of nuclear safety and security as prerequisites for nuclear power. In addition, it demonstrates how different technical aspects, through implementation of a good dependability management, contribute to a strengthened safety and an improvement of availability of the NPP through dependability indicators determination and evaluation. (author)

Preliminary Evaluation of an Aviation Safety Thesaurus' Utility for Enhancing Automated Processing of Incident Reports

Science.gov (United States)

Barrientos, Francesca; Castle, Joseph; McIntosh, Dawn; Srivastava, Ashok

2007-01-01

This document presents a preliminary evaluation the utility of the FAA Safety Analytics Thesaurus (SAT) utility in enhancing automated document processing applications under development at NASA Ames Research Center (ARC). Current development efforts at ARC are described, including overviews of the statistical machine learning techniques that have been investigated. An analysis of opportunities for applying thesaurus knowledge to improving algorithm performance is then presented.

Stepping Up Occupational Safety and Health Through Employee Participation.

Science.gov (United States)

Vaughan, Gary R.

1986-01-01

The effectiveness of the Occupational Safety and Health Act of 1970 is examined, and it is suggested that employee participation could help improve occupational safety and health in the future, through safety committees, safety circles, safety teams, and individual participation. (MSE)

Safety enhancement through calibration and maintenance

International Nuclear Information System (INIS)

Mohammad Ali Khalid; Taiman Kadni

2000-01-01

Although radiation causes an alarming effect to living organism, it has been accepted for diagnostic and therapy in medicine as well as quality control and test method in industry. Due to the benefit gained, public at large is willing to accept the risk on condition that proper protection and safety standard is implemented and practised. Instrument plays a very important role not only in generation radiation but also measuring it. Therefore to ensure safety it is fair to say that all instrument must be calibrated to a certain standard and maintained to operate to its design specifications from time to time. (author)

Global Nuclear Safety and Security Network

International Nuclear Information System (INIS)

Guo Lingquan

2013-01-01

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

Annual report on the administration of the Radiation Control for health and Safety Act of 1968, Public Law 90-602, April 1, 1991. Rept. for Jan-Dec 90

International Nuclear Information System (INIS)

1991-01-01

The Secretary of Health and Human Services is required by Subpart 3, Part F of Title III of the Public Health Service Act; 42 USC 263b et seq. (Public Law 90-602) to submit an annual report to the President for transmittal to the Congress on or before April 1 on the administration of the Radiation Control for Health and Safety Act. The detailed information required in the report is outlined in Section 360D of the Public Health Service Act. The Food and Drug Administration, through its Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act of 1968. The report provides a summary of the operations of the Center in carrying out that responsibility for calendar year 1990. In reviewing the operations of the Center for Devices and Radiological Health as reported in the document, it should be kept in mind that the day-to-day administration of the Act is only part of the Center's function. Other responsibilities include the administration and enforcement of the 1976 Medical Device Amendments to the Federal Food, Drug, and Cosmetic Act (not covered in the report). Manufacturers of electronic products are required by 21 CFR 1002.20 to report accidental radiation occurrences to the Center for Devices and Radiological Health. The Center no longer maintains a Radiation Incidents Registry, since accidental radiation occurrences are reported through the Device Experience Network (DEN) and through the requirements of the Medical Device Reporting (MDR) Regulations

Effectiveness and safety of oral olanzapine treatment transitioned from rapid-acting intramuscular olanzapine for agitation associated with schizophrenia

Directory of Open Access Journals (Sweden)

Katagiri H

2018-04-01

Full Text Available Hideaki Katagiri,1 Masanori Taketsuna,2 Shinpei Kondo,3 Kenta Kajimoto,4 Etsuko Aoi,5 Yuka Tanji1 1Bio-Medicines, Medicines Development Unit Japan, Eli Lilly Japan K.K., Kobe, Japan; 2Statistical Sciences, Medicines Development Unit Japan, Eli Lilly Japan K.K., Kobe, Japan; 3Post Marketing Study Management, Medicines Development Unit Japan, Eli Lilly Japan K.K., Kobe, Japan; 4Scientific Communications, Medicines Development Unit Japan, Eli Lilly Japan K.K., Kobe, Japan; 5Global Patient Safety Japan, Quality and Patient Safety, Eli Lilly Japan K.K., Kobe, Japan Objective: To assess the effectiveness and safety of oral olanzapine treatment transitioned from rapid-acting intramuscular olanzapine (RAIM in patients with acute agitation associated with schizophrenia in a real-world clinical setting. Methods: The postmarketing surveillance study with a 3-day observational period after the last RAIM administration was conducted (original study. Following this, an extended study was added for patients who received oral olanzapine after RAIM administration during the original study period, in order to additionally observe them for 7 days after initial RAIM administration. Effectiveness and safety from initial RAIM administration were evaluated using the Positive and Negative Syndrome Scale-Excited Component score and treatment-emergent adverse events (TEAEs, respectively. Results: The effectiveness and safety analysis set included a total of 521 and 522 patients, respectively. A majority of patients received 10 mg of RAIM (475/522 patients, 91.0%. The mean ± SD total Positive and Negative Syndrome Scale-Excited Component score was 23.6±6.2 (n=318 at baseline (before initial RAIM administration, 17.4±6.8 (n=280 at 2 hours after initial administration, 16.2±6.8 (n=246 2 days after final administration, 14.9±6.2 (n=248 3 days after final administration, 13.8±5.9 (n=242 4 days after final administration, 13.2±5.8 (n=221 7 days after initial

Workplace Safety and Health Topics: Safety & Prevention

Science.gov (United States)

... 1, 2018 Content source: National Institute for Occupational Safety and Health Education and Information Division Email Recommend Tweet YouTube Instagram Listen Watch RSS ABOUT About CDC Jobs Funding LEGAL Policies Privacy FOIA No Fear Act OIG 1600 Clifton Road Atlanta , GA 30329-4027 USA 800-CDC-INFO ( ...

76 FR 7854 - Patient Safety Organizations: Voluntary Delisting From Quality Excellence, Inc./PSO

Science.gov (United States)

2011-02-11

... Arkansas Foundation for Medical Care, of its status as a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21--b... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety...

Operating experience: safety perspective

International Nuclear Information System (INIS)

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

2015-01-01

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

Development approach on usage of radiation and inspection of QA according to the change of approval procedure of safety regulatory guides

International Nuclear Information System (INIS)

Oh, B. J.; Ahn, H. Z.; Kim, S. W.; Yoo, S. O.; Kang, S. C.; Yang, S. H.; Han, S. J.; Kim, H. S.; Kim, H. J.

2002-01-01

In accordance with 2001 amendment of the Atomic Energy Act(AEA), KINS also amended its internal 'Regulation on Implementation of Entrusted AEA-related Work'. Up to now the nuclear safety-specialized institute has used its internally developed guidelines in the safety regulation. From now on, however, the institute will enhance the objectivity and transparency by having the instruments approved by the Ministry of Science ad Technology. In this paper, we introduced the major points and directions to be considered to the development of the safety regulatory guides on Inspection for the quality assurance of the nuclear reactor facilities and the use of radioisotopes, and review and inspection for dosimeter reading

Nuclear safety policy statement in korea

International Nuclear Information System (INIS)

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

2006-01-01

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

Hospital employee assault rates before and after enactment of the california hospital safety and security act.

Science.gov (United States)

Casteel, Carri; Peek-Asa, Corinne; Nocera, Maryalice; Smith, Jamie B; Blando, James; Goldmacher, Suzi; O'Hagan, Emily; Valiante, David; Harrison, Robert

2009-02-01

This study examines changes in violent event rates to hospital employees before and after enactment of the California Hospital Safety and Security Act in 1995. We compared pre- and post-initiative employee assault rates in California (n = 116) emergency departments and psychiatric units with those in New Jersey (n = 50), where statewide workplace violence initiatives do not exist. Poisson regression with generalized estimating equations was used to compare assault rates between a 3-year pre-enactment period (1993-1995) and a 6-year post-enactment period (1996-2001) using New Jersey hospitals as a temporal control. Assault rates among emergency department employees decreased 48% in California post-enactment, compared with emergency department employee assault rates in New Jersey (rate ratio [RR] = 0.52, 95% confidence interval [CI]: 0.31, 0.90). Emergency department employee assault rates decreased in smaller facilities (RR = 0.46, 95% CI: 0.21, 0.96) and for-profit-controlled hospitals (RR = 0.39, 95% CI: 0.19, 0.79) post-enactment. Among psychiatric units, for-profit-controlled hospitals (RR = 0.41, 95% CI: 0.19, 0.85) and hospitals located in smaller communities (RR = 0.44, 95% CI: 0.21, 0.92) experienced decreased assault rates post-enactment. Policy may be an effective method to increase safety to health care workers.

75 FR 17410 - Agency Forms Undergoing Paperwork Reduction Act Review

Science.gov (United States)

2010-04-06

... for Occupational Safety and Health (NIOSH), Centers for Disease Control and Prevention (CDC). [[Page... Health Act, the National Institute for Occupational Safety and Health (NIOSH) has been at the forefront..., NIOSH employs engineers and scientists with experience and expertise in mine safety and health issues...

Safety and Health in Nuclear Malaysia workplace

International Nuclear Information System (INIS)

Wo, Y.M.

2013-01-01

Safety and health at work place is essential to ensure the health of their workers as required under the Occupational Safety and Health Act 1994 (Act 514). In Malaysian Nuclear Agency, each building / block was appointed with one/ two supervisors, known as Area Supervisor to ensure the safety of buildings / blocks. The area supervisor will conduct periodic bimonthly inspections of the building / block under their supervision. This paper presents the results of the inspection of 80 supervisors over 45 buildings / blocks at the Malaysian Nuclear Agency for the first six months of the year 2013. (author)

Design verification enhancement of field programmable gate array-based safety-critical I&C system of nuclear power plant

Energy Technology Data Exchange (ETDEWEB)

Ahmed, Ibrahim [Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104 (Korea, Republic of); Jung, Jaecheon, E-mail: jcjung@kings.ac.kr [Department of Nuclear Power Plant Engineering, KEPCO International Nuclear Graduate School, 658-91 Haemaji-ro, Seosang-myeon, Ulju-gun, Ulsan 45014 (Korea, Republic of); Heo, Gyunyoung [Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do 17104 (Korea, Republic of)

2017-06-15

Highlights: • An enhanced, systematic and integrated design verification approach is proposed for V&V of FPGA-based I&C system of NPP. • RPS bistable fixed setpoint trip algorithm is designed, analyzed, verified and discussed using the proposed approaches. • The application of integrated verification approach simultaneously verified the entire design modules. • The applicability of the proposed V&V facilitated the design verification processes. - Abstract: Safety-critical instrumentation and control (I&C) system in nuclear power plant (NPP) implemented on programmable logic controllers (PLCs) plays a vital role in safe operation of the plant. The challenges such as fast obsolescence, the vulnerability to cyber-attack, and other related issues of software systems have currently led to the consideration of field programmable gate arrays (FPGAs) as an alternative to PLCs because of their advantages and hardware related benefits. However, safety analysis for FPGA-based I&C systems, and verification and validation (V&V) assessments still remain important issues to be resolved, which are now become a global research point of interests. In this work, we proposed a systematic design and verification strategies from start to ready-to-use in form of model-based approaches for FPGA-based reactor protection system (RPS) that can lead to the enhancement of the design verification and validation processes. The proposed methodology stages are requirement analysis, enhanced functional flow block diagram (EFFBD) models, finite state machine with data path (FSMD) models, hardware description language (HDL) code development, and design verifications. The design verification stage includes unit test – Very high speed integrated circuit Hardware Description Language (VHDL) test and modified condition decision coverage (MC/DC) test, module test – MATLAB/Simulink Co-simulation test, and integration test – FPGA hardware test beds. To prove the adequacy of the proposed

Design verification enhancement of field programmable gate array-based safety-critical I&C system of nuclear power plant

International Nuclear Information System (INIS)

Ahmed, Ibrahim; Jung, Jaecheon; Heo, Gyunyoung

2017-01-01

Highlights: • An enhanced, systematic and integrated design verification approach is proposed for V&V of FPGA-based I&C system of NPP. • RPS bistable fixed setpoint trip algorithm is designed, analyzed, verified and discussed using the proposed approaches. • The application of integrated verification approach simultaneously verified the entire design modules. • The applicability of the proposed V&V facilitated the design verification processes. - Abstract: Safety-critical instrumentation and control (I&C) system in nuclear power plant (NPP) implemented on programmable logic controllers (PLCs) plays a vital role in safe operation of the plant. The challenges such as fast obsolescence, the vulnerability to cyber-attack, and other related issues of software systems have currently led to the consideration of field programmable gate arrays (FPGAs) as an alternative to PLCs because of their advantages and hardware related benefits. However, safety analysis for FPGA-based I&C systems, and verification and validation (V&V) assessments still remain important issues to be resolved, which are now become a global research point of interests. In this work, we proposed a systematic design and verification strategies from start to ready-to-use in form of model-based approaches for FPGA-based reactor protection system (RPS) that can lead to the enhancement of the design verification and validation processes. The proposed methodology stages are requirement analysis, enhanced functional flow block diagram (EFFBD) models, finite state machine with data path (FSMD) models, hardware description language (HDL) code development, and design verifications. The design verification stage includes unit test – Very high speed integrated circuit Hardware Description Language (VHDL) test and modified condition decision coverage (MC/DC) test, module test – MATLAB/Simulink Co-simulation test, and integration test – FPGA hardware test beds. To prove the adequacy of the proposed

[Innovative training for enhancing patient safety. Safety culture and integrated concepts].

Science.gov (United States)

Rall, M; Schaedle, B; Zieger, J; Naef, W; Weinlich, M

2002-11-01

Patient safety is determined by the performance safety of the medical team. Errors in medicine are amongst the leading causes of death of hospitalized patients. These numbers call for action. Backgrounds, methods and new forms of training are introduced in this article. Concepts from safety research are transformed to the field of emergency medical treatment. Strategies from realistic patient simulator training sessions and innovative training concepts are discussed. The reasons for the high numbers of errors in medicine are not due to a lack of medical knowledge, but due to human factors and organisational circumstances. A first step towards an improved patient safety is to accept this. We always need to be prepared that errors will occur. A next step would be to separate "error" from guilt (culture of blame) allowing for a real analysis of accidents and establishment of meaningful incident reporting systems. Concepts with a good success record from aviation like "crew resource management" (CRM) training have been adapted my medicine and are ready to use. These concepts require theoretical education as well as practical training. Innovative team training sessions using realistic patient simulator systems with video taping (for self reflexion) and interactive debriefing following the sessions are very promising. As the need to reduce error rates in medicine is very high and the reasons, methods and training concepts are known, we are urged to implement these new training concepts widely and consequently. To err is human - not to counteract it is not.

76 FR 73687 - Advisory Committee on Construction Safety and Health (ACCSH)

Science.gov (United States)

2011-11-29

... arising in the administration of the safety and health provisions under the Contract Work Hours and Safety... 10:10 a.m. to 12:10 p.m. Multilingual Issues, Diversity, Women in Construction 1 to 3 p.m. ACCSH Work... Health Act of 1970 (29 U.S.C. 656), Section 107 of the Contract Work Hours and Safety Standards Act...

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)

78 FR 6819 - Patient Safety Organizations: Voluntary Relinquishment From the BREF PSO

Science.gov (United States)

2013-01-31

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21--b-26, provides for the formation of...

78 FR 6820 - Patient Safety Organizations: Voluntary Relinquishment From Ryder Trauma Center

Science.gov (United States)

2013-01-31

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Quality (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21--b-26, provides for the formation...

Does Employee Safety Matter for Patients Too? Employee Safety Climate and Patient Safety Culture in Health Care.

Science.gov (United States)

Mohr, David C; Eaton, Jennifer Lipkowitz; McPhaul, Kathleen M; Hodgson, Michael J

2015-04-22

We examined relationships between employee safety climate and patient safety culture. Because employee safety may be a precondition for the development of patient safety, we hypothesized that employee safety culture would be strongly and positively related to patient safety culture. An employee safety climate survey was administered in 2010 and assessed employees' views and experiences of safety for employees. The patient safety survey administered in 2011 assessed the safety culture for patients. We performed Pearson correlations and multiple regression analysis to examine the relationships between a composite measure of employee safety with subdimensions of patient safety culture. The regression models controlled for size, geographic characteristics, and teaching affiliation. Analyses were conducted at the group level using data from 132 medical centers. Higher employee safety climate composite scores were positively associated with all 9 patient safety culture measures examined. Standardized multivariate regression coefficients ranged from 0.44 to 0.64. Medical facilities where staff have more positive perceptions of health care workplace safety climate tended to have more positive assessments of patient safety culture. This suggests that patient safety culture and employee safety climate could be mutually reinforcing, such that investments and improvements in one domain positively impacts the other. Further research is needed to better understand the nexus between health care employee and patient safety to generalize and act upon findings.

Atomic Energy Act 1989

International Nuclear Information System (INIS)

1989-05-01

This Act, which entered into force on 1 september 1989, contains a series of provisions dealing with different subjects: increase of public financing for British Nuclear Fuels plc, amendment of the Nuclear Installations Act 1965 regarding the powers of the Health and Safety Executive to recover expenses directly from nuclear operators and obligation of the UKAEA to take out insurance or other financial security to cover its liability and finally, measures to enable the UK to ratify the IAEA Convention on Assistance in Case of a Nuclear Accident or Radiological Emergency [fr

Safety standards and safety record of nuclear power plants

International Nuclear Information System (INIS)

Davis, A.B.

1984-01-01

This paper focuses on the use of standards and the measurement and enforcement of these standards to achieve safe operation of nuclear power plants. Since a discussion of the safety standards that the Nuclear Regulatory Commission (NRC) uses to regulate the nuclear power industry can be a rather tedious subject, this discussion will provide you with not only a description of what safety standards are, but some examples of their application, and various indicators that provide an overall perspective on safety. These remarks are confined to the safety standards adopted by the NRC. There are other agencies such as the Environmental Protection Agency, the Occupational Safety and Health Administration, and the state regulatory agencies which impact on a nuclear power plant. The NRC has regulatory authority for the commercial use of the nuclear materials and facilities which are defined in the Atomic Energy Act of 1954 to assure that the public health and safety and national security are protected

Defining safety culture and the nexus between safety goals and safety culture. 1. An Investigation Study on Practical Points of Safety Management

International Nuclear Information System (INIS)

Hasegawa, Naoko; Takano, Kenichi; Hirose, Ayako

2001-01-01

In a report after the Chernobyl accident, the International Atomic Energy Agency indicated the definition and the importance of safety culture and the ideal organizational state where safety culture pervades. However, the report did not mention practical approaches to enhance safety culture. In Japan, although there had been investigations that clarified the consciousness of employees and the organizational climate in the nuclear power and railway industries, organizational factors that clarified the level of organization safety and practical methods that spread safety culture in an organization had not been studied. The Central Research Institute of the Electric Power Industry conducted surveys of organizational culture for the construction, chemical, and manufacturing industries. The aim of our study was to clarify the organizational factors that influence safety in an organization expressed in employee safety consciousness, commitment to safety activities, rate of accidents, etc. If these areas were clarified, the level of organization safety might be evaluated, and practical ways could be suggested to enhance the safety culture. Consequently, a series of investigations was conducted to clarify relationships among organizational climate, employee consciousness, safety management and activities, and rate of accidents. The questionnaire surveys were conducted in 1998-1999. The subjects were (a) managers of the safety management sections in the head offices of the construction, chemical, and manufacturing industries; (b) responsible persons in factories of the chemical and manufacturing industries; and (c) general workers in factories of the chemical and manufacturing industries. The number of collected data was (a) managers in the head office: 48 from the construction industry and 58 from the chemical and manufacturing industries, (b) responsible persons in factories: 567, and (c) general workers: from 29 factories. Items in the questionnaires were selected from

What should the Price--Anderson Act accomplish

International Nuclear Information System (INIS)

Kane, G.L.

1977-01-01

A historical review of the Price-Anderson Act's goals is followed by recommendations for amendments to improve guarantees of public safety. Failures of the original Act are identified as its failure to cover some accident situations appropriately and to provide incentives for promoting public safety. Legislation should correct these problems and be extended to all energy areas. Legislation based on worst-case situations is not found to be meaningful in terms of increasing safety or estimating comprehensive compensation because it relies on invalidated assumptions, which are still useful in safety awareness. Legislation could take the direction of putting 1.5 percent of the reactor cost into a fund, with the vendor and licensee contributing equal parts. When an incident occurs at any reactor, another one percent is put in by every reactor plus a $1 million penalty proportioned among those responsible. The Federal government would cover amounts above the fund, which would have no limit. Compensation to public funds by the industry would be a social decision based on the social and economic impact

Creating a culture of safety by coaching clinicians to competence.

Science.gov (United States)

Duff, Beverley

2013-10-01

Contemporary discussions of nursing knowledge, skill, patient safety and the associated ongoing education are usually combined with the term competence. Ensuring patient safety is considered a fundamental tenet of clinical competence together with the ability to problem solve, think critically and anticipate variables which may impact on patient care outcomes. Nurses are ideally positioned to identify, analyse and act on deteriorating patients, near-misses and potential adverse events. The absence of competency may lead to errors resulting in serious consequences for the patient. Gaining and maintaining competence are especially important in a climate of rapid evidence availability and regular changes in procedures, systems and products. Quality and safety issues predominate highlighting a clear need for closer inter-professional collaboration between education and clinical units. Educators and coaches are ideally placed to role model positive leadership and resilience to develop capability and competence. With contemporary guidance and support from educators and coaches, nurses can participate in life-long learning to create and enhance a culture of safety. The added challenge for nurse educators is to modernise, rationalise and integrate education delivery systems to improve clinical learning. Investing in evidence-based, contemporary education assists in building a capable, resilient and competent workforce focused on patient safety. Crown Copyright © 2012. Published by Elsevier Ltd. All rights reserved.

Safety inspections to TRIGA reactors

International Nuclear Information System (INIS)

Byszewski, W.

1988-01-01

The operational safety advisory programme was created to provide useful assistance and advice from an international perspective to research reactor operators and regulators on how to enhance operational safety and radiation protection on their reactors. Safety missions cover not only the operational safety of reactors themselves, but also the safety of associated experimental loops, isotope laboratories and other experimental facilities. Safety missions are also performed on request in other Member States which are interested in receiving impartial advice and assistance in order to enhance the safety of research reactors. The results of the inspections have shown that in some countries there are problems with radiation protection practices and nuclear safety. Very often the Safety Analysis Report is not updated, regulatory supervision needs clarification and improvement, maintenance procedures should be more formalised and records and reports are not maintained properly. In many cases population density around the facility has increased affecting the validity of the original safety analysis

Hawaii State Plan for Occupational Safety and Health. Final rule.

Science.gov (United States)

2012-09-21

This document announces the Occupational Safety and Health Administration's (OSHA) decision to modify the Hawaii State Plan's ``final approval'' determination under Section 18(e) of the Occupational Safety and Health Act (the Act) and to transition to ``initial approval'' status. OSHA is reinstating concurrent federal enforcement authority over occupational safety and health issues in the private sector, which have been solely covered by the Hawaii State Plan since 1984.

New electricity act brings in private sector

International Nuclear Information System (INIS)

Anon.

1995-01-01

Opening up the State's electricity industry, previously the domain of the former Queensland Electricity Commission (QEC), is part of an overall restructuring of the industry under the new Queensland Electricity Act. Under this Act, the QEC was split into generating and transmission and supply corporations. The Act provides for the regulation of the electricity industry and the regulation of the use of electricity and safety in relation to the supply and use of electricity.(Author). 6 photos

Act No 282 reorganising ENEA

International Nuclear Information System (INIS)

1991-01-01

This Act reorganises the National Agency for Research and Development of Nuclear and Alternative Energies - ENEA - and reorients its responsibilities. It is now called the National Agency for New Technologies, Energy and the Environment and retains its acronym (Ente per le nouve tecnologies, l'energia e l'ambiente - ENEA). It will also deal with environmental questions and new technologies, in particular, carrying out studies and research on the latter and evaluating their economic, social and environmental consequences. Already in 1982, the National Nuclear Energy Committee (CNEN) had been entrusted with wider tasks and renamed ENEA. The present ENEA retains its competence regarding nuclear activities, notably in the field of nuclear safety and radiation protection. The new Act confirms the tasks already conferred on the Nuclear Safety and Health Protection Directorate (DISP), we well as its operational independence while remaining within ENEA [fr

Development of coated nifedipine dry elixir as a long acting oral delivery with bioavailability enhancement.

Science.gov (United States)

Choi, Jae-Yoon; Jin, Su-Eon; Park, Youmie; Lee, Hyo-Jong; Park, Yohan; Maeng, Han-Joo; Kim, Chong-Kook

2011-10-01

To develop the long acting nifedipine oral delivery with bioavailability enhancement, a nifedipine dry elixir (NDE) containing nifedipine ethanol solution in dextrin shell was prepared using a spray-dryer, and then coated nifedipine dry elixir (CNDE) was prepared by coating NDE with Eudragit acrylic resin. The physical characteristics and bioavailability of NDE and CNDE were evaluated, and then compared to those of nifedipine powder. NDE and CNDE, which were spherical in shape, had about 6.64 and 8.68-8.75 μm of geometric mean diameters, respectively. The amount of nifedipine dissolved from NDE for 60 min increased about 7- and 40-fold compared to nifedipine powder in pH 1.2 simulated gastric fluid and pH 6.8 simulated intestinal fluid, respectively. Nifedipine released from CNDE was retarded in both dissolution media compared with that from NDE. After oral administration of NDE, the C(max) and AUC(0→8h) of nifedipine in rat increased about 13- and 7-fold, respectively, and the Tmax of nifedipine was reduced significantly compared with those after oral administration of nifedipine powder alone. The AUC(0→8h) and T(max) of nifedipine in CNDE increased markedly and the C(max) of nifedipine in CNDE was significantly reduced compared to those in NDE. It is concluded that CNDE, which could lower the initial burst-out plasma concentration and maintain the plasma level of nifedipine over a longer period with bioavailability enhancement, might be one of potential alternatives to the marketed long acting oral delivery system for nifedipine.

29 CFR 1977.3 - General requirements of section 11(c) of the Act.

Science.gov (United States)

2010-07-01

... WILLIAMS-STEIGER OCCUPATIONAL SAFETY AND HEALTH ACT OF 1970 General § 1977.3 General requirements of... 29 Labor 9 2010-07-01 2010-07-01 false General requirements of section 11(c) of the Act. 1977.3 Section 1977.3 Labor Regulations Relating to Labor (Continued) OCCUPATIONAL SAFETY AND HEALTH...

Occupational Safety and Health Curriculum Manual.

Science.gov (United States)

Gourley, Frank A., Jr., Comp.

With the enactment of the Occupational Safety and Health Act of 1970, the need for manpower development in the field of industrial safety and hygiene has resulted in the development of a broad based program in Occupational Safety and Health. The manual provides information to administrators and instructors on a program of study in this field for…

Radioactive Substances Act 1948

International Nuclear Information System (INIS)

1948-01-01

This Act regulates the use of radioactive substances and radiation producing devices in the United Kingdom. It provides for the control of import, export, sale, supply etc. of such substances and devices and lays down the safety regulations to be complied with when dealing with them. (NEA) [fr

Granzyme B-dependent proteolysis acts as a switch to enhance the proinflammatory activity of IL-1α.

LENUS (Irish Health Repository)

Afonina, Inna S

2011-10-21

Granzyme B is a cytotoxic lymphocyte-derived protease that plays a central role in promoting apoptosis of virus-infected target cells, through direct proteolysis and activation of constituents of the cell death machinery. However, previous studies have also implicated granzymes A and B in the production of proinflammatory cytokines, via a mechanism that remains undefined. Here we show that IL-1α is a substrate for granzyme B and that proteolysis potently enhanced the biological activity of this cytokine in vitro as well as in vivo. Consistent with this, compared with full-length IL-1α, granzyme B-processed IL-1α exhibited more potent activity as an immunoadjuvant in vivo. Furthermore, proteolysis of IL-1α within the same region, by proteases such as calpain and elastase, was also found to enhance its biological potency. Thus, IL-1α processing by multiple immune-related proteases, including granzyme B, acts as a switch to enhance the proinflammatory properties of this cytokine.

Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

International Nuclear Information System (INIS)

Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

2004-01-01

Full text: The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by (1) implementing safety upgrades, or (2) assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

Cost effective safety enhancements for research reactors in Uzbekistan and Kazakhstan - results of a joint program with US DOE

International Nuclear Information System (INIS)

Earle, O.K.; Carlson, R.B.; Rakhmanov, A.; Salikhbaev, U.S.; Chernyaev, V.; Chakrov, P.

2004-01-01

The US Department of Energy's Office of International Nuclear Safety and Cooperation established the Integrated Research Reactor Safety Enhancement Program (IRRSEP) in February 2002 to support U.S. nonproliferation goals by implementing safety upgrades, or assisting with the safe shutdown and decommissioning of foreign test and research reactors which present security concerns. IRRSEP's key program components are: Phase I: Self-evaluation by facility using provided checklists followed by prioritization to identify the 20 highest risk facilities; Phase II: Site visits with technical evaluation to finalize a list of projects that will enhance safety consistent with IAEA observations; Phase III: Corrective measures to implement the projects. Phases I, II and III are accomplished on a rolling basis, such that work is ongoing at three or four reactors per year. IRRSEP's key objective is to resolve the highest-priority nuclear safety issues at the most vulnerable foreign research reactors as quickly as possible. The prioritization methodology employed identified which research reactors fell into this category. The corrective measures mutually developed with the host facility are based on the premise of developing a sustainable infrastructure within each country to deal with its own nuclear material safety, security, and response issues in the future. IRRSEP also assists in creating an international framework of cooperation and openness between research and test reactor operators, and national and international regulators. The initial projects under IRRSEP are underway at research reactors in Kazakhstan, Uzbekistan, and Romania. This paper focuses on the projects undertaken at the WWR-K research reactor at the Institute of Nuclear Physics in Alatau, Kazakhstan and the WWR-SM research reactor at the Institute of Nuclear Physics in Ulugbek, Uzbekistan. These projects demonstrate the success and cost effectiveness of the IRRSEP program

Gypsum plasterboards enhanced with phase change materials: A fire safety assessment using experimental and computational techniques

Directory of Open Access Journals (Sweden)

Kolaitis Dionysios I.

2013-11-01

Full Text Available Phase Change Materials (PCM can be used for thermal energy storage, aiming to enhance building energy efficiency. Recently, gypsum plasterboards with incorporated paraffin-based PCM blends have become commercially available. In the high temperature environment developed during a fire, the paraffins, which exhibit relatively low boiling points, may evaporate and, escaping through the gypsum plasterboard's porous structure, emerge to the fire region, where they may ignite, thus adversely affecting the fire resistance characteristics of the building. Aiming to assess the fire safety behaviour of such building materials, an extensive experimental and computational analysis is performed. The fire behaviour and the main thermo-physical physical properties of PCM-enhanced gypsum plasterboards are investigated, using a variety of standard tests and devices (Scanning Electron Microscopy, Thermo Gravimetric Analysis, Cone Calorimeter. The obtained results are used to develop a dedicated numerical model, which is implemented in a CFD code. CFD simulations are validated using measurements obtained in a cone calorimeter. In addition, the CFD code is used to simulate an ISO 9705 room exposed to fire conditions, demonstrating that PCM addition may indeed adversely affect the fire safety of a gypsum plasterboard clad building.

47{sup th} Annual meeting on nuclear technology (AMNT 2016). Key Topics / Enhanced safety and operation excellence

Energy Technology Data Exchange (ETDEWEB)

Bohnstedt, Angelika [Karlsruher Institut fuer Technologie (KIT), Eggenstein-Leopoldshafen (Germany). Programm Nukleare Entsorgung, Sicherheit und Strahlenforschung (NUSAFE); Baumann, Erik [AREVA GmbH, Erlangen (Germany). Radiation Protection

2016-12-15

Summary report on the Key Topic 'Enhanced Safety and Operation Excellence' Focus Session 'Radiation Protection' of the 47{sup th} Annual Meeting on Nuclear Technology (AMNT 2016) held in Hamburg, 10 to 12 May 2016. Other Sessions of AMNT 2016 have been and will be covered in further issues of atw.

77 FR 42738 - Patient Safety Organizations: Voluntary Relinquishment From the Coalition for Quality and Patient...

Science.gov (United States)

2012-07-20

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety Organizations: Voluntary Relinquishment From the Coalition for Quality and Patient Safety of Chicagoland (CQPS.... SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41,42...

Positioning radiation safety in occupational safety and health programme in an organization

International Nuclear Information System (INIS)

Abed Bin Onn

2000-01-01

The Atomic Energy Licensing Act 1984, which is under purview of the Ministry of Science, Technology and Environment, and Occupational Safety and Health Act, OSHA 1994, under Ministry of Human Resources were discussed. RPO responsibilities were discussed in detailed. As the conclusion, organization which complies with the provisions of the AELA 1984 are well on the way to complying the requirements of OSHA 1994

Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2003

Energy Technology Data Exchange (ETDEWEB)

NONE

2004-07-01

The work of the institute is directed to the assessment and enhancement of the safety of technical plants and to the increase of the efficiency and environmental sustainability of those facilities. Subjects of investigation are equally nuclear plants and installations of process industries. To achieve the goals mentioned, the institute is mainly engaged in the scientific fields of thermal fluid dynamics including magneto-hydrodynamics (MHD) and materials sciences. In 2003, the ISR worked on the following main scientific projects. Sub-programme: Plant and Rector Safety. Project: accident analysis of nuclear reactors, safety of materials and components, particle and radiation transport, safety and efficiency of chemical processes. Sub-programme: Thermal Fluid Dynamics. Project: magneto-hydrodynamics, thermal fluid dynamics of multiphase systems. Considerable progress could also be achieved in the CFD simulation of two-phase flows. New approaches for the forces acting on steam bubbles in a water flow could be developed and implemented into the CFX code in close cooperation with the CFX developer ANSYS/CFX. The qualified models allow to simulate the evolution of bubble size specific radial void distribution profiles along the flow path. These theoretical studies and the related experiments at the Rossendorf TOPFLOW test facility represent an important part of the German CFD network that aims at the improvement of thermal hydraulic calculation methods in reactor safety. (orig.)

Forschungszentrum Rossendorf, Institute of Safety Research. Annual report 2003

International Nuclear Information System (INIS)

2004-01-01

The work of the institute is directed to the assessment and enhancement of the safety of technical plants and to the increase of the efficiency and environmental sustainability of those facilities. Subjects of investigation are equally nuclear plants and installations of process industries. To achieve the goals mentioned, the institute is mainly engaged in the scientific fields of thermal fluid dynamics including magneto-hydrodynamics (MHD) and materials sciences. In 2003, the ISR worked on the following main scientific projects. Sub-programme: Plant and Rector Safety. Project: accident analysis of nuclear reactors, safety of materials and components, particle and radiation transport, safety and efficiency of chemical processes. Sub-programme: Thermal Fluid Dynamics. Project: magneto-hydrodynamics, thermal fluid dynamics of multiphase systems. Considerable progress could also be achieved in the CFD simulation of two-phase flows. New approaches for the forces acting on steam bubbles in a water flow could be developed and implemented into the CFX code in close cooperation with the CFX developer ANSYS/CFX. The qualified models allow to simulate the evolution of bubble size specific radial void distribution profiles along the flow path. These theoretical studies and the related experiments at the Rossendorf TOPFLOW test facility represent an important part of the German CFD network that aims at the improvement of thermal hydraulic calculation methods in reactor safety. (orig.)

Safety and tolerability of pasireotide long-acting release in acromegaly-results from the acromegaly, open-label, multicenter, safety monitoring program for treating patients who have a need to receive medical therapy (ACCESS) study.

Science.gov (United States)

Fleseriu, Maria; Rusch, Elisha; Geer, Eliza B

2017-01-01

Pasireotide long-acting release is a somatostatin analog that is indicated for treatment of patients with acromegaly. This analysis documents the safety of pasireotide long-acting release in patients with acromegaly enrolled in the ACCESS trial (ClinicalTrials.gov identifier: NCT01995734). ACCESS is an open-label, multicenter, single-arm, expanded-treatment protocol designed to provide patients access to pasireotide long-acting release pending regulatory approval. Patients received pasireotide long-acting release 40 mg administered intramuscularly every 28 days. The primary outcome was the proportion of patients having a treatment-emergent grade ≥3 or serious adverse event. Efficacy data were not collected. Forty-four adult patients with active acromegaly were enrolled in the study for an average of 37.6 weeks (range, 4-70 weeks). Twenty-five grade ≥3 treatment-emergent adverse events were reported in 11 patients (25.0 %), 3 of whom (27.3 %) experienced grade ≥3 hyperglycemia. In patients treated with pasireotide long-acting release for ≥3 months (n = 42), mean glycated hemoglobin and fasting plasma glucose levels increased significantly from 5.9 % and 100.4 mg/dL at baseline to 6.8 % and 135.9 mg/dL at 3 months, respectively. Ten patients (22.7 %) were treated with pasireotide long-acting release for ≥15 months, after which mean glycated hemoglobin and fasting plasma glucose levels were 6.3 % and 123 mg/dL, respectively. Twenty-one patients (48 %) initiated antidiabetic medication. Grade ≥3 adverse events (primary outcome) were reported in 25.0 % of acromegaly patients treated with pasireotide long-acting release in a clinical setting. Hyperglycemia-related adverse events were reported in 45.5 % of patients, but were typically manageable, supporting the role of pasireotide long-acting release as a safe treatment option for acromegaly patients.

20 CFR 401.160 - Health or safety.

Science.gov (United States)

2010-04-01

... 20 Employees' Benefits 2 2010-04-01 2010-04-01 false Health or safety. 401.160 Section 401.160... INFORMATION Disclosure of Official Records and Information § 401.160 Health or safety. The Privacy Act allows us to disclose information in compelling circumstances where an individual's health or safety is...

The impact of the Department of Veterans Affairs Health Care Personnel Enhancement Act of 2004 on VA physicians' salaries and retention.

Science.gov (United States)

Weeks, William B; Wallace, Tanner A; Wallace, Amy E

2009-01-01

To determine whether the Department of Veterans Affairs Health Care Personnel Enhancement Act (the Act), which was designed to achieve VA physician salary parity with American Academy of Medical Colleges (AAMC) Associate Professors and enacted in 2006, had achieved its goal. Using VA human resources datasets and data from the AAMC, we calculated mean VA physician salaries, with 95 percent confidence intervals, for 15 different medical specialties. For each specialty, we compared VA salaries to the median, 25th, and 75th percentile of AAMC Associate Professors' incomes. The Act's passage resulted in a $20,000 annual increase in VA physicians' salaries. VA primary care physicians, medical subspecialists, and psychiatrists had salaries that were comparable to their AAMC counterparts prior to and after enactment of the Act. However, VA surgical specialists', anesthesiologists', and radiologists' salaries lagged their AAMC counterparts both before and after the Act's enactment. Income increases were negatively correlated with full-time workforce changes. VA does not appear to provide comparable salaries for physicians necessary for surgical care. In certain cases, VA should consider outsourcing surgical services.

Collaborating with nurse leaders to develop patient safety practices.

Science.gov (United States)

Kanerva, Anne; Kivinen, Tuula; Lammintakanen, Johanna

2017-07-03

Purpose The organisational level and leadership development are crucial elements in advancing patient safety, because patient safety weaknesses are often caused by system failures. However, little is known about how frontline leader and director teams can be supported to develop patient safety practices. The purpose of this study is to describe the patient safety development process carried out by nursing leaders and directors. The research questions were: how the chosen development areas progressed in six months' time and how nursing leaders view the participatory development process. Design/methodology/approach Participatory action research was used to engage frontline nursing leaders and directors into developing patient safety practices. Semi-structured group interviews ( N = 10) were used in data collection at the end of a six-month action cycle, and data were analysed using content analysis. Findings The participatory development process enhanced collaboration and gave leaders insights into patient safety as a part of the hospital system and their role in advancing it. The chosen development areas advanced to different extents, with the greatest improvements in those areas with simple guidelines to follow and in which the leaders were most participative. The features of high-reliability organisation were moderately identified in the nursing leaders' actions and views. For example, acting as a change agent to implement patient safety practices was challenging. Participatory methods can be used to support leaders into advancing patient safety. However, it is important that the participants are familiar with the method, and there are enough facilitators to steer development processes. Originality/value Research brings more knowledge of how leaders can increase their effectiveness in advancing patient safety and promoting high-reliability organisation features in the healthcare organisation.

A knee-mounted biomechanical energy harvester with enhanced efficiency and safety

Science.gov (United States)

Chen, Chao; Chau, Li Yin; Liao, Wei-Hsin

2017-06-01

Energy harvesting is becoming a major limiting issue for many portable devices. When undertaking any activity, the human body generates a significant amount of biomechanical energy, which can be collected by means of a portable energy harvester. This energy provides a method of powering portable devices such as prosthetic limbs. In this paper, a knee-mounted energy harvester with enhanced efficiency and safety is proposed and developed to convert mechanical energy into electricity during human motion. This device can change the bi-directional knee input into uni-directional rotation for an electromagnetic generator using a specially designed transmission system. Without the constraint of induced impact on the human body, this device can harvest biomechanical energy from both knee flexion and extension, improving the harvesting efficiency over previous single-direction energy harvesters. It can also provide protection from device malfunction, and increase the safety of current biomechanical energy harvesters. A highly compact and light prototype is developed taking into account human kinematics. The biomechanical energy harvesting system is also modeled and analyzed. The prototype is tested under different conditions including walking, running and climbing stairs, to evaluate the energy harvesting performance and effect on the human gait. The experimental results show that the prototype can harvest an average power of 3.6 W at 1.5 m s-1 walking speed, which is promising for portable electronic devices.

Accelerating Research Impact in a Learning Health Care System: VA's Quality Enhancement Research Initiative in the Choice Act Era.

Science.gov (United States)

Kilbourne, Amy M; Elwy, A Rani; Sales, Anne E; Atkins, David

2017-07-01

Since 1998, the Veterans Health Administration (VHA) Quality Enhancement Research Initiative (QUERI) has supported more rapid implementation of research into clinical practice. With the passage of the Veterans Access, Choice and Accountability Act of 2014 (Choice Act), QUERI further evolved to support VHA's transformation into a Learning Health Care System by aligning science with clinical priority goals based on a strategic planning process and alignment of funding priorities with updated VHA priority goals in response to the Choice Act. QUERI updated its strategic goals in response to independent assessments mandated by the Choice Act that recommended VHA reduce variation in care by providing a clear path to implement best practices. Specifically, QUERI updated its application process to ensure its centers (Programs) focus on cross-cutting VHA priorities and specify roadmaps for implementation of research-informed practices across different settings. QUERI also increased funding for scientific evaluations of the Choice Act and other policies in response to Commission on Care recommendations. QUERI's national network of Programs deploys effective practices using implementation strategies across different settings. QUERI Choice Act evaluations informed the law's further implementation, setting the stage for additional rigorous national evaluations of other VHA programs and policies including community provider networks. Grounded in implementation science and evidence-based policy, QUERI serves as an example of how to operationalize core components of a Learning Health Care System, notably through rigorous evaluation and scientific testing of implementation strategies to ultimately reduce variation in quality and improve overall population health.

Enhancing vaccine safety capacity globally: A lifecycle perspective

NARCIS (Netherlands)

R.T. Chen (Robert T.); T.T. Shimabukuro (Tom T.); D.B. Martin (David); P. Zuber (Patrick); D.M. Weibel (Daniel); M.C.J.M. Sturkenboom (Miriam)

2015-01-01

textabstractMajor vaccine safety controversies have arisen in several countries beginning in the last decades of 20th century. Such periodic vaccine safety controversies are unlikely to go away in the near future as more national immunization programs mature with near elimination of target

State Office for Nuclear Safety - New Regulatory Body in Croatia

International Nuclear Information System (INIS)

Novosel, N.; Prah, M.; Valcic, I.; Cizmek, A.

2006-01-01

The Act on Nuclear Safety was adopted by the Croatian Parliament on 15 October 2003, and it is published in the Official Gazette No. 173/03. This Act regulates safety and protective measures for using nuclear materials and specified equipment and performing nuclear activities, and establishes the State Office for Nuclear Safety. Provisions of this Act apply on nuclear activities, nuclear materials and specified equipment. Also, by accession to international conventions and agreements, Croatia took the responsibility of implementing the provisions of those international treaties. In the process of European and international integrations, Croatia has to make harmonization with European and international standards also in the field of nuclear safety. The State Office for Nuclear Safety as an independent regulatory authority started its work on 1st June 2005 by taking over responsibility for activities relating to nuclear safety and cooperation with the International Atomic Energy Agency from the Ministry of the Economy, Labour and Entrepreneurship. In this paper responsibilities, organization and projects of the State Office for Nuclear Safety will be presented, with the accent on development of regulations and international cooperation. (author)

Psychological aspects of food safety risk perception

DEFF Research Database (Denmark)

Scholderer, Joachim

signals, motivating approach. Novelty, and the detection of certain olfactory and visual cues associated with spoilage or contamination, act as orientation or threat signals and motivate closer inspection or avoidance. Anticipatory affects are an inherent part of these behaviour regulation systems...... problematic food safety behaviours are likely to occur. The presentation will begin with an overview of the relevant psychological mechanisms that regulate approach and avoidance behaviour with respect to potentially hazardous foods. Learned representations of familiarity and reward value act as safety...

Safer Systems: A NextGen Aviation Safety Strategic Goal

Science.gov (United States)

Darr, Stephen T.; Ricks, Wendell R.; Lemos, Katherine A.

2008-01-01

The Joint Planning and Development Office (JPDO), is charged by Congress with developing the concepts and plans for the Next Generation Air Transportation System (NextGen). The National Aviation Safety Strategic Plan (NASSP), developed by the Safety Working Group of the JPDO, focuses on establishing the goals, objectives, and strategies needed to realize the safety objectives of the NextGen Integrated Plan. The three goal areas of the NASSP are Safer Practices, Safer Systems, and Safer Worldwide. Safer Practices emphasizes an integrated, systematic approach to safety risk management through implementation of formalized Safety Management Systems (SMS) that incorporate safety data analysis processes, and the enhancement of methods for ensuring safety is an inherent characteristic of NextGen. Safer Systems emphasizes implementation of safety-enhancing technologies, which will improve safety for human-centered interfaces and enhance the safety of airborne and ground-based systems. Safer Worldwide encourages coordinating the adoption of the safer practices and safer systems technologies, policies and procedures worldwide, such that the maximum level of safety is achieved across air transportation system boundaries. This paper introduces the NASSP and its development, and focuses on the Safer Systems elements of the NASSP, which incorporates three objectives for NextGen systems: 1) provide risk reducing system interfaces, 2) provide safety enhancements for airborne systems, and 3) provide safety enhancements for ground-based systems. The goal of this paper is to expose avionics and air traffic management system developers to NASSP objectives and Safer Systems strategies.

Electrical safety guidelines

Energy Technology Data Exchange (ETDEWEB)

1993-09-01

The Electrical Safety Guidelines prescribes the DOE safety standards for DOE field offices or facilities involved in the use of electrical energy. It has been prepared to provide a uniform set of electrical safety standards and guidance for DOE installations in order to affect a reduction or elimination of risks associated with the use of electrical energy. The objectives of these guidelines are to enhance electrical safety awareness and mitigate electrical hazards to employees, the public, and the environment.

Principles and Practices of Occupational Safety and Health: Administrator's Manual.

Science.gov (United States)

Occupational Safety and Health Administration, Washington, DC.

The manual guides an instructor in conducting a training course for first-line supervisors to familiarize them with six aspects relating to the Occupational Safety and Health Act of 1970: (1) requirements of the Act, (2) compliance with its standards, (3) identification of health and safety hazards, (4) correction of adverse conditions, (5) record…

Tenth act amending the German atomic energy act

International Nuclear Information System (INIS)

Heller, W.

2009-01-01

On January 14, 2009, the German federal government introduced into parliament the 10th Act Amending the Atomic Energy Act. In the first reading in the federal parliament, Federal Minister for the Environment Gabriel emphasized 2 main points: Intensified protection of nuclear facilities and of transports of radioactive substances against unauthorized interventions; transfer by law to the Federal Office for Radiological Protection (BfS) of decommissioning of the Asse mine. Reliability review: The amendment to Sec.12 b of the Atomic Energy Act is to meet the different safety and security conditions after the terrorist attacks on September 11, 2001 in the United States and other terrorist activities afterwards (London, Madrid) also with respect to hazards arising to nuclear facilities and nuclear transports. The bill must be seen in conjunction with the Ordinance on Reliability Reviews under the Atomic Energy Act dated July 1, 1999 which covers reviews of reliability of persons holding special responsibilities. Asse II mine: The competence of the Federal Office for Radiological Protection is achieved by an amendment to Sec.23, Para.1, Number 2, Atomic Energy Act, in which the words ''and for the Asse II mine'' are added after the word ''waste.'' Further proceedings depend on the additional provision in a new Sec.57 b, Atomic Energy Act. Accordingly, the operation and decommissioning of the Asse II mine are subject to the regulations applicable to facilities of the federation pursuant to Sec.9a, Para.3. In this way, Asse II is given the same legal status as the federal waste management facilities. Moreover, it is stipulated that the mine is to be shut down immediately. (orig.)

Slovak Republic act of 1 April 1998 on the peaceful use of nuclear energy and on alterations and amendments to Act No. 174/1968 Collection of laws of CSSR on State supervision of work safety as amended by Act of the National Council of the Slovak Republic No. 256/1994 of Collection of laws of the Slovak Republic

International Nuclear Information System (INIS)

1998-01-01

These act contains: Part I. Chapter (Ch.) one: Basic provisions; Paragraph (P) 1: Subject of act; P2: Definition of certain terms; P3: Principles of peaceful use of nuclear energy; P4: Conditions for use of nuclear energy; P5: Conditions for issue of authorization; P6: Application for the issue of an authorization; P7: Issue of authorization; P8: Termination and limitation of authorization; P8: Termination and limitation of authorization. Ch.2: Nuclear materials; P9: Nuclear materials, special materials and equipment; P10: Procurement and use of nuclear materials (NM); P11: Transportation of NM; P12: Accounting and control of NM; Ch.3: Nuclear installations, management of radioactive waste and spent nuclear fuel; P13: Nuclear installation (NI); P14: Construction of nuclear installations (NI); P15. Commissioning and operation of NI; P16. Extension of operational lifetime of NI; P17: Radioactive waste management; P18: Management of spent nuclear fuel; P19: Decommissioning of NIs; Ch.4. Nuclear safety and quality assurance; P20: Nuclear safety; P21: Professional qualification; P22: Quality assurance; P23: Physical protection of NIs and NMs; P24. Events at nuclear installations and accidents during transportation of NMs; P25: Emergency planning; Ch.5. P26: Nuclear damage and compensation for such damage; P27: Liability for nuclear damage; P28: Limitation of liability; P29: Meeting of claims for compensation for nuclear damage; P30: Financial cover for nuclear damage liability. Ch.6: NRA SR. P31: Competence of the Authority; P32: The Authority performs the State supervision; P33: The obligations of the authorized persons towards the authority and apprising by the authority of the national organs; P34: Nuclear safety inspectors; P35: Discontinuation of the operating of a NI or its construction. P36: Penalties. Ch.7. Common, temporary and concluding provisions. P37. Relation to administrative procedure; P38: Temporary provisions; P39: Abrogation provision; P40: List of

78 FR 57621 - Sunshine Act Meeting

Science.gov (United States)

2013-09-19

... CONSUMER PRODUCT SAFETY COMMISSION Sunshine Act Meeting TIME AND DATE: Wednesday, September 25..., Maryland. STATUS: Commission Meeting--Open to the public Matters To Be Considered Briefing Matter: Voluntary Recall Notice--Notice of Proposed Rulemaking. [[Page 57622

Enhanced Accident Tolerant LWR Fuels National Metrics Workshop Report

Energy Technology Data Exchange (ETDEWEB)

Lori Braase

2013-01-01

The U.S. Department of Energy Office of Nuclear Energy (DOE-NE), in collaboration with the nuclear industry, has been conducting research and development (R&D) activities on advanced Light Water Reactor (LWR) fuels for the last few years. The emphasis for these activities was on improving the fuel performance in terms of increased burnup for waste minimization and increased power density for power upgrades, as well as collaborating with industry on fuel reliability. After the events at the Fukushima Nuclear Power Plant in Japan in March 2011, enhancing the accident tolerance of LWRs became a topic of serious discussion. In the Consolidated Appropriations Act, 2012, Conference Report 112-75, the U.S. Congress directed DOE-NE to: • Give “priority to developing enhanced fuels and cladding for light water reactors to improve safety in the event of accidents in the reactor or spent fuel pools.” • Give “special technical emphasis and funding priority…to activities aimed at the development and near-term qualification of meltdown-resistant, accident-tolerant nuclear fuels that would enhance the safety of present and future generations of light water reactors.” • Report “to the Committee, within 90 days of enactment of this act, on its plan for development of meltdown-resistant fuels leading to reactor testing and utilization by 2020.” Fuels with enhanced accident tolerance are those that, in comparison with the standard UO2-zirconium alloy system currently used by the nuclear industry, can tolerate loss of active cooling in the reactor core for a considerably longer time period (depending on the LWR system and accident scenario) while maintaining or improving the fuel performance during normal operations, and operational transients, as well as design-basis and beyond design-basis events. The overall draft strategy for development and demonstration is comprised of three phases: Feasibility Assessment and Down-selection; Development and Qualification; and

The role of probabilistic safety assessment and probabilistic safety criteria in nuclear power plant safety

International Nuclear Information System (INIS)

1992-01-01

The purpose of this Safety Report is to provide guidelines on the role of probabilistic safety assessment (PSA) and a range of associated reference points, collectively referred to as probabilistic safety criteria (PSC), in nuclear safety. The application of this Safety Report and the supporting Safety Practice publication should help to ensure that PSA methodology is used appropriately to assess and enhance the safety of nuclear power plants. The guidelines are intended for use by nuclear power plant designers, operators and regulators. While these guidelines have been prepared with nuclear power plants in mind, the principles involved have wide application to other nuclear and non-nuclear facilities. In Section 2 of this Safety Report guidelines are established on the role PSA can play as part of an overall safety assurance programme. Section 3 summarizes guidelines for the conduct of PSAs, and in Section 4 a PSC framework is recommended and guidance is provided for the establishment of PSC values

Operating procedure automation to enhance safety of nuclear power plants

International Nuclear Information System (INIS)

Husseiny, A.A.; Sabri, Z.A.; Adams, S.K.; Rodriguez, R.J.; Packer, D.; Holmes, J.W.

1989-01-01

Use of logic statements and computer assist are explored as means for automation and improvement on design of operating procedures including those employed in abnormal and emergency situations. Operating procedures for downpower and loss of forced circulation are used for demonstration. Human-factors analysis is performed on generic emergency operating procedures for three strategies of control; manual, semi-automatic and automatic, using standard emergency operating procedures. Such preliminary analysis shows that automation of procedures is feasible provided that fault-tolerant software and hardware become available for design of the controllers. Recommendations are provided for tests to substantiate the promise of enhancement of plant safety. Adequate design of operating procedures through automation may alleviate several major operational problems of nuclear power plants. Also, automation of procedures is necessary for partial or overall automatic control of plants. Fully automatic operations are needed for space applications while supervised automation of land-based and offshore plants may become the thrust of new generation of nulcear power plants. (orig.)

KHNP Safety Culture Framework based on Global Standard, and Lessons learned from Safety Culture Evaluation

International Nuclear Information System (INIS)

Kim, Younggab; Hur, Nam Young; Jeong, Hyeon Jong

2015-01-01

In order to eliminate the vague fears of the people about the nuclear power and operate continuously NPPs, a strong safety culture of NPPs should be demonstrated. Strong safety culture awareness of workers can overcome social distrust about NPPs. KHNP has been a variety efforts to improve and establish safety culture of NPPs. Safety culture framework applying global standards was set up and safety culture assessment has been carried out periodically to enhance safety culture of workers. In addition, KHNP developed various safety culture contents and they are being used in NPPs by workers. As a result of these efforts, safety culture awareness of workers is changed positively and the safety environment of NPPs is expected to be improved. KHNP makes an effort to solve areas for improvement derived from safety culture assessment. However, there are some areas to take a long time in completing the work. Therefore, these actions are necessary to be carried out consistently and continuously. KHNP also developed recently safety culture enhancement system based on web. All information related to safety culture in KHNP will be shared through this web system and this system will be used to safety culture assessment. In addition to, KHNP plans to develop safety culture indicators for monitoring the symptoms of safety culture weakening

KHNP Safety Culture Framework based on Global Standard, and Lessons learned from Safety Culture Evaluation

Energy Technology Data Exchange (ETDEWEB)

Kim, Younggab; Hur, Nam Young; Jeong, Hyeon Jong [KHNP Central Research Institute, Daejeon (Korea, Republic of)

2015-05-15

In order to eliminate the vague fears of the people about the nuclear power and operate continuously NPPs, a strong safety culture of NPPs should be demonstrated. Strong safety culture awareness of workers can overcome social distrust about NPPs. KHNP has been a variety efforts to improve and establish safety culture of NPPs. Safety culture framework applying global standards was set up and safety culture assessment has been carried out periodically to enhance safety culture of workers. In addition, KHNP developed various safety culture contents and they are being used in NPPs by workers. As a result of these efforts, safety culture awareness of workers is changed positively and the safety environment of NPPs is expected to be improved. KHNP makes an effort to solve areas for improvement derived from safety culture assessment. However, there are some areas to take a long time in completing the work. Therefore, these actions are necessary to be carried out consistently and continuously. KHNP also developed recently safety culture enhancement system based on web. All information related to safety culture in KHNP will be shared through this web system and this system will be used to safety culture assessment. In addition to, KHNP plans to develop safety culture indicators for monitoring the symptoms of safety culture weakening.

EGP contribution to Mochovce completion, safety enhancement and operation

International Nuclear Information System (INIS)

Letko, A.; Matula, P.

2000-01-01

The Re-Evaluation Programme of Mochovce NPP was created in 1995 as an integral part of the completion of the Unit 1 and Unit 2. This program analyzed the general fulfillment of the principle of nuclear safety in the NPP Mochovce project. The analysis has required new corrections of the project, so that the project met the higher safety requirements when starting production. 87 safety measures represent the 'Program'. The basis for their creation were the international missions from 1992 to 1995 which defined. The final safety aim was represented by 'The Technical Specification of the Safety Measures' supported by The Nuclear Power Plant Research Institute and recommended by The Nuclear Regulatory Authority of the Slovak Republic. The technical specification served as a qualified base for the next steps in the pre-project, project and realization stages. (author)

Defining safety culture and the nexus between safety goals and safety culture. 3. A Methodology for Identifying Deficiencies in Safety Culture

International Nuclear Information System (INIS)

Apostolakis, George; Weil, Rick

2001-01-01

At present, the drivers of performance problems at nuclear power plants (NPPs) are organizational in nature. Organizational deficiencies and other 'latent' conditions cause human errors, resulting in incidents that impact the performance of NPPs. Therefore, the human reliability community, regulators, and others concerned with NPP safety express the view that safety culture and organizational factors play an important role in plant safety. However, we have yet to identify one complete set of organizational factors, establish links between deficient safety culture and performance, or develop adequate tools to measure safety culture. This paper will contribute to the resolution of these issues. Safety culture is not a single factor but rather is a collection of several distinct factors. This paper asserts that in order to pro-actively manage safety culture at NPPs, leading indicators and appropriate measurements must be identified and developed. Central to this effort are the identification of the distinct factors comprising safety culture and the relationships between those factors and performance. We have identified several factors important to safety culture. We have developed a methodology that is a combination of traditional root-cause analysis and theories of human error, most notably Reason's theory of accident causation. In addition to this methodology's usefulness in identifying deficiencies in safety culture, it could also be used as a starting point to identify leading indicators of deteriorating safety performance. We have identified six organizational factors as being important: communication, formalization, goal prioritization, problem identification, roles and responsibilities, and technical knowledge. In addition, we have found that certain organizational factors, although pervasive throughout the organization, have a much greater influence on the successful outcome of particular tasks of work processes, rather than being equally important to all

Fuel Fracture (Crumbling) Safety Impact (OCRWM)

International Nuclear Information System (INIS)

DUNCAN, D.R.

1999-01-01

The safety impact of experimentally observed N Reactor fuel sample fracture and fragmentation is evaluated using an average reaction rate enhancement derived from data from thermo-gravimetric analysis (TGA) experiments on fuel samples. The enhanced reaction rates attributed to fragmentation were within the existing safety basis

Enhancement of color and clarity in topaz and diamonds by nuclear radiation, safety and security concerns

International Nuclear Information System (INIS)

Shamshad Ahmed

2009-01-01

Inducement of color and clarity in gemstone Topaz, otherwise devoid of these attributes, has been achieved by synergistic utilization of neutron irradiation, electron beam irradiation and heat. The transformation of the colorless, cheaply available topaz into desirable deep blue topaz is a significant value addition, not achievable by other contending techniques .Likewise colorless and unclear diamonds, available in trade at throw away price, have been transformed by neutron irradiation into colored diamonds, known as fancy diamonds. The enhanced gems may possess stable or unstable colors depending on the nature of the color centers produced. In the case of blue topaz and fancy diamonds the colors produced were stable and heating at elevated temperatures can only lead to fading of colors. The enhancement of gems by neutron irradiation is commercially viable provided appropriate equipment and tools are used .In the paper are described the processes of the enhancement of topaz and diamonds along with the instrumentation involved. However, in view of the radioactivity generated as a result of the exposure of gems to the neutrons, and the likelihood of undue exposure of the users, operators etc to the radioactive gems, safety aspects command serious attention. In the paper, the strategies to avoid or to mitigate the radioactivity generated have been discussed. Also documented are the methodologies and the controls to ensure that the radioactive gems are not released before ensuring that the radioactivity, if any, in the irradiated materials is not above the permissible levels in conformity with the international standards. Safety, security and safeguard of these materials are thus appropriately addressed. (Authors)

Administration of the Radiation Control for Health Safety Act of 1968, public law 90-602, April 1, 1984 (1983 annual report)

International Nuclear Information System (INIS)

1984-01-01

The Food and Drug Administration through its National Center for Devices and Radiological Health, is responsible for the day-to-day administration of the Radiation Control for Health and Safety Act. This report covers the detailed operation of the Agency in carrying out that responsibility for calendar year 1983. There are nine equipment performance or regulatory standards (television receivers, cold-cathode gas discharge tubes, microwave ovens, diagnostic x-ray systems, cabinet x-ray systems, laser products, ultrasonic therapy products, mercury vapor lamps, and sunlamp products) now in effect

Trending of low level events and near misses to enhance safety performance in nuclear power plants

International Nuclear Information System (INIS)

2005-11-01

The IAEA Safety Fundamentals publication, Safety of Nuclear Installations, Safety Series No. 110, states the need for operating organizations to establish a programme for the collection and analysis of operating experience in nuclear power plants. Such a programme ensures that operating experience is analysed, events important to safety are reviewed in depth, and lessons learned are disseminated to the staff of the organization and to relevant national and international organizations. As a result of the effort to enhance safety in operating organizations, incidents are progressively decreasing in number and significance. This means that in accordance with international reporting requirements the amount of collected data becomes less sufficient to draw meaningful statistical conclusions. This is where the collection and trend analysis of low level events and near misses can prove to be very useful. These trends can show which of the safety barriers are weak or failing more frequently. Evaluation and trending of low level events and near misses will help to prevent major incidents because latent weaknesses have been identified and corrective actions taken to prevent recurrence. This leads to improved safety and production. Low level events and near misses, which may reach several thousand per reactor operating year, need to be treated by the organizations as learning opportunities. A system for capturing these low level events and near misses truly needs to be an organization-wide system in which all levels of the organization, including contractors, participate. It is desirable that the overall operational experience feedback (OEF) process should integrate the lessons learned and the associated data from significant events with those of lower level events and near misses. To be able to effectively implement a process dealing with low level events and near misses, it is necessary that the organization have a well established OEF process for significant events

Oswer integrated health and safety standard operating practices. Directive

International Nuclear Information System (INIS)

1993-02-01

The directive implements the OSWER (Office of Solid Waste and Emergency Response) Integrated Health and Safety Standards Operating Practices in conjunction with the OSHA (Occupational Safety and Health Act) Worker Protection Standards, replacing the OSWER Integrated Health and Safety Policy

Segmentation Scheme for Safety Enhancement of Engineered Safety Features Component Control System

International Nuclear Information System (INIS)

Lee, Sangseok; Sohn, Kwangyoung; Lee, Junku; Park, Geunok

2013-01-01

Common Caused Failure (CCF) or undetectable failure would adversely impact safety functions of ESF-CCS in the existing nuclear power plants. We propose the segmentation scheme to solve these problems. Main function assignment to segments in the proposed segmentation scheme is based on functional dependency and critical function success path by using the dependency depth matrix. The segment has functional independence and physical isolation. The segmentation structure is that prohibit failure propagation to others from undetectable failures. Therefore, the segmentation system structure has robustness to undetectable failures. The segmentation system structure has functional diversity. The specific function in the segment defected by CCF, the specific function could be maintained by diverse control function that assigned to other segments. Device level control signals and system level control signals are separated and also control signal and status signals are separated due to signal transmission paths are allocated independently based on signal type. In this kind of design, single device failure or failures on signal path in the channel couldn't result in the loss of all segmented functions simultaneously. Thus the proposed segmentation function is the design scheme that improves availability of safety functions. In conventional ESF-CCS, the single controller generates the signal to control the multiple safety functions, and the reliability is achieved by multiplication within the channel. This design has a drawback causing the loss of multiple functions due to the CCF (Common Cause Failure) and single failure Heterogeneous controller guarantees the diversity ensuring the execution of safety functions against the CCF and single failure, but requiring a lot of resources like manpower and cost. The segmentation technology based on the compartmentalization and functional diversification decreases the CCF and single failure nonetheless the identical types of controllers

Segmentation Scheme for Safety Enhancement of Engineered Safety Features Component Control System

Energy Technology Data Exchange (ETDEWEB)

Lee, Sangseok; Sohn, Kwangyoung [Korea Reliability Technology and System, Daejeon (Korea, Republic of); Lee, Junku; Park, Geunok [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2013-05-15

Common Caused Failure (CCF) or undetectable failure would adversely impact safety functions of ESF-CCS in the existing nuclear power plants. We propose the segmentation scheme to solve these problems. Main function assignment to segments in the proposed segmentation scheme is based on functional dependency and critical function success path by using the dependency depth matrix. The segment has functional independence and physical isolation. The segmentation structure is that prohibit failure propagation to others from undetectable failures. Therefore, the segmentation system structure has robustness to undetectable failures. The segmentation system structure has functional diversity. The specific function in the segment defected by CCF, the specific function could be maintained by diverse control function that assigned to other segments. Device level control signals and system level control signals are separated and also control signal and status signals are separated due to signal transmission paths are allocated independently based on signal type. In this kind of design, single device failure or failures on signal path in the channel couldn't result in the loss of all segmented functions simultaneously. Thus the proposed segmentation function is the design scheme that improves availability of safety functions. In conventional ESF-CCS, the single controller generates the signal to control the multiple safety functions, and the reliability is achieved by multiplication within the channel. This design has a drawback causing the loss of multiple functions due to the CCF (Common Cause Failure) and single failure Heterogeneous controller guarantees the diversity ensuring the execution of safety functions against the CCF and single failure, but requiring a lot of resources like manpower and cost. The segmentation technology based on the compartmentalization and functional diversification decreases the CCF and single failure nonetheless the identical types of

Odor and the Clean Air Act

International Nuclear Information System (INIS)

Morse, H.N.

1993-01-01

The case described in this paper involves the interpretation of language contained in the Texas Clean Air Act Texas Health and Safety Code Ann. Sections 382.001-382.141. The State of Texas, on behalf of the Texas Air Control Board, brought suit in the District Court of Erath County, Texas against the F/R Cattle Company, Inc., alleging that, because of odors emanating from the company's cattle feeding facility, the company was violating the Clean Air Act. The Board is granted the power and duty to administer the Clean Air Act and is directed to accomplish the purposes of the Act through the control of air contaminants by all practical and economically feasible methods. Described here is the evidence presented at and proceedings of the trial

Operational safety experience feedback by means of unusual event reports

International Nuclear Information System (INIS)

1996-07-01

Operational experience of nuclear power plants can be used to great advantage to enhance safety performance provided adequate measures are in place to collect and analyse it and to ensure that the conclusions drawn are acted upon. Feedback of operating experience is thus an extremely important tool to ensure high standards of safety in operational nuclear power plants and to improve the capability to prevent serious accidents and to learn from minor deviations and equipment failures - which can serve as early warnings -to prevent even minor events from occurring. Mechanisms also need to be developed to ensure that operating experience is shared both nationally as well as internationally. The operating experience feedback process needs to be fully and effectively established within the nuclear power plant, the utility, the regulatory organization as well as in other institutions such as technical support organizations and designers. The main purpose of this publication is to reflect the international consensus as to the general principles and practices in the operational safety experience feedback process. The examples of national practices for the whole or for particular parts of the process are given in annexes. The publication complements the IAEA Safety Series No.93 ''Systems for Reporting Unusual Events in Nuclear Power Plants'' (1989) and may also give a general guidance for Member States in fulfilling their obligations stipulated in the Nuclear Safety Convention. Figs, tabs

Operational safety experience feedback by means of unusual event reports

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-07-01

Operational experience of nuclear power plants can be used to great advantage to enhance safety performance provided adequate measures are in place to collect and analyse it and to ensure that the conclusions drawn are acted upon. Feedback of operating experience is thus an extremely important tool to ensure high standards of safety in operational nuclear power plants and to improve the capability to prevent serious accidents and to learn from minor deviations and equipment failures - which can serve as early warnings -to prevent even minor events from occurring. Mechanisms also need to be developed to ensure that operating experience is shared both nationally as well as internationally. The operating experience feedback process needs to be fully and effectively established within the nuclear power plant, the utility, the regulatory organization as well as in other institutions such as technical support organizations and designers. The main purpose of this publication is to reflect the international consensus as to the general principles and practices in the operational safety experience feedback process. The examples of national practices for the whole or for particular parts of the process are given in annexes. The publication complements the IAEA Safety Series No.93 ``Systems for Reporting Unusual Events in Nuclear Power Plants`` (1989) and may also give a general guidance for Member States in fulfilling their obligations stipulated in the Nuclear Safety Convention. Figs, tabs.

48 CFR 52.250-4 - SAFETY Act Pre-qualification Designation Notice.

Science.gov (United States)

2010-10-01

..., or fails to meet, the requirements of any solicitation issued by any Federal, State, local or tribal...) Definitions. As used in this provision— Act of terrorism means any act determined to have met the following... unlawful. (2) Causes harm, including financial harm, to a person, property, or entity, in the United States...

Occupational safety and health management among five ASEAN countries: Thailand, Indonesia, Malaysia, Philippines, and Singapore.

Science.gov (United States)

Buranatrevedh, Surasak

2015-03-01

Occupational safety and health is one of important issues for workforce movement among ASEAN countries. The objective was to study laws, main agencies, and law enforcement regarding occupational safety and health in Thailand, Indonesia, Malaysia, Philippines, and Singapore. This documentary research covered laws, main agencies' duties, and occupational safety and health law enforcement in Thailand, Indonesia, Malaysia, Philippines, and Singapore. Thailand has its Occupational Safety, Health, and Work EnvironmentAct 2011. Its main agency was Department of Labor Protection and Welfare. Indonesia had WorkSafety Act (Law No. 1, 1970). Its main agency was Department of Manpower and Transmigration. Malaysia had Occupational Safety and Health Act (OSHA) 1994. Its main agency is the Department of Occupational Safety and Health. The Philippines has its Occupational Safety and Health Standards. Its main agency was Department ofLabor and Employment. Singapore has its Workplace Safety and Health Act 2006. Its main agency is Occupational Safety and Health Division. Occupational safety and health law enforcement among each county covers work environment surveillance, workers' health surveillance, advice about prevention and control of occupational health hazards, training and education of employers and employees, data systems, and research. Further in-depth surveys of occupational safety and health among each ASEAN county are needed to develop frameworks for occupational safety and health management for all ASEAN countries.

Implementation of the safety culture for HANARO Safety Management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which the management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of the safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of safety management in nuclear activities for a reactor application and utilization has also been emphasized more than 10 years in HANARO which is a 30 MW multi-purpose research reactor and achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation like the seminars and lectures related to safety matters, participation in international workshops, the development of safety culture indicators, the survey on the attitude of safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e-Learning program for safety education. (author)

16 CFR 1115.8 - Compliance with product safety standards.

Science.gov (United States)

2010-01-01

... applicable mandatory consumer product safety standards and to report to the Commission any products which do.... 1115.8 Section 1115.8 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION CONSUMER PRODUCT SAFETY ACT REGULATIONS SUBSTANTIAL PRODUCT HAZARD REPORTS General Interpretation § 1115.8 Compliance with...

78 FR 70560 - Patient Safety Organizations: Voluntary Relinquishment From Morgridge Institute for Research PSO

Science.gov (United States)

2013-11-26

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Research and Quality (AHRQ), HHS. ACTION: Notice of delisting. SUMMARY: The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act), Public Law 109-41, 42 U.S.C. 299b-21-b-26, provides for the...

76 FR 1460 - Maritime Advisory Committee for Occupational Safety and Health (MACOSH); Committee Reestablishment

Science.gov (United States)

2011-01-10

... duties imposed by the Occupational Safety and Health (OSH) Act of 1970 (29 U.S.C. 655, 656). Authority to...(b) of the Occupational Safety and Health Act of 1970 (29 U.S.C. 655(b)(1), 656(b)), the Federal... DEPARTMENT OF LABOR Occupational Safety and Health Administration Maritime Advisory Committee for...

76 FR 60494 - Patient Safety Organizations: Voluntary Relinquishment From HPI-PSO

Science.gov (United States)

2011-09-29

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... a Patient Safety Organization (PSO). The Patient Safety and Quality Improvement Act of 2005 (Patient... delivery. The Patient Safety and Quality Improvement Final Rule (Patient Safety Rule), 42 CFR Part 3...

Act 25/1964 of 29 April on nuclear energy

International Nuclear Information System (INIS)

1964-01-01

This outline Act governs all nuclear activities in Spain. It lays down all the principles presently applicable for safety and protection against ionizing radiation and for third party liability for nuclear damage. The Act also regulates the licensing of nuclear installations and the possession and use of radioactive materials. (NEA) [fr

Environmental safety of the disposal system for radioactive substance-contaminated wastes

International Nuclear Information System (INIS)

Oosako, Masahiro

2012-01-01

In accordance with the full-scale enforcement of 'The Act on Special Measures concerning the Handling of Radioactive Pollution' in 2012, the collective efforts of entire Japan for dealing with radioactive pollutants began. The most important item for dealing with radioactive pollution is to control radioactive substances that polluted the global environment and establish a contaminated waste treatment system for risk reduction. On the incineration system and landfill disposal system of radioactive waste, this paper arranges the scientific information up to now, and discusses the safety of the treatment / disposal systems of contaminated waste. As for 'The Act on Special Measures concerning the Handling of Radioactive Pollution,' this paper discusses the points of the Act and basic policy, roadmap for the installation of interim storage facilities, and enforcement regulations (Ordinance of the Ministry of the Environment). About the safety of waste treatment system, it discusses the safety level of technical standards at waste treatment facilities, safety of incineration facilities, and safety of landfill disposal sites. (O.A.)

NS [Nuclear Safety] update. Current safety and security activities and developments taking place in the Department of Nuclear Safety and Security. Issue no. 4, June 2007

International Nuclear Information System (INIS)

2007-04-01

This newsletter contains information on the Centre for Advanced Safety Assessment Tools (CASAT), the new strategy for the recovery of radioactive sources, the Technical Support Organization Conference and a message form the Director of the Division of Nuclear Installation Safety. To improve the efficiency of safety assessment methods, ensure transparency in their validation and application and establish an excellent knowledge base and training programmes, the IAEA's Centre for Advanced Safety Assessment Tools (CASAT) has therefore been formed. The Centre addresses the need for continuous technical support mechanisms for safety assessment methods. It provides support to Member States to enhance their safety assessment capabilities for present and future generations of nuclear systems, with a special focus on countries with a developing nuclear technology and nuclear safety infrastructure. It serves as a consolidated repository of relevant safety analysis knowledge, provides for focused training including advanced analytical simulations, and supports collaboration on safety assessment projects among Member States. The resources provided through CASAT include codes, models, databases, verification and validation information, analytical procedures and guides. The main purpose of the recently established Radioactive Source Technical Coordination Group (RSTCG) is to facilitate the technical coordination of activities of the IAEA related to the control and management of radioactive sources through the development of common approaches in technical matters and to advise the management of the relevant Divisions. It is the task of the RSTCG to provide the programme managers of the participating divisions/sections with a common opinion/advice on technical issues related to the control and management of radioactive sources. The RSTCG members obtain, inter alia from programme managers, information on all relevant project proposals, and share relevant materials in due time to

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jongsup; Han, Geeyang; Kim, Iksoo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG (International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safely. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30MW multi-purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementations have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of a e-learning program for a safety education purpose

77 FR 32975 - Patient Safety Organizations: Expired Listing for The American Cancer Biorepository, Inc. d/b/a...

Science.gov (United States)

2012-06-04

... DEPARTMENT OF HEALTH AND HUMAN SERVICES Agency for Healthcare Research and Quality Patient Safety... Biorepository or ``ACB'' as a Patient Safety Organization (PSO) due to its failure to seek continued listing. The Patient Safety and Quality Improvement Act of 2005 (Patient Safety Act) authorizes the listing of...

Nuclear safety research master plan

Energy Technology Data Exchange (ETDEWEB)

Ha, Jae Joo; Yang, J. U.; Jun, Y. S. and others

2001-06-01

The SRMP (Safety Research Master Plan) is established to cope with the changes of nuclear industry environments. The tech. tree is developed according to the accident progress of the nuclear reactor. The 11 research fields are derived to cover the necessary technologies to ensure the safety of nuclear reactors. Based on the developed tech. tree, the following four main research fields are derived as the main safety research areas: 1. Integrated nuclear safety enhancement, 2. Thermal hydraulic experiment and assessment, 3. Severe accident management and experiment, and 4. The integrity of equipment and structure. The research frame and strategies are also recommended to enhance the efficiency of research activity, and to extend the applicability of research output.

The regulatory process, nuclear safety research and the fuel cycle in the United Kingdom

International Nuclear Information System (INIS)

Watson, P.

1996-01-01

The main legislation governing the safety of nuclear installations in the United Kingdom is the Health and Safety at Work Act 1974 (HSWA) and the associated relevant statutory provisions of the Nuclear Installations Act 1965 (as amended). The HSWA sought to simplify and unify all industrial safety legislation and set in place the Health and Safety Commission (HSC) and its executive arm, the Health and Safety Executive (HSE). The Health and Safety Executive's Nuclear Safety Division (NSD) regulates the nuclear activities on such sites through HM Nuclear Installations Inspectorate (NII). Under the Nuclear Installations Act (NIA) no corporate body may use any site for the purpose of installing or operating any reactor, other than such a reactor comprised in a means of transport, or other prescribed installation unless the operator has been granted a nuclear site licence by the Health and Safety Executive. Nuclear fuel cycle facilities are examples of such prescribed installations. (J.P.N.)

A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

International Nuclear Information System (INIS)

Yang, Seung Hyo; Choi, Sun Do

2012-01-01

Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control

A study on the revision of nuclear safety act to build the foundation of nuclear export and import control system in Korea

Energy Technology Data Exchange (ETDEWEB)

Yang, Seung Hyo; Choi, Sun Do [Korea Institute of Nuclear Nonproliferation and Control, Daejeon (Korea, Republic of)

2012-10-15

Nuclear related items require export and import control beyond the multilateral export control system according to Safeguard Agreement, Additional Protocol and bilateral agreements. Besides Korea as a nuclear supplier is needed to actively cope with its export control system, which is being reinforced internationally. In regard to this trend, this study drew the revision plan of present Nuclear Safety Act to found the nuclear export and import control system in Korea by examining the related legislations and analyzing the implementation status of nuclear export and import control.

Act concerning the establishment of a Federal Office for Radiation Protection

International Nuclear Information System (INIS)

1989-01-01

The Federal Office for Radiation Protection shall be placed under the competence of the Federal Minister for the Environment, Nature Conservation and Reactor Safety, and shall have the powers of a higher federal authority. The Office shall have its seat in Salzgitter. The Office shall fulfil administrative tasks within the federal powers in the fields of radiation protection including preventive radiation protection, nuclear safety, transport of radioactive materials, and nuclear waste management including the construction and operation of installations under the competence of the Federal Covernment, for the collection and ultimate disposal of nuclear wastes. The Office shall fulfil such Federal tasks as are defined in these areas by the Atomic Energy Act, the Act on Preventive Radiation Protection, or any other federal act, or such tasks as will be assigned to the Office on the basis of said acts. Any amendments of the above acts required for proper fulfilment of tasks by the Federal Office for Radiation Protection shall be duly announced. (orig./HP) [de

Strengthening leadership as a catalyst for enhanced patient safety culture

DEFF Research Database (Denmark)

Kristensen, Solvejg; Christensen, Karl Bang; Jaquet, Annette

2016-01-01

OBJECTIVES: Current literature emphasises that clinical leaders are in a position to enable a culture of safety, and that the safety culture is a performance mediator with the potential to influence patient outcomes. This paper aims to investigate staff's perceptions of patient safety culture...... in a Danish psychiatric department before and after a leadership intervention. METHODS: A repeated cross-sectional experimental study by design was applied. In 2 surveys, healthcare staff were asked about their perceptions of the patient safety culture using the 7 patient safety culture dimensions...... in the Safety Attitudes Questionnaire. To broaden knowledge and strengthen leadership skills, a multicomponent programme consisting of academic input, exercises, reflections and discussions, networking, and action learning was implemented among the clinical area level leaders. RESULTS: In total, 358 and 325...

Nuclear Malaysia. Towards being a certification body for radiation safety auditors

International Nuclear Information System (INIS)

Nik Ali, Nik Arlina; Mudri, Nurul Huda; Mod Ali, Noriah

2012-01-01

Current management practice demands that an organisation inculcate safety culture in preventing radiation hazard. Radiation safety audit is known as a step in ensuring radiation safety compliance at all times. The purpose of Radiation Safety Auditing is to ensure that the radiation safety protection system is implemented in accordance to Malaysia Atomic Energy Licensing Act 1984, or Act 304, and International Standards. Competent radiation safety auditors are the main element that contributes to the effectiveness of the audit. To realise this need, Innovation Management Centre (IMC) is now in progress to be a certification body for safety auditor in collaboration with Nuclear Malaysia Training Centre (NMTC). NMTC will offer Radiation Safety Management Auditor (RSMA) course, which provide in depth knowledge and understanding on requirement on radiation safety audit that comply with the ISO/IEC 17024 General Requirements for Bodies Operating Certification Systems of Persons. Candidates who pass the exam will be certified as Radiation Safety Management Auditor, whose competency will be evaluated every three years. (author)

Role of effective nurse-patient relationships in enhancing patient safety.

Science.gov (United States)

Conroy, Tiffany; Feo, Rebecca; Boucaut, Rose; Alderman, Jan; Kitson, Alison

2017-08-02

Ensuring and maintaining patient safety is an essential aspect of care provision. Safety is a multidimensional concept, which incorporates interrelated elements such as physical and psychosocial safety. An effective nurse-patient relationship should ensure that these elements are considered when planning and providing care. This article discusses the importance of an effective nurse-patient relationship, as well as healthcare environments and working practices that promote safety, thus ensuring optimal patient care.

Acoustic Waves: A Route to Enhance Sodium Fast Reactor Safety

International Nuclear Information System (INIS)

Jeannot, Jean-Philippe; Baque, François; Cavaro, Matthieu; Gastaldi, Olivier; Lhuilier, Christian; Massacret, Nicolas; Moriot, Jérémy; Paumel, Kévin; Vandergaegen, Matthias; Rodriguez, Gilles

2013-01-01

Improvement to prevent core meltdown and to provide a more robust safety demonstration → Safety objectives: - A level of safety at least equivalent to EPR’s level, - Consolidation of the defence-in-depth principle, - A more robust safety demonstration than those of the Phenix and Superphenix reactor. Acoustic techniques: - Low attenuation by the sodium medium - High velocity of US wave (2289 m.s-1 at 550°C) →

NUMO's approach for long-term safety assessment - 59404

International Nuclear Information System (INIS)

Ebashi, Takeshi; Kaku, Kenichi; Ishiguro, Katsuhiko

2012-01-01

One of NUMO's policies for ensuring safety is staged and flexible project implementation and decision-making based on iterative confirmation of safety. The safety assessment takes the central role in multiple lines of reasoning and argumentation by providing a quantitative evaluation of long-term safety; a key aspect is uncertainty management. This paper presents NUMO's basic strategies for long-term safety assessment based on the above policy. NUMO's approach considering Japanese boundary conditions is demonstrated as a starting-point for evaluating the long-term safety of an actual site. In Japan, the Act on Final Disposal of Specified Radioactive Waste states that the siting process shall consist of three stages. The Nuclear Waste Management Organization of Japan (NUMO) is responsible for geological disposal of vitrified high-level waste and some types of TRU waste. NUMO has chosen to implement a volunteer approach to siting. NUMO decided to prepare the so-called 2010 technical report, which sets out three safety policies, one of which is staged project implementation and decision-making based on iterative confirmation of safety. Based on this policy, NUMO will gradually integrate relevant interdisciplinary knowledge to build a safety case when a formal volunteer application is received that would allow site investigations to be initiated. The safety assessment takes the central role in multiple lines of reasoning and argumentation by providing a quantitative evaluation of long-term safety; one of a key aspect is uncertainty management. This paper presents the basic strategies for NUMO's long-term safety assessment based on the above policy. In concrete terms, the common procedures involved in safety assessment are applied in a stepwise manner, based on integration of knowledge obtained from site investigations/evaluations and engineered measures. The results of the safety assessment are then reflected in the planning of site investigations and engineered

Implementation of the safety culture for HANARO safety management

Energy Technology Data Exchange (ETDEWEB)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2008-11-15

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose.

Implementation of the safety culture for HANARO safety management

International Nuclear Information System (INIS)

Wu, Jong Sup; Han, Gee Yang; Kim, Ik Soo

2008-01-01

Safety is the fundamental principal upon which a management system is based. The IAEA INSAG(International Nuclear Safety Group) states the general aims of a safety management system. One of which is to foster and support a strong safety culture through the development and reinforcement of good safety attitudes and behavior in individuals and teams, so as to allow them to carry out their tasks safety. The safety culture activities have been implemented and the importance of a safety management in nuclear activities for a reactor application and utilization has also been emphasized for more than 10 years in HANARO which is a 30 MW multi purpose research reactor that achieved its first criticality in February 1995. The safety culture activities and implementation have been conducted continuously to enhance its safe operation such as the seminars and lectures related to safety matters, participation in international workshops and the development of safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture indicators, a survey on the attitude of HANARO staff toward the safety culture, the development of operational safety performance indicators (SPIs), the preparation of a safety text book and the development of an e Learning program for a safety education purpose

Statutory Instrument No. 2056, The Nuclear Installations Act 1965 etc. (Repeals and Modifications) Regulations 1974

International Nuclear Information System (INIS)

1975-01-01

These Regulations contain repeals and modifications of provisions of the Nuclear Installations Act 1965 and a modification of the Nuclear Installations (Dangerous Occurrences) Regulations 1965. They are made in consequence of the establishment on 1st January 1975 of the Health and Safety Executive and the coming into operation on that date of provisions of the Health and Safety at Work etc. Act 1974 which supersede or affect provisions of the 1965 Act and the 1965 Regulations. (NEA) [fr

Food safety and the reversed political consumer

DEFF Research Database (Denmark)

Christensen, Tove; Denver, Sigrid; Mørkbak, Morten Raun

We address the question of whether people act as political consumers in relation to food safety. By linking evidence from economic valuation studies on consumers' willingness to pay with sociological studies on consumer behaviour and market studies, we find that food safety does not call...

78 FR 40396 - Safety Zone; America's Cup Safety Zone and No Loitering Area, San Francisco, CA

Science.gov (United States)

2013-07-05

...-AA00 Safety Zone; America's Cup Safety Zone and No Loitering Area, San Francisco, CA AGENCY: Coast... America's Cup races. This safety zone and no loitering area are established to enhance the safety of spectators and mariners near the north east corner of the America's Cup regulated area. All persons or...

Meeting the maglev system's safety requirements

Energy Technology Data Exchange (ETDEWEB)

Pierick, K

1983-12-01

The author shows how the safety requirements of the maglev track system derive from the general legal conditions for the safety of tracked transport. It is described how their compliance beyond the so-called ''development-accompanying'' and ''acceptance-preparatory'' safety work can be assured for the Transrapid test layout (TVE) now building in Emsland and also for later application as public transport system in Germany within the meaning of the General Railway Act.

The need to optimize inservice testing and inspection to enhance safety

International Nuclear Information System (INIS)

Perry, J.A.

1996-01-01

Welcome to the Fourth U.S. Nuclear Regulatory Commission and American Society of Mechanical Engineers (USNRC/ASME) Symposium on Valve and Pump Testing in Nuclear Power Plants. This symposium provides a forum to exchange information on technical and regulatory issues associated with the testing of valves and pumps used in nuclear power plants. Progress made since the last symposium will be discussed along with various methods for in service testing of valves and pumps. Active participation by industry representatives, regulators and consultants will entail discussion of a broad array of ideas and points of view regarding how to improve the in service testing of valves and pumps at nuclear power plants. One of the challenges faced is the need to optimize the in service testing and inspection to enhance safety, operability and reliability. The author addresses this challenge from an ASME Nuclear Codes and Standards point of view

The need to optimize inservice testing and inspection to enhance safety

Energy Technology Data Exchange (ETDEWEB)

Perry, J.A.

1996-12-01

Welcome to the Fourth U.S. Nuclear Regulatory Commission and American Society of Mechanical Engineers (USNRC/ASME) Symposium on Valve and Pump Testing in Nuclear Power Plants. This symposium provides a forum to exchange information on technical and regulatory issues associated with the testing of valves and pumps used in nuclear power plants. Progress made since the last symposium will be discussed along with various methods for in service testing of valves and pumps. Active participation by industry representatives, regulators and consultants will entail discussion of a broad array of ideas and points of view regarding how to improve the in service testing of valves and pumps at nuclear power plants. One of the challenges faced is the need to optimize the in service testing and inspection to enhance safety, operability and reliability. The author addresses this challenge from an ASME Nuclear Codes and Standards point of view.

Safety shutdown separators

Science.gov (United States)

Carlson, Steven Allen; Anakor, Ifenna Kingsley; Farrell, Greg Robert

2015-06-30

The present invention pertains to electrochemical cells which comprise (a) an anode; (b) a cathode; (c) a solid porous separator, such as a polyolefin, xerogel, or inorganic oxide separator; and (d) a nonaqueous electrolyte, wherein the separator comprises a porous membrane having a microporous coating comprising polymer particles which have not coalesced to form a continuous film. This microporous coating on the separator acts as a safety shutdown layer that rapidly increases the internal resistivity and shuts the cell down upon heating to an elevated temperature, such as 110.degree. C. Also provided are methods for increasing the safety of an electrochemical cell by utilizing such separators with a safety shutdown layer.

RBMK safety issues

International Nuclear Information System (INIS)

Weber, J.P.; Reichenbach, D.; Tscherkashow, J.M.

1995-01-01

On the basis of information and documents from the RBMK operation countries, the Western consortium mainly examined the two most modern plants, Ignalin-2 and Smolensk-3. The identification of numerous shortcomings, some of which had already been recongized by the participating Eastern organizations, resulted in some 300 specific recommendations to reactor designers, operators and licensing authorities. These recommendations are to be acted upon at once; only a small number did not meet with the approval of the Eastern partners. The safety review provided the Western consotrium with a profound insight into the design and safety of third-generation RBMK reactors; the Eastern partners were able to accumulate experience in working with Western safety philosophy. (orig.) [de

48 CFR 923.7002 - Worker safety and health.

Science.gov (United States)

2010-10-01

... Information and Protection of Worker Safety and Health” or “952.223-77, Conditional Payment of Fee or Profit—Protection of Worker Safety and Health” implement the requirements of section 234C of the Atomic Energy Act... 48 Federal Acquisition Regulations System 5 2010-10-01 2010-10-01 false Worker safety and health...

Occupational Safety and Health Programs in Career Education.

Science.gov (United States)

DiCarlo, Robert D.; And Others

This resource guide was developed in response to the Occupational Safety and Health Act of 1970 and is intended to assist teachers in implementing courses in occupational safety and health as part of a career education program. The material is a synthesis of films, programed instruction, slides and narration, case studies, safety pamphlets,…

Safety assessment, safety performance indicators at the Paks Nuclear Power Plant

International Nuclear Information System (INIS)

Baji, C.; Vamos, G.; Toth, J.

2001-01-01

The Paks Nuclear Power Plant has been using different methods of safety assessment (event analysis, self-assessment, probabilistic safety analysis), including performance indicators characterizing both operational and safety performance since the early years of operation of the plant. Regarding the safety performance, the indicators include safety system performance, number of scrams, release of radioactive materials, number of safety significant events, industrial safety indicator, etc. The Paks NPP also reports a set of ten indicators to WANO Performance Indicator Programme which, among others, include safety related indicators as well. However, a more systematic approach to structuring and trending safety indicators is needed so that they can contribute to the enhancement of the operational safety. A more comprehensive set of indicators and a systematic evaluation process was introduced in 1996. The performance indicators framework proposed by the IAEA was adapted to Paks in this year to further improve the process. Safety culture assessment and characterizing safety culture is part of the assessment process. (author)

S. 1304: DOE Nuclear Safety and Environment Act. Introduced in the Senate of the United States, One Hundred First Congress, First Session, July 12, 1989

International Nuclear Information System (INIS)

Anon.

1989-01-01

A bill was introduced to enhance nuclear safety at Department of Energy nuclear facilities, to modify certain functions of the Defense Nuclear Facilities Safety Board, to apply the provisions of OSHA to certain Department of Energy nuclear facilities, to clarify the jurisdiction and powers of Government agencies dealing with nuclear wastes, to ensure independent research on the effects of radiation on human beings, to encourage a process of environmental compliance and cleanup at these facilities, and to protect communities that contain these facilities

Safety performance evaluation using proactive indicators in a selected industry

Directory of Open Access Journals (Sweden)

Abolfazl Barkhordari

2015-03-01

Full Text Available Background & Objectives: Quality and effectiveness of safety systems are critical factors in achieving their goals. This study was aimed to represent a method for performance evaluation of safety systems by proactive indicators using different updated models in the field of safety which will be tested in a selected industry. Methods: This study is a cross-sectional study. Proactive indicators used in this study were: Unsafe acts rate, Safety Climate, Accident Proneness, and Near-miss incident rate. The number of in 1473 safety climate questionnaires and 543 Accident Proneness questionnaires was completed. Results: The minimum and maximum safety climate score were 56.88 and 58.2, respectively, and the minimum and maximum scores of Accident Proneness were 98.2 and 140.7, respectively. The maximum number of Near-miss incident rate were 408 and the minimum of that was 196. The maximum number of unsafe acts rate was 43.8 percent and the minimum of that was 27.2 percent. In nine dimensions of Safety climate the eighth dimension (personal perception of risk with the score of 4.07 has the lowest score and the fourth (laws and safety regulations dimension with 8.05 has the highest score. According to expert opinions, the most important indicator in the assessment of safety performance was unsafe acts rate, while near-miss incident rate was the least important one. Conclusion: The results of this survey reveal that using proactive (Prospective indicators could be an appropriate method in organizations safety performance evaluation.

16 CFR 1500.129 - Substances named in the Federal Caustic Poison Act.

Science.gov (United States)

2010-01-01

... Poison Act. 1500.129 Section 1500.129 Commercial Practices CONSUMER PRODUCT SAFETY COMMISSION FEDERAL... REGULATIONS § 1500.129 Substances named in the Federal Caustic Poison Act. The Commission finds that for those substances covered by the Federal Caustic Poison Act (44 Stat. 1406), the requirements of section 2(p)(1) of...

Nuclear Activities (Prohibitions) Act 1983

International Nuclear Information System (INIS)

1983-01-01

The purpose of this Act is to protect the health and safety of the people of Victoria and its environment by prohibiting nuclear activities from being carried out and regulating the possession of certain nuclear material in a manner consistent with assisting Australia in meeting its international nuclear non-proliferation objectives. (NEA) [fr

Fundamental Consumer Rights Under the Consumer Protection Act 68 of 2008: A Critical Overview and Analysis

Directory of Open Access Journals (Sweden)

R van Niekerk

2010-12-01

Full Text Available South Africa was in need of a comprehensive framework of legislation, policies and government authorities to regulate consumer-supplier interaction. The Consumer Protection Act 68 of 2008, which was signed by the President of the Republic of South Africa on 29 April 2009 and published in the Government Gazette on 29 April 2009, now provides an extensive framework for consumer protection and aims to develop, enhance and protect the rights of consumers and to eliminate unethical suppliers and improper business practices. Certain areas of the common law regarding consumer rights have been codified by the Act and certain unfair business practices that were previously unregulated are now governed by the Act. The Act has a wide field of application. It applies to every transaction occurring within South Africa for the supply of goods or services or the promotion of goods or services and the goods or services themselves, unless the transaction is exempted from the application of the Act. The Act also specifically regulates aspects of franchise agreements. In terms of the Act, consumers obtain several new rights and some existing rights are broadened and reinforced. These rights are: the right to equality in the consumer market; privacy; choice; disclosure and information; fair and responsible marketing; fair and honest dealing; fair, just and reasonable terms and conditions; and fair value, good quality and safety. The last right in terms of the Act deals with a supplier's accountability to consumers. The authors critically analyse and discuss these rights. It is clear that the Act is written in favour of the consumer.

Nuclear liability and the Price--Anderson Act

International Nuclear Information System (INIS)

Wilson, R.

1977-01-01

The Price-Anderson Act is viewed as meeting public needs in a unique and responsible way, reflecting the far-sightedness of those involved in the early development of nuclear power who saw the importance of building safety into each step of the program. An extension of the Act is advised as a first step in recognizing that many potential and real disasters (e.g., dam breaks, floods, etc.) are man-made rather than ''Acts of God''. Rather than abolish the Price-Anderson Act because it is unique, the case is made for extending it to cover these other situations. Provisions of the Act are examined in terms of the role of negligence in nuclear accidents, and the conclusion is reached that public concern for reactor safety should not be affected. Limited assets on the part of insurers and insurance pools have made government involvement important but not a real subsidy because of high premiums. Premiums in the new amendment are paid retroactively when there is an accident, which relieves the problem of anticipating what premiums may be needed in the future. This limits government liability and, combined with the waiver of defenses against liability, offers better protection for the public. Recommendations for allowing tort law to operate above the $560 million Price-Anderson limits are criticized, and a counter proposal is made for reassessing the figure at an appropriate limit and extending insurance to competitive industries

Radiation Safety (Qualifications) Regulations 1980

International Nuclear Information System (INIS)

1980-01-01

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

Development of reliability-based safety enhancement technology; development of organization concept model in nuclear power plants